ML14275A333

Initial Exam 2014-301 Final RO Written Exam

ML14275A333
Person / Time
Site:	Robinson
Issue date:	09/23/2014
From:	Operator Licensing and Human Performance Branch
To:	Progress Energy Carolinas
References
50-261/14-301
Download: ML14275A333 (70)

Text

Name: _____________

___________________ ILC-14 RO NRC Exam

Form: 0 Version: 0

1. Given the following plant conditions:- The reactor has tripped due to a pressurizer steam space leak- Safety Injection has automatically initiatedWhich ONE(1) of the following completes the statement below?The MINIMUM values specified by EOP-E-0, REACTOR TRIP OR SAFETYINJECTION, to transition to EPP-7, SI TERMINATION, to terminate Safety Injectionare RCS pressure greater than (1)

PSIG and RCS subcooling based on coreexit TCs greater than (2) degrees F.(1) 1650(2) 30(1) 1650(2) 35(1) 1715(2) 30(1) 1715(2) 35 A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 1

ILC-14 RO NRC Exam

2. Given the following plant conditions:Initial conditions:- Reactor Power is 100%- Pressurizer level control and letdown is in a normal automatic alignment- Only Charging pump "B" is running and its speed controller is in AUTOCurrent conditions:- Pressurizer Safety Valve RC-551A, fails 100% open- RCS pressure is 2075 PSIG and lowering slowly- Reactor will NOT tripWhich ONE(1) of the following completes the statements below?

RC-551A's lift set point is (1) psig. Based on current plant conditions, long term, LC-459G, MASTER PRESSURIZERLEVEL CONTROLLER, demand signal will (2)

.(1) 2335(2) lower(1) 2335(2) rise(1) 2485(2) lower(1) 2485(2) rise A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 2

ILC-14 RO NRC Exam

3. Given the following plant conditions:- The unit was initially at 100% power- A LOCA has occurred

- RCS pressure is 1300 psig and lowering

- Tave is 548 F

- Containment pressure peaked at 4.2 psig

- The crew is performing actions of EPP-8, Post LOCA Cooldown andDepressurizationAs directed by EPP-8 which one of the following identifies the method that will be usedto initiate cooldown of the RCS?Initiate cooldown using the...steam dumps at the maximum achievable ratesteam dumps at no greater than 100°F/hr in the last 60 minutessteam line PORVs at the maximum achievable ratesteam line PORVs at no greater than 100°/hr in the la st 60 minutes A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 3

ILC-14 RO NRC Exam

4. Given the following plant conditions:- Unit 2 has suffered a LBLOCA- Restoration efforts are in progress with the following plant conditions:- Core Exit Thermocouples are currently reading 720 o F- Full Range RVLIS is 45%- CV Pressure is currently 11 psig

- CV Sump Level is 350 inches and rising- CV Radiation Levels are > 5 R/hr- CV Spray Pumps "A" & "B" have trippedFRP-C.1, Response to Inadequate Core CoolingFRP-C.2, Response to Degraded Core Cooling

FRP-J.1, Response to High Containment PressureFRP-J.2, Response to Containment FloodingWhich ONE(1) of the following completes the statements below?

Based on the indications above, which Function Restoration Procedures(FRP's) havemet entry criteria IAW Critical Safety Function Status Trees(CSFST's):FRP-C.1 and FRP-J.1FRP-C.1 and FRP-J.2FRP-C.2 and FRP-J.1FRP-C.2 and FRP-J.2 A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 4

ILC-14 RO NRC Exam

5. Given the following plant conditions:- The plant is at 100% power- At 0200 the Reactor Operator determined that Seal Injection flow was lost toRCP 'A'- The following RCP "A" conditions existed at that time 0205:Pump Bearing

1. 1 Seal Leakoff Temperature

Shaft Vibrations

Temperature 166ºF 15.2 Mils 148ºF- It is now 0215 and the following RCP "A" conditions exist:Pump Bearing

1. 1 Seal Leakoff Temperature

Shaft Vibrations

Temperature 231ºF 15.3 Mils 222ºFWhich ONE(1) of the following completes the statement below?

IAW AOP-018, REACTOR COOLANT PUMP ABNORMAL CONDITIONS, the RCP

.operation may continue. There are no parameters requiring immediate RCPshutdown.must be shut down due to pump bearing temperature exceeding operating limits.must be shut down due to pump shaft vibration exceeding operating limits.must be shut down due to #1 seal leakoff temperature exceeding operating limits.

A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 5

ILC-14 RO NRC Exam

6. Given the following plant conditions:- Shutdown with the RHR System aligned for core cooling- RCS level is at (-) 69 inches and stable as read on LI-403 and LI-404- Steam Generator Primary Manway removal in progress- The "A" RHR pump is running- RHR System total flow is oscillating from 2800 to 3500 gpm- "A" RHR pump discharge pressure is oscillating

- RHR HX LO FLOW annuncia tor, APP-001-A7 alarmingBased on the above conditions, with of the following identifies the FIRST correct actionto mitigate the events as directed by AOP-020, LOSS OF RESIDUAL HEATREMOVAL. Raise RCS LevelReduce RHR flowStop the "A" RHR PumpStop the "B" RHR Pump A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 6

ILC-14 RO NRC Exam

7. Given the following plant conditions:The control room operating crew has entered FRP-C.2 "Response to Degraded CoreCooling" and the following plant conditions exist:- RCP "A" is running- RCP's "B" & "C" have been secured

- CCW flow to RCP "A" motor has just been lost- RCP "A" upper thrust bearing temperature has risen to 205 °FBased on the above conditions, which one of the following choices:(1) describes whether RCP "A" is required to be immediately secured?(2) the reason for either securing RCP "A" or allowing it to run?(1) RCP "A" is required to be immediately secured(2) bearing and motor damage could occur(1) RCP "A" is required to be immediately secured(2) RCP "A" could be pumping two-phase flow through the core(1) RCP "A" is NOT required to be immediately secured(2) PZR spray is being supplied by loop "A"(1) RCP "A" is NOT required to be immediately secured(2) RCP "A" is providing single or two-phase flow through the core A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 7

ILC-14 RO NRC Exam

8. Given the following plant conditions:- The plant is operating at 100% RTP- A failure of the pressurizer pressure Master Controller, PC-444J, results in actualpressure lowering to 2185 psig and continuing to lowerWhich ONE(1) of the following completes the statements below?

If PC-444J is placed in manual per the IMMEDIATE ACTIONS of AOP-019,Malfunction of RCS Pressure Control, the controller's

__ _(1) arrow would beinitially depressed to regain pressure control.If spray valve PCV-455A would not close and the reactor was tripped due to loweringpressure, then the minimum RCP(s) required to be secured per EOP-E-0, Reactor Tripor Safety Injection, to stop spray flow is/are RCP

___(2)____

.(1) down(2) "B" & "C"(1) down(2) "C"(1) up(2) "B" & "C"(1) up(2) "C" A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 8

ILC-14 RO NRC Exam

9. Given the following plant conditions:A primary system pipe break with a failure of the reactor to trip (ATWS) has resulted inthe following plant conditions:- Reactor Power is 12% and lowering- CV Pressure is 12 psig and risingWhich ONE(1) of the following completes the statements below?For the above conditions, FRP-S.1 "Response to Nuclear Power Generation/ATWS"states that RCP's ____(1)____ be tripped.Per FRP-S.1, if the Main Turbine is unable to be tripped, uncontrolled RCS cooldown isprevented by FIRST performing a ____(2)

____ .(1) should(2) Turbine runback(1) should(2) closure of all MSIV's(1) should NOT(2) Turbine runback(1) should NOT(2) closure of all MSIV's A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 9

ILC-14 RO NRC Exam

10. Given the following plant conditions:- The plant is at 100% RTP- The following Radiation Monitors go into alarm:- Condenser Air Ejector Gas Monitor, R-15

- Condensate Polisher Waste Effluent Monitor, R S/G Sample Radiation Monitor, R-19A- "A" Main Steam Line N-16 Detector, R-24AWhich ONE(1) of the following describes the correct response to the above givenconditions?Condensate Polishing Building Sump pumps TRIP.V1-31, Blowdown Isolation Valve to Catch Basin, CLOSES.FCV-1933A and B, S/G A Blowdown Sample Isolation Valves, CLOSE. Condensate Polishing Building Sump pumps TRIP.FCV-1933A and B, S/G A Blowdown Sample Isolation Valves, CLOSE. RCV-10549, Condensate Polisher Discharge to Storm Drains, CLOSES.V1-31, Blowdown Isolation Valve to Catch Basin, CLOSES.RCV-10549, Condensate Polisher Discharge to Storm Drains, CLOSES.

A.B.C.D.11. Given the following plant conditions:- All Steam Generators are faultedWhich ONE(1) of the following completes the statement below?

is the basis for a minimum of 80 gpm indicated AFW flow to each Steam Generator per EPP-16, UNCONTROLLED DEPRESSURIZATION OF ALL STEAMGENERATORS.Preventing Steam Generator dryoutPrevent water hammer in the feed ringsMeeting minimum heat sink flow requirementsEnsure the feed lines stay warm to prevent excessive thermal shock to the feedlines during recovery actions A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 10 ILC-14 RO NRC Exam

12. Given the following plant conditions:- The unit has entered EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, dueto a Safety Injection- Steam generator narrow range levels following the reactor trip lowered to andare currently

- S/G "A" is 16% and stable

- S/G "B" is 17% and stable

- S/G "C" is 17% and stable- Operators are currently performing the step in EOP-E-0 that says "Check AFWPumps- RUNNING"Which ONE(1) of the following completes the statement below?

The SDAFW pump is (1)

. IAW with EOP-E-0, the crew will (2)

.(1) OFF(2) manually start the SDAFW pump(1) OFF(2) check AFW header section valves FULL OPEN(1) ON(2) manually stop the SDAFW pump(1) ON(2) check SDAFW pump discharge valves FULL OPEN A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 11 ILC-14 RO NRC Exam

13. Given the following plant conditions:- A cool down of <100°F/hr is in progress per EPP-1, Loss of All AC, using SteamLine PORVsWhich ONE(1) of the following completes the statements below?IAW EPP-1, the crew will depressurize intact S/G's to (1) psig. During thedepressurization, the crew will check RCS Cold Leg Temperatures greater than

(2)

°F.(1) 140(2) 355(1) 140 (2) 290(1) 240(2) 355(1) 240(2) 290 A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 12 ILC-14 RO NRC Exam

14. Given the following plant conditions:Initial Conditions:- Unit 2 was at 100% power- A Loss of all Offsite Power (LOOP) has occurred

- Operators entered EPP-5, NATURAL CIRCULATION COOLDOWNCurrent Conditions:- Emergency Diesel Generators continue to operate normally

- Operators have just completed the step in EPP-5 to check cool down rate required -GREATER THAN limits, and have determined that a transition toEPP-6, NATURAL CIRCULATION COOL DOWN WITH STEAM VOID INVESSEL, is not required- CRDM Cooling Fan HVH-5A is running

- CRDM Cooling Fan HVH-5B is NOT runningWhich ONE(1) of the following completes the statement below?IAW EPP-5, the MINIMUM value for subcooling is (1)

o F and you must cooldown less than (2)

oF/hr to preclude formation of a steam void in the vesselupper head.(1) 55(2) 10(1) 100(2) 10(1) 55 (2) 25(1) 100(2) 25 A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 13 ILC-14 RO NRC Exam

15. Given the following plant conditions:- Unit was at 100% power- Loss of a Vital Instrument Bus occurred- The control room crew has just completed the Immediate Actions of AOP-024,LOSS OF INSTRUMENT BUSThe Immediate Action, "Place the Main Turbine in Manual," is procedurally directed tobe performed for loss of ANY Instrument Bus, without taking time at that point todiagnose which bus was lost.Which ONE(1) of the following completes the statements below?The BASIS for the action is to mitigate the effects of a loss of Instrument Bus (1)

.This is because a continuous turbine Load Reference runback would occur if theturbine were in Automatic, making an automatic reactor trip unavoidable because all (2)

.(1) 1(2) Pressurizer spray valve control is lost (1) 1(2) Feedwater Regulating Valve M/A stations are lost(1) 4(2) Pressurizer spray valve control is lost(1) 4(2) Feedwater Regulating Valve M/A stations are lost A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 14 ILC-14 RO NRC Exam

16. Given the following plant conditions:- Plant is at 35% RTP- APP-002-E7 (INST AIR COMP D TRIP) in alarm- APP-002-F7 (INST AIR HDR LO PRESS) in alarm

- AOP-017 (LOSS OF INSTRUMENT AIR) is in progress- Station Air and Instrument Air have been cross-connected- Transition has been made to AOP-017; Section A (Modes 1 AND 2)

- Instrument Air pressure is 63 psig- "B" and "C" S/Gs Levels are at 41% and slowly loweringWhich ONE(1) of the following completes the statment below?

The operating crew is required to_____ while continuing in AOP-017.dispatch operator(s) to cross-connect Station Air and Construction Airtrip the reactor and Go to EOP-E-0 (Reactor Trip Or Safety Injection)trip the turbine and implement AOP-007 (Turbine Trip below P-8)lower turbine load as necessary to maintain feed and steam flows matched A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 15 ILC-14 RO NRC Exam

17. Which ONE(1) of the following completes the statements below?In accordance with EPP-20, LOCA OUTSIDE CONTAINMENT:The FIRST flowpath to be isolated from the RCS when attempting to isolate an RCSleak outside containment will be associated with (1)

.The RCS parameters to be monitored to confirm that the RCS leak has or has NOTbeen isolated is (2)

.(1) RHR(2) RCS Pressure(1) RHR(2) PZR Level(1) RCP Seal Return(2) RCS Pressure(1) RCP Seal Return(2) PZR Level A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 16 ILC-14 RO NRC Exam

18. Given the following plant conditions:- A reactor trip has occurred due to a trip of both Main Feed Pumps - The following conditions exist:- The crew has recently entered FRP-H.1, RESPONSE TO LOSS OFSECONDARY HEAT SINK, after completion of immediate actions ofEOP-E-0, REACTOR TRIP OR SAFETY INJECTION- The BOP operator notes the following annunciators are lit:- APP-007-F1, AFW PMP A LO DISCH PRESS/MTR TRIP- APP-007-F2, AFW PMP B LO DISCH PRESS/MTR TRIP

- APP-007-F5, SDAFW PMP LO DISCH PRESS TRIP- SG wide range levels are: A: 8 % B: 15 % C: 16 %- All SG pressures are 1035 psig

- RCS pressure is 2300 psig- CST level is 5% and lowering due to sabotage and is INACCESSIBLE- Condensate System is AVAILABLEOP-402, AUXILIARY FEEDWATER SYSTEMAttachment 2 of FRP-H.1, SW BACKUP TO MDAFW PUMPSWhich ONE(1) of the following completes the statements below?In accordance with FRP-H.1, based on the CST concerns, Service Water backupsupply is required to be aligned to both (1)

.After action has been taken to address the CST concerns, for the given conditions, theNEXT major action taken to restore heat sink IAW FRP-H.1 is to (2)

.(1) MDAFW pumps AND SDAFW pump IAW OP-402(2) initiate RCS Bleed and Feed(1) MDAFW pumps ONLY IAW Attachment 2 of FRP-H.1(2) initiate RCS Bleed and Feed(1) MDAFW pumps AND SDAFW pump IAW OP-402(2) attempt to establish Main Feedwater flow(1) MDAFW pumps ONLY IAW Attachment 2 of FRP-H.1(2) attempt to establish Main Feedwater flow A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 17 ILC-14 RO NRC Exam

19. The plant is at 100% power when the requirements of LCO 3.2.4, QPTR, are notsatisfied.Which ONE(1) of the following completes the statements below?The maximum power level at which the LCO will no longer apply is (1)

%. Thereason for the power level stated in the LCO applicability statement is to (2)

.(1) 15(2) prevent unanalyzed xenon effects on power distribution during subsequentpower increases(1) 15(2) achieve a condition where the Quadrant Power Distribution is no longer asignificant concern to safety analyses(1) 50(2) prevent unanalyzed xenon effects on power distribution during subsequentpower increases(1) 50(2) achieve a condition where the Quadrant Power Distribution is no longer asignificant concern to safety analyses A.B.C.D.Tuesday, September 23, 2014 11:14:20 AM 18 ILC-14 RO NRC Exam

20. Given the following plant conditions:- Turbine load was reduced from 95 to 90% to support scheduled maintenance. - Control Bank D was inserted from 210 to 197 steps during the load reduction foraxial flux control. - At 90% power, the Reactor Operator immediately reports that two of the ControlBank D rods, D-8 and H-8, IRPI(s) remain at 210 steps and did not appear tomove.- APP-005-E2, ROD CONT SYSTEM URGENT FAILURE - NOT illuminated- All Power Range NI's indicate 90%Which ONE(1) of the following completes the statements below?In accordance with AOP-001, Malfunction of Reactor Control System, UNTIL theproblem is determined to be either an IRPI indicator(s) issue or actual stuck rods, Tavemay be maintained on program using (1)

.SUBSEQUENTLY, I&C Maintenance and Reactor Engineering support determined thatthe problem with D-8 was an IRPI indication problem and only H-8 is misaligned. All Lift Coil Disconnect Switches for Control Bank D rods except H-8 (2) beplaced in the OFF position to support rod realignment per AOP-001, Section B.(1) Turbine load adjustment(2) will(1) Turbine load adjustment(2) will NOT(1) Control Bank D(2) will(1) Control Bank D(2) will NOT A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 19 ILC-14 RO NRC Exam

21. Given the following plant conditions:Initial conditions:- Unit 2 was at 100% power- A manual reactor trip was unsuccessfully attempted due to a FeedwaterController malfunction- The crew has entered FRP-S.1, RESPONSE TO NUCLEAR POWERGENERATION/ATWSCurrent Conditions:- Operators have just reached the step in FRP-S.1 to initiate Emergency BorationWhich ONE(1) of the following completes the statements below?To maximize borated water flow to the RCS, FRP-S.1 states that the HIC-121potentiometer, "Charging Controller - DEMAND SIGNAL" is to be established at ____(1)____

%.Per FRP-S.1,

____(2)____ is the preferred, highest Boration rate, Charging Pump supply source.MOV-350, BA TO CHARGING PMP SUCTCVC-358, RWST TO CHARGING PUMP SUCTION(1) 0(2) MOV-350(1) 0(2) CVC-358(1) 100(2) MOV-350(1) 100(2) CVC-358 A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 20 ILC-14 RO NRC Exam

22. Given the following plant conditions:- The plant is operating at 100% RTP- 'A' Charging Pump is in Auto and its speed is lowering

- Pressurizer Backup Group 'A' heaters are in AUTO and have energized- Backup Group 'B' heaters are in ONWhich ONE(1) of the following completes the statements below?Based on these indications, the reference leg for (1) is leaking. With no operatoraction, a letdown isolation signal will eventually occur. Following the isolation, BackupGroup 'B' heaters will be (2)

.(1) LT-459(2) energized(1) LT-460(2) energized(1) LT-459(2) de-energized(1) LT-460(2) de-energized A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 21 ILC-14 RO NRC Exam

23. Given the following plant conditions:- 0800 The reactor is shut down in Mode 6 and refueling of the core is in progress. All Source Range Nuclear Instrument channels and Post Accident MonitorSource Range channels are operable.

Audio count rate is operable andselected to N-32.- 0810 Source Range Nuclear Instrument channel N-31 power supply failurecauses detector supply voltage to slowly lower by approximately 200 volts.- 0820 N-31 power supply output is 0 volts and N-31 has been declaredinoperable.Which ONE(1) of the following completes the statements below?

At 0810 Control room indication of N-31 will be (1) as compared to N-32.At 0825 the crew commences the required logging associated with PAMinstrumentation.At 0830 In accordance with Tech Spec 3.9.2, core alterations (2) continue.(1) the same(2) may(1) the same(2) may NOT(1) lower(2) may(1) lower(2) may NOT A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 22 ILC-14 RO NRC Exam

24. Given the following plant conditions:- Power ascension is in progress during a plant startup with the following powerrange nuclear instrument readings:- N-41 = 10.5%- N-42 = 10.5%

- N-43 = 9.0%

- N-44 = 9.5%- Intermediate range nuclear instrument (N-35) has been declared inoperable dueto a loss of its compensating voltage.- Per APP-005, the CRS has directed you to bypass N-35 in accordance withOWP-001, NUCLEAR INSTRUMENTATION.- You have just placed the intermediate range level trip switch for N-35 in theBYPASS position.Given the above plant conditions, which one of the following describes the status ofLCO 3.3.1, RPS ISNTRUMENTATION, for the Intermediate Range Neutron FluxFunction AND the actions (if any) that are needed to comply with LCO 3.3.1?3.3.1 is NOT applicable because power is >P-103.3.1 is NOT applicable because power is >P-6 but <P-103.3.1 is applicable, power must be lowered <P-63.3.1 is applicable, raise thermal power >P-10 A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 23 ILC-14 RO NRC Exam

25. Given the following plant conditions:- Unit 2 is at 100% power- Control Room Air Cleaning Fan, HVE-19A, is tagged out for scheduled motorinspection- A valid high radiation alarm on R-1 occursWhich ONE(1) of the following completes the statement below?Control room exhaust fan, HVE-16, is shutdown (1) and Aux Building SupplyFan, HVS-1 (2) required to be shutdown.(1) automatically(2) is(1) automatically(2) is NOT(1) manually(2) is(1) manually(2) is NOT A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 24 ILC-14 RO NRC Exam

26. Given the following plant conditions:- Unit 2 is currently operating at 100% RTP- A fire has been reported in a LHRAWhich ONE(1) of the following completes the statement below?

IAW FP-001, FIRE EMERGENCY, prior to authorizing entry into this fire area, aRadiological Controls (RC) brief

____(1)____ required and an RC Technician

____(2)____ required to enter the area with the Fire Brigade.(1) is still(2) is(1) is NOT(2) is(1) is still(2) is NOT(1) is NOT(2) is NOT A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 25 ILC-14 RO NRC Exam

27. Given the following plant conditions:- A loss of off-site power occurred 15 minutes ago- The crew is performing EOP-ES-0.1, Reactor Trip Response- The BOP is verifying Natural Circulation in accordance with ES-0.1 Attachment1, Natural Circulation Verification:- RCS pressure is 1800 psig and stable

- SG pressures are all 1000 lowering- RCS Thot is 586 oF and trending down- RCS Tcold is 547 oF and trending down- Core Exit Thermocouple temperature is 591 oF and trending downWhich ONE(1) of the following completes the statement below?The Natural Circulation criteria in Attachment 1 (1) met. Over the next 60minutes, RCS Core Delta T will (2)

.(1) are(2) lower(1) are(2) rise(1) are NOT(2) lower(1) are NOT(2) rise A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 26 ILC-14 RO NRC Exam

28. Given the following plant conditions:- Unit 2 was at 35% power, End of Life (EOL) following 300 days of continuousoperation- A bus fault has resulted in loss of 4kV Bus 4Which ONE(1) of the following completes the statement below?

Based on the current conditions, RCP B has tripped on

____(1)____ .Two minutes following the loss of RCP B, SG B steam flow is

____(2)____

than SG's"A" and "C".(1) under-frequency(2) higher(1) under-frequency(2) lower(1) under-voltage(2) higher(1) under-voltage(2) lower A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 27 ILC-14 RO NRC Exam

29. Given the following plant conditions:- The following sequence of events has occurred on Unit 2:- 0900: CVC-381, "RCP Seal Return Isolation" is closed and cannot bere-opened- 0903: Receipt of annunciator APP-001-C1, "RCP THERM BAR COOL WTRHI FLOW"- 0904: Receipt of annunciator APP-001-D1, "RCP THERM BAR COOL WTRLO FLOW"- 0905: Unit 2 is at 70% RTPWhich ONE(1) of the following completes the statement below?Based on these conditions, a #1 seal return flow-path is still available to the ___(1)___ . AOP-014 (2) state that the RCP should be secured within 24hours.Reactor Coolant Drain Tank (RCDT)Pressurizer Relief Tank (PRT)(1) RCDT(2) is(1) PRT(2) is(1) RCDT(2) is NOT(1) PRT(2) is NOT A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 28 ILC-14 RO NRC Exam

30. Given the following plant conditions:- The plant is operating at 100% power with CVCS in its normal letdown alignmentwhen the Letdown Temperature element (TE-144) fails upscale.- Pressurizer Pressure Control is in MANUAL- Rod Control is in MANUALWhich ONE(1) of the following completes the statement below?Based on the conditions above, VCT/Demineralizer Diversion Valve (TCV-143, NONGEN HX OUTLET TEMP) will

___(1)___ and RCS temperature and pressure will ___(2)___.(1) bypass the demineralizers(2) remain unchanged(1) bypass the demineralizers(2) lower(1) maintain its current position(2) rise(1) maintain its current position(2) lower A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 29 ILC-14 RO NRC Exam

31. Given the following plant conditions:- A Large Break LOCA and Loss of Offsite Power have occurred- EDG B tripped while starting- RWST level is 9%

- Alignment to the CV Sump has been completed- CV Pressure is currently 12 psigWhich ONE(1) of the following completes the statement below?

SI-844A and B, CV Spray Pump Suction Isolation Valves, will be (1)

. RHR Pump A (2)

capable of supplying suction to CV Spray Pump B.(1) closed(2) IS(1) closed(2) IS NOT(1) open(2) IS (1) open(2) IS NOT A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 30 ILC-14 RO NRC Exam

32. Given the following plant conditions:- Plant startup activities following a refueling outage are in progress- The Pressurizer is solid- RCP "A" is running

- PCV-145, LOW PRESSURE LETDOWN VALVE, has been placed in MANUAL- GP-002, COLD SHUTDOWN TO HOT SUBCRITICAL AT NO LOAD TAVG,Section 8.2 (Instructions for Plant Heatup up to 199ºF) is in progress- RCS temperature is 143º F and risingHCV-758, RHR HX DISCH FLOWFCV-605, RHR HX BYPASS VALVEWhich ONE(1) of the following completes the statement below?As the RCS heats up the operators will adjust PCV-145 by pushing the (1) buttonto control RCS pressure. The operators will throttle (2) to control RCS heat uprate.(1) down(2) HCV-758(1) down(2) FCV-605(1) up(2) HCV-758(1) up(2) FCV-605 A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 31 ILC-14 RO NRC Exam

33. Given the following plant conditions:- The reactor is at 100% RTP- A CV Vacuum release is in progress- A Safety Injection signal is receivedPCV-1922 A/B, CONTAINMENT ISOLATION VALVE SEAL WATER (IVSW)RHR-744 A/B, LOOP DISCHARGE TO RCS ISOLATION VALVES V12-12/13, VACUUM RELIEF VALVES SI-867 A/B, BIT INJECTION TANK INLETSWhich of the following valves will NOT reposition automatically due the aboveconditions?PCV-1922 A/BV12-12/13SI-867 A/BRHR-744 A/B A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 32 ILC-14 RO NRC Exam

34. Given the following plant conditions:- The unit is at 100% power- APP-003-B3, PRT HI TEMP, is in alarm

- The station is addressing a gradual rising PRT temperature and level due to seatleakage on a pressurizer safety valve as a mitigating action until the unit isremoved from service for repairs.Which ONE(1) of the following completes the statement below?

In accordance with APP-003-B3, Pressurizer Relief Tank Control System, actions todrain the PRT and makeup with primary water

___(1)___ allowed to be performedsimultaneously.If the leaking pressurizer safety valve subsequently fails open, the PRT is protectedfrom exceeding its design pressure by rupture disks that operate at the minimumpressure of

___(2)____ psig.(1) are(2) 100(1) are(2) 120(1) are NOT (2) 100(1) are NOT (2) 120 A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 33 ILC-14 RO NRC Exam

35. Given the following plant conditions:- The plant is at 100% power, steady-state- The controller for TCV-144, NON-REGEN HX OUTLET TEMP CONTROLVALVE, has just been placed in MANUAL due to erratic operationSubsequently- A 60 gpm orifice is placed in service, replacing the 45 gpm orifice that had beenin service by itself- No adjustments have been made to TCV-144Which ONE(1) of the following completes the statements below?Reactor Coolant System temperature will (1) due to reactivity effects. If letdowntemperature continues to rise, TCV-143, VCT/DEMIN DIVERSION, will divert letdown flow to the VCT at (2)

.(1) rise(2) 130º F(1) rise(2) 135º F(1) lower(2) 130º F(1) lower(2) 135º F A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 34 ILC-14 RO NRC Exam

36. Given the following plant conditions:- Unit is in Mode 2- The crew is performing actions of AOP-014, Component Cooling Water System Malfunction, Section D, due to low CCW System flow and rising temperatureWhich ONE(1) of the following completes the statement below?Any Reactor Coolant Pump whose (1) bearing temperature exceeds (2) must be stopped.(1) motor(2) 185º F(1) pump(2) 185º F(1) motor(2) 200º F(1) pump(2) 200º F A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 35 ILC-14 RO NRC Exam

37. Given the following plant conditions:- The plant is operating at 100% power - Charging pump "A" is running in AUTO- Charging pump "B" is running in MAN at 20% demand- Pressurizer level control switch, LM-459 is selected to NORM- Pressurizer Backup Heater "A" Switch is ON- All other control systems are in AUTOSubsequently:- Pressurizer level transmitter, LT-460, fails downscaleWhich ONE(1) of the following completes the statements below?

Charging Pump "A" speed will (1) and APP-003-B7, PZR PROT LO LEVEL (2) illuminate.(1) rise(2) will(1) lower(2) will(1) rise(2) will NOT(1) lower(2) will NOT A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 36 ILC-14 RO NRC Exam

38. Given the following plant conditions:- MST-021, "Reactor Protection Logic Train "B" at Power", is currently in progresswith the following configuration:- "A" Trip Breaker is racked in and closed- "A" Bypass Breaker is racked out

- "B" Trip Breaker is racked in and open- "B" Bypass Breaker is racked in and closed- The Unit CRS has determined that conditions requiring a Manual Trip have beenmet. Upon actuation of BOTH RTGB Manual Trip Pushbuttons by the OAC, thereactor has failed to trip.- No AUTOMATIC trip setpoints have been reachedWhich ONE(1) of the following completes the statements below?Based on the above conditions, the "B" Bypass Breaker ____(1)

____ could havecontributed to the failure of the reactor to TRIP. The crew ____(2)____ required toenter EOP-E-0, "Reactor Trip or Safety Injection".(1) Shunt Trip Coil(2) is(1) Under-voltage Coil(2) is(1) Shunt Trip Coil(2) is NOT(1) Under-voltage Coil(2) is NOT A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 37 ILC-14 RO NRC Exam

39. Given the following plant conditions:- Power is 100% RTP- Annunciator APP-009-B8, "480V NORM BUS OVLD" is received- Annunciator APP-009-E7, "480V GRD FAULT" is receivedSubsequently:- The Field AO reports that the following breakers have TRIPPED and are OPEN:- 52/15B, "MAIN BKR. 480V BUS 3"

- 52/14A, " 'B' ROD DRIVE MG"- In addition, the Field AO reports that the 480V Bus 3 "GROUND FAULT RELAYFLAG" has actuated.Which ONE(1) of the following completes the statement below?Based on the above conditions, receipt of annunciator APP-005-E6, "ROD CONT MGSETS TRIPPED" ____(1)____ expected. Upon the tripping of breaker 52/15B theground fault condition cleared. With no further operator action APP-009-E7 will____(2)____

extinguish.(1) is(2) Automatically(1) is (2) NOT(1) is NOT(2) Automatically(1) is NOT(2) NOT A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 38 ILC-14 RO NRC Exam

40. Given the following plant conditions:- The unit is operating at 100% power.- PZR Pressure channel PT-455, PZR PRESSURE PROTECTION CHANNEL I, isfailed, with all bistables in the TRIPPED condition.- A subsequent electrical fault results in loss of Instrument Bus 3.Which ONE(1) of the following completes the statement below?Which ONE (1) of the following describes the impact that the loss of Instrument Bus 3has on the plant? A reactor trip occurs, ________.

but NO Sl occursand an SI occurs, but ONLY Train 'A' Engineered Safeguards loads areautomatically started by the sequencersand an Sl occurs, but ONLY Train 'B' Engineered Safeguards loads areautomatically started by the sequencersand an Sl occurs, with BOTH trains of Engineered Safeguards loads automaticallystarted by the sequencers A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 39 ILC-14 RO NRC Exam

41. Given the following plant conditions:

0400:- The unit is at 100% RTP- Containment Air Recirculation Cooling units HVH-2, HVH-3, and HVH-4 are inoperation- Containment Air Recirculation Cooling unit HVH-1 has been stopped for breakermaintenance that will be performed on the next shift 0500:- A large break LOCA has occurred- SI has actuated 0510:- The SI signal has been resetWhich ONE(1) of the following completes the statement below?At 0515, the normal air inlet damper for HVH-1 is

__(1)__ and the status of HVH-2 fan is __(2)___ .(1) closed(2) off(1) closed(2) on(1) open(2) off(1) open (2) on A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 40 ILC-14 RO NRC Exam

42. Given the following plant conditions:- The unit tripped from 100% power with the following conditions:- The Crew is in EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT,with a Safety Injection in progress due to a Large Break LOCA- Containment pressure peaked at 15 psig and currently is 6 psig and loweringslowly-The following annunciators are in alarm:- APP-002-F2 SPRAY ADD TANK LO LEVEL

- APP-002-A3 RWST HI/LO LVL-Spray additive tank level is 10% and lowering slowlyWhich ONE(1) of the following completes the statement below?The operators will close CV spray additive tank discharge valves, SI-845A and SI-845B ___(1)____ and go to EPP-9, TRANSFER TO COLD LEG RECIRCULATION (2)

.(1) at this time(2) when alarm APP-002-B3 RWST LO-LO LVL actuates(1) at this time(2) at this time(1) when containment pressure is less than 4 psig(2) when alarm APP-002-B3 RWST LO-LO LVL actuates(1) when containment pressure is less than 4 psig(2) at this time A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 41 ILC-14 RO NRC Exam

43. Given the following plant conditions:- A loss of offsite power and a reactor trip has occurred- APP-007-F5, SD AFW PMP LO DISCH PRESS TRIP alarms and remains locked in- Two minutes later the pump has been verified to be coasting down locally due toan overspeed tripWhich ONE(1) of the following completes the statements below?SDAFW Pump Steam Shutoff Valves, V1-8A, V1-8B, and V1-8C should be (1) at this time. The BOP operator is required to (2) closure of SDAFW PumpDischarge Valves, V2-14A, V2-14B, and V2-14C.(1) open(2) verify automatic(1) open(2) perform manual(1) closed(2) verify automatic(1) closed(2) perform manual A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 42 ILC-14 RO NRC Exam

44. Given the following plant conditions:- Reactor power is at 62% RTP- S/G "C" water level is stable at 52%- FCV-498, "S/G 'C' FWRV" has been placed in local-handwheel control inaccordance with OP-403, "FEEDWATER SYSTEM" for level control circuit maintenance- Field personnel have reached OP-403 step 8.4.3.2.n, "INITIATE the requiredmaintenance activities."Subsequently:- I&C Maintenance reports that, locally, the FCV-498 Bailey Positioner has failedand is out-putting a max signalWhich ONE(1) of the following completes the statement below?

Based on the above conditions, FCV-498 ____(1)____ reposition.Should "MFP A" trip during the above conditions, AOP-010, "MAINFEEDWATER/CONDENSATE MALFUNCTION" will direct Operators to ____(2)____ .(1) will(2) perform a Reactor Trip(1) will(2) stabilize reactor power <60%(1) will NOT(2) perform a Reactor Trip(1) will NOT(2) stabilize reactor power <60%

A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 43 ILC-14 RO NRC Exam

45. Given the following plant conditions:- The CST has developed a leak- The reactor is in Mode 1; Mode 3 preparations are currently in progressWhich ONE(1) of the following completes the statement below?OP-402, "AUXILIARY FEEDWATER SYSTEM" states that once CST level is below___(1)___ %, the ___(2)___ Driven AFW pump(s) require(s) venting prior to use, if notalready in operation.(1) 10(2) Motor(1) 10 (2) Steam(1) 34(2) Motor(1) 34 (2) Steam A.B.C.D.46. Which ONE(1) of the following completes the statement below?Emergency Diesel Generator (EDG) amperage shall NOT exceed (1) amps, to prevent exceeding the current rating of the (2)

.(1) 3200(2) EDG output breaker(1) 3200(2) generator stator windings(1) 4000(2) EDG output breaker(1) 4000(2) generator stator windings A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 44 ILC-14 RO NRC Exam

47. Given the following plant conditions:- The plant is at 100% power, steady-state- A fault in the 230kV switchyard sends trip-open signals to generator outputbreakers 52/8 & 52/9- Breaker 52/8 fails to openWhich ONE(1) of the following completes the statement below?Generator lockout relay(s)

(1) will actuate directly from 52/8 failure to open (donot infer later signals that may actuate either or both lockout relays).Following the Fast Bus Transfer, if the lockout relay(s) is/are reset with the 52/8failure-to-open signal still present, (2)

.(1) 86P AND 86BU (2) one or more 4kV bus supply or tie breakers will reposition(1) 86P AND 86BU (2) there will be no effect on 4kV bus alignment(1) ONLY 86P(2) one or more 4kV bus supply or tie breakers will reposition (1) ONLY 86P(2) there will be no effect on 4kV bus alignment A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 45 ILC-14 RO NRC Exam

48. Given the following plant conditions:- A Loss of Offsite Power has occurred- BOTH EDGs have failed to auto start and cannot be manually started- EPP-1, LOSS OF ALL AC POWER, has been implementedWhich ONE(1) of the following completes the statement below?In accordance with EPP-1, low priority loads

__(1)___ required to be shed fromInstrument Buses 2 and 3 to minimize the discharge rate of station batteries.Assuming battery load remains constant, battery current will

__(2)__ as terminalvoltage lowers.(1) are(2) rise(1) are(2) lower(1) are NOT(2) rise(1) are NOT(2) lower A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 46 ILC-14 RO NRC Exam

49. Which ONE(1) of the following completes the statement below?EDG "A" auto started and loaded due to a Loss of Offsite Power. The DG speed control __ (1)_

aligned with 0% percent droop.Following the Blackout Sequencer loading, the 480 Emergency Bus E-1 frequencyindicates 58.9 Hz. With no additional action, the speed of DG "A" (2) be adjustedfrom the Generator Control Panel using the EDG "A" Speed Control Switch inaccordance with OP-604.(1) is(2) can(1) is(2) can NOT(1) is NOT(2) can(1) is NOT(2) can NOT A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 47 ILC-14 RO NRC Exam

50. Given the following plant conditions:- The unit has entered EPP-1, Loss of All AC Power- EDG "A" is unavailable due to maintenance- EDG "B" failed to start

- The Inside AO was dispatched to locally start the "B" EDG- EDG "B" LOCAL-REMOTE switch was placed in the LOCAL position at the DGEngine Control PanelWhich ONE(1) of the following completes the statement below?

When the AO depresses the Local Engine Start pushbutton, the engine

___(1)___automatically prelube.Assuming the EDG "B" is successfully started and the LOCAL-REMOTE switchremains in the LOCAL position, the EDG "B" output breaker 52/27B

___(2)___ beclosed from the RTGB.(1) will(2) can(1) will(2) can NOT(1) will NOT(2) can(1) will NOT(2) can NOT A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 48 ILC-14 RO NRC Exam

51. Given the following plant conditions:- The plant is operating at 100% RTP- A release of Waste Condensate Tank (WCT) "A" is in progress- APP-036-E7, RAD MONITOR TROUBLE, is received

- BOP reports the FAIL light for R-18, LIQUID WASTE DISPOSAL EFFLUENTmonitor, is ONWhich ONE (1) of the following describes the status of RCV-018, LIQUID WASTERELEASE ISOLATION VALVE?RCV-018 will...

NOT automatically close. The release must be terminated manuallyautomatically close when the monitor FAIL light is illuminated NOT automatically close, and CANNOT be closed from the Waste Disposal Panelautomatically close, and must be reset by cycling the valve's pneumatic controller A.B.C.D.52. Given the following plant conditions:- Operating at 100% power- EDG "B" is unavailable due to emergent maintenance- All other systems are in their normal at power configuration- The "SU TRANSF OVLD/ PHASE TRIP" alarm energizes due to an overload ofbreaker 52/17, Start-Up Transformer to 4KV Bus 3.Thirty seconds after the above alarm is received, which of the following CCW pumpscan be manually started from the main control room?CCW "A" pump onlyCCW "B" pump onlyCCW "C" pump only CCW pumps "A" & "B" A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 49 ILC-14 RO NRC Exam

53. Which one of the following completes the statements below regarding the design of theMSIV accumulators?MSIV accumulators are designed to maintain a minimum of 58 psig for at least ____(1)____ minutes. Nitrogen

____(2)____ be aligned as a backup motiveforce for the MSIV's.(1) 15(2) can NOT(1) 30 (2) can NOT(1) 15(2) can (1) 30(2) can A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 50 ILC-14 RO NRC Exam

54. Given the following plant conditions:- The plant was operating at 100% power- A catastrophic failure of Instrument Air header piping occurred- IA header pressure is 5 psig and lowering

- APP-001-C1, "RCP THERM BAR COOL WTR HI FLOW," is in alarm- APP-001-D1, "RCP THERM BAR COOL WTR LO FLOW," is in alarm- Operators are concurrently executing AOP-017, LOSS OF INSTRUMENT AIRand EOP-E-0, REACTOR TRIP OR SAFETY INJECTION- ONLY Charging pump "A" is running at minimum speed per AOP-017Which ONE(1) of the following completes the statement below?LCV-115A, VCT/HI DP TK DIV, will fail to the

____(1)____

.Consider separately:With the instrument air header depressurized, in order to raise RCP seal injection flowper Section B of AOP-017, you shall

____(2)____

.(1) CVCS Hold Up Tank(2) throttle closed charging flow valve (HCV-121) from the Main Control Room (1) CVCS Hold Up Tank(2) locally throttle RCP seal water flow control valves(1) VCT(2) throttle closed charging flow valve (HCV-121) from the Main Control Room(1) VCT(2) locally throttle RCP seal water flow control valves A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 51 ILC-14 RO NRC Exam

55. Which one of the following describes a correct configuration for the Containment MainPersonnel Access Hatch doors and equalizing valves while the airlock is in use forentering/exiting Containment while the plant is in MODE 1?Outer door OPENOuter door equalizing valve OPENInner door CLOSEDInner door equalizing valve CLOSED Outer door OPENOuter door equalizing valve OPENInner door CLOSEDInner door equalizing valve OPEN Outer door CLOSEDOuter door equalizing valve OPENInner door OPENInner door equalizing valve CLOSEDOuter door CLOSEDOuter door equalizing valve CLOSEDInner door OPENInner door equalizing valve CLOSED A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 52 ILC-14 RO NRC Exam

56. Given the following plant conditions:- A Reactor trip coincident with a Loss of Offsite Power has occurred- RVLIS has lost indicationWhich ONE(1) of the following completes the statements below?

IAW EPP-6, the crew will cool down from 500°F to 450°F at (1)

°F/hr. During the FIRST depressurization, the crew will depressurize to (2) psig.(1) 100(2) 1600(1) 50(2) 1600(1) 100(2) 800(1) 50(2) 800 A.B.C.D.57. The Unit is commencing a Reactor Start Up and is pulling control groups "A" and "B" rods. At 25 steps on the "B" bank an IRPI module for a "B" group rod fails low. Which ONE(1) of the following completes the statement below?Annunciator APP-005-F2 ROD BOTTOM, ROD DROP (1) be ILLUMINATEDand an ERFIS printout for Rod Deviation (2)___ occur.

(1) will(2) will(1) will(2) will NOT(1) will NOT(2) will(1) will NOT(2) will NOT A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 53 ILC-14 RO NRC Exam

58. Given the following plant conditions:A Loss of Coolant Accident (LOCA) has been in progress for the last two hours. Youhave been assigned to monitor plant parameters as indicated on the Main ControlRoom ICCM plasma displays.Both Train 'A' and 'B' ICCM plasma displays contain the exact SAME indications.- FULL RANGE RVLIS 100%- SUBCOOL (T/C) 34 o F- AVG 5 HIGH 605 o F- SUBCOOL (RTD) 37 o F- HIGH RTD 607 o FOperators are MANUALLY monitoring the CSF-2, Core Cooling Critical SafetyFunction Status Tree and have reached the "RCS Subcooling" Decision Block.Which ONE(1) of the following completes the statement below?

In accordance with OMM-022, "EMERGENCY OPERATING PROCEDURES USER'SGUIDE" and based on the conditions above, CSFST parameter monitoring____(1)____ be relaxed to 10-20 minutes.When monitoring for the "RCS Subcooling" Decision Block, the ICCM plasma displayvalue of ____(2)____ should be used per OMM-022.(1) may(2) SUBCOOL (T/C)(1) may(2) SUBCOOL (RTD)(1) may NOT(2) SUBCOOL (T/C)(1) may NOT(2) SUBCOOL (RTD)

A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 54 ILC-14 RO NRC Exam

59. Which ONE (1) of the following is the power supply for HVE-3, CV Air Iodine Removal Fan?MCC-5MCC-6 MCC-9MCC-10 A.B.C.D.60. Given the following plant conditions:- Containment particulate and gas monitors R-11 and R-12 are in service- Containment Purge fan HVE-1A is runningWhich ONE(1) of the following completes the statement below?

If purge fan HVE-1A loses power ___(1)__

__.Subsequently: - R-11 alarmed and is now reading below the alarm setpointAfter resetting the R-11 alarm, manual operation of containment purge inlet and outletvalves (2) be performed.(1) all containment purge inlet and outlet valves will automatically close(2) can(1) all containment purge inlet and outlet valves will automatically close(2) can NOT(1) containment purge fan HVE-1B will automatically start(2) can(1) containment purge fan HVE-1B will automatically start(2) can NOT A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 55 ILC-14 RO NRC Exam

61. Given the following plant conditions:- Boron concentrations in the Spent Fuel Pit (SFP) have just been analyzed to be 1483 ppm.- The Shift Manager determines that OP-910, SPENT FUEL PIT COOLING ANDPURIFICATION SYSTEM, Section 8.4.6 will be used by conservatively applying the note in that procedure to raise boron concentration.- "NOTE: Each 100 pound bag of granulated boric acid will raise SFP boronconcentration by 6 ppm."Which ONE(1) of the following completes the statement below?Based on the information above and the NOTE provided, the MINIMUM number ofbags of granulated boric acid needed to raise the SFP boron concentration to theMINIMUM Tech Spec limit is (1) bags. Based on the information above and the NOTE provided, the MINIMUM number ofbags of granulated boric acid needed to raise the SFP boron concentration to theMINIMUM Administrative limit of OP-910 is (2) bags.(1) 3(2) 95(1) 78(2) 95(1) 3(2) 153(1) 78(2) 153 A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 56 ILC-14 RO NRC Exam

62. Given the following plant conditions:- Unit 2 is in Mode 6 and refueling activities are in progress with the equipment hatch REMOVED- R-14C, Plant Vent Low Range Noble Gas Monitor is out of service

- A fuel assembly has been visibly damaged during removal from the core- AOP-013, "Fuel Handling Accident", is in progress R-2, CV area rad monitorR-12, CV Air & Plant Vent Radioactive GasWhich ONE(1) of the following completes the statement below?Radiation Monitor

___(1)____ would provide the FIRST indications in the control roomof a developing leak from the damaged fuel assembly. Once the Rad Monitor is inALARM, IAW AOP-013, the containment purge system is verified ___(2)___ service.(1) R-2(2) in(1) R-2(2) NOT in(1) R-12(2) in(1) R-12(2) NOT in A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 57 ILC-14 RO NRC Exam

63. Given the following plant conditions:- A startup following a refueling outage is in progress with the reactor at 25%power and stable, holding for Chemistry with the following conditions:- Rod control is in AUTO- All other systems are in automaticA 100 MWe load rejection occurs. Which one of the following describes the OVERALLresponse and final condition for Steam Generator water level?With no operator action, NR S/G water levels will _______ .lower, then return to original levelrise, then return to original levelrise, then stabilize at a level lower than the original level lower, then stabilize at a level lower than the original level A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 58 ILC-14 RO NRC Exam

64. Given the following plant conditions:Which of the following correctly completes the following statements in accordance withOP-704, Spent Resin Storage Tank, for transferring spent resin from the Spent ResinStorage Tank (SRST) to a High Integrity Container (HIC)?Which ONE (1) of the following completes the statements below to minimize radiationexposure to site personnel:The method used to warn personnel of the radiological hazard is/are (1)

.A flush of the transfer lines__(2)___ required after resin transfer.(1) gates with signs and alarms posted at all doors to the auxiliary building andradwaste building(2) is(1) gates with signs and alarms posted at all doors to the auxiliary building andradwaste building(2) is NOT(1) a PA announcement made to warn unnecessary personel to stay clear(2) is(1) a PA announcement made to warn unnecessary personel to stay clear(2) is NOT A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 59 ILC-14 RO NRC Exam

65. Given the following plant conditions:- The plant is operating at 100% RTP- The instrument air / station air cross connect bypass filter inlet and outlet valvesare tagged out for filter replacement- A loss of Instrument Air has occurred with pressure currently at 75 psig- The crew is implementing AOP-017, LOSS OF INSTRUMENT AIRSA-70, PRIMARY AIR COMP RECEIVER TO STATION AIR HEADERSA-5, STATION AIR TO INST AIR CROSS CONNECTWhich ONE(1) of the following completes the statement below?As pressure lowered, at (1) psig Instrument Air header pressure, AOP-017directed an operator to be dispatched to (2)

.(1) 85(2) open SA-70 (1) 80(2) open SA-70 (1) 85(2) open SA-5(1) 80(2) open SA-5 A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 60 ILC-14 RO NRC Exam

66. Which ONE(1) of the following completes the statements below?IAW OMM-001-2, SHIFT ROUTINES AND OPERATING PRACTICES, the MINIMUMnumber of personnel that are reserved for fire response is (1)

. The MINIMUM number of SRO's required for safe shutdown activities whenimplementing DSP-002, HOT SHUTDOWN USING THE DEDICATED/ALTERNATESHUTDOWN SYSTEM, is (2)

.(1) 7(2) 1(1) 7(2) 2(1) 5(2) 1(1) 5(2) 2 A.B.C.D.67. Which one of the following includes acceptance criteria for the ECCS following apostulated Loss-of-Coolant Accident, as required by 10 CFR 50.46, "Acceptancecriteria for emergency core cooling systems for light-water nuclear reactors?"The calculated maximum fuel element cladding temperature shall be maintained less than ___(1)___ degrees F and the maximum cladding oxidation less than

___(2)___

percent.(1) 2200(2) 1(1) 2200(2) 17(1) 2500(2) 1(1) 2500(2) 17 A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 61 ILC-14 RO NRC Exam

68. The operating crew is performing actions to place the plant in Mode 5 in accordancewith GP-007, "PLANT COOLDOWN FROM HOT SHUTDOWN TO COLD SHUTDOWN" with the following sequence of events:- 0830 MDAFW Pump "B" placed in service- 1430 MDAFW Pump "B" secured

- 1432 RHR Pump "A" placed in service- 1448 RHR Pump "A" secured due to a flow indication problem on FI-608- 1458 RHR Pump "A" placed in service

- 1505 RHR Pump "A" secured due to a flow indication problem on FI-608- 1509 RHR Pump "A" placed in service- 1525 RHR Pump "A" secured due to a flow indication problem on FI-608FI-608, RHR SYSTEM HEATUP LINE FLOW INDICATIONThe time is currently 1530Which ONE(1) of the following completes the statement below?The maximum number of consecutive pump starts available for MDAFW Pump "B" inaccordance with OP-402, AUXILIARY FEEDWATER SYSTEM is __(1)

__ .A 45 minute waiting period prior to restarting RHR Pump "A" __(2)__ required inaccordance with OP-201, RESIDUAL HEAT REMOVAL SYSTEM.(1) 2(2) is(1) 2 (2) is NOT(1) 3 (2) is(1) 3(2) is NOT A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 62 ILC-14 RO NRC Exam

69. Given the following plant conditions:- The plant is at 100% power- A malfunction in LC-459G, PRESSURIZER LEVEL, has caused PZR level toincrease to 64% over the last 10 minutes. The controller remains in AUTO, withno operator action- Pressurizer heaters and sprays over-compensated for the rising pressure causedby rising level, and stabilized PZR pressure at 2225 psig by the lowest indicator- All other RCS parameters are within their normal control bandsThe Reactor Operator should notify the CRS that:the reactor should be tripped because a trip setpoint will be reached within the next2 minutes an entry condition for ITS 3.4.9, Pressurizer, has been metan entry condition for ITS 3.4.1, RCS Pressure, Temperature, and Flow Departurefrom Nucleate Boiling (DNB) Limits, has been met entry into AOP-025, RTGB Instrument Failure, is required A.B.C.D.70. Which ONE(1) of the following completes the statement below?A release of a Waste Gas Decay Tank ___(1)___ allowed while simultaneouslyreleasing the containment via a continuous CV purge.A release of a Waste Gas Decay Tank is allowed while stack monitor R-14C is out of service ___(2)___ .(1) is(2) as long as R-14D is operable because the ranges overlap(1) is NOT(2) as long as R-14D is operable because the ranges overlap(1) is(2) as long as an independent sample of the tank to be released has beenperformed(1) is NOT(2) as long as an independent sample of the tank to be released has beenperformed A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 63 ILC-14 RO NRC Exam

71. Given the following plant conditions:- SBLOCA is in progress- CV Ventilation Isolation valves did not closeEOP-E-0: REACTOR TRIP OR SAFETY INJECTIONWhich ONE(1) of the following completes the statements below?IAW EOP-E-0 Attachment 1, Auto Action Verification, the crew will depress the (1) push button on R-11 or R-12 to initiate the automatic actions that should haveoccurred. Once the automatic actions have occurred, the R-11/R-12 vacuum pump (2) have to be secured.(1) H.V. OFF(2) will(1) H.V. OFF(2) will NOT(1) Alarm/Reset(2) will(1) Alarm/Reset(2) will NOT A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 64 ILC-14 RO NRC Exam

72. Given the following conditions:- While entering the plant to relieve the shift, you notice smoke coming from theReactor Auxiliary Building.- You have NOT logged onto any RWP or obtained proper dosimetry (EAD).

- Your assistance is required in the Auxiliary Building.Which one of the following is allowed/required IAW FP-001, FIRE EMERGENCY forthe stated conditions?An exception to the requirement for an EAD AND RWP login is allowed for qualifiedmembers of the Fire Brigade (No RC Tech is required to invoke the exception).

An EAD must be obtained AND RWP login must be completed prior to AuxiliaryBuilding entry. An exception to the requirement for obtaining an EAD AND RWP login is allowedONLY IF an RC Tech is present to monitor personnel entry/exit to the AuxiliaryBuilding.RWP login is NOT required, and emergency dosimetry (EAD) is obtained from theRCA entrance.

A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 65 ILC-14 RO NRC Exam

73. Given the following plant conditions:- A reactor shutdown is in progress in accordance with GP-006-1, "NORMALPLANT SHUTDOWN FROM POWER OPERATION"- Reactor Power is 3%- The Main Turbine has been shutdown

- The electric plant is in a normal shutdown alignment with buses supplied from the SUTSubsequently:- Operators have depressed both Reactor Trip pushbuttons in accordance withGP-006 Reactor Trip breakers remain CLOSED- Intermediate Range SUR indication is fluctuating between 0.1 and -0.1 DPMEOP-E-0, REACTOR TRIP OR SAFETY INJECTIONFRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWSWhich answer below describes the required crew response to the above conditions?Enter EOP-E-0, do NOT enter FRP-S.1 Enter FRP-S.1, do NOT enter EOP-E-0Enter EOP-E-0 AND FRP-S.1 Do NOT enter EOP-E-0 OR FRP-S.1 A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 66 ILC-14 RO NRC Exam

74. Given the following plant conditions:- The plant is at 100% power- Control Room receives APP-036-H5, ANNUN SYS DC PWR LOST- The plant remains stableWhich ONE(1) of the following completes the statement below?As Balance of Plant Operator, you direct the Turbine Building Auxiliary Operator tocheck Breaker 10, Annunciator Panel (RTGB), on Distribution Panel (1)

.Per OP-603, Electrical Distribution, Precautions & Limitations, if there is no evidence ofabnormality present, the breaker can be reset (2)

.(1) A(2) one time(1) B(2) only after consultation with Engineering(1) A(2) only after consultation with Engineering(1) B(2) one time A.B.C.D.Tuesday, September 23, 2014 11:14:21 AM 67 ILC-14 RO NRC Exam

75. Given the following plant conditions:- The unit is operating at 100% power- Grid frequency is beginning to lowerWhich ONE(1) of the following completes the statement below?The highest frequency, below which entry into AOP-026 (Grid Instability) will berequired, is (1)

Hz.The highest frequency, below which an automatic Reactor trip will occur, is (2)

Hz.(1) 59.8(2) 58.2(1) 59.8(2) 58.4(1) 59.0(2) 58.2(1) 59.0(2) 58.4 A.B.C.D.You have completed the test!Tuesday, September 23, 2014 11:14:21 AM 68 ANSWER KEY REPORTfor ILC-14 RO NRC Exam Test Form: 0 Answers 0#IDPointsType1007 EA1.03 11.00MCSB2008 AK2.03 11.00MCSC 3009 EK2.03 11.00MCSB 4011 EG2.4.21 11.00MCSC 5022 AA1.09 11.00MCSB 6025 AA2.07 11.00MCSB 7026 AK3.03 11.00MCSD 8027 AG2.4.49 11.00MCSA 9029 EG2.4.31 11.00MCSC 10038 EA1.10 11.00MCSC 11040 AK3.04 11.00MCSA 12054 AA2.03 11.00MCSB 13055 EK1.02 11.00MCSC 14056 AK1.04 11.00MCSB 15057 AK3.01 11.00MCSD 16065 AA2.06 11.00MCSB 17W/E 04 EK2.2 11.00MCSA 18W/E 05 EK1.3 11.00MCSD 19003 AK3.05 11.00MCSD 20005 AG2.1.28 11.00MCSA 21024 AA2.02 11.00MCSA 22028 AA1.02 11.00MCSC 23032 AK1.01 11.00MCSC 24033 AA2.09 11.00MCSA 25061 AA1.01 11.00MCSB 26067 AK3.02 11.00MCSC 27W/E 09 EK2.2 11.00MCSC 28003 K5.04 11.00MCSD 29003 K6.04 11.00MCSB 30004 K3.06 11.00MCSC 31005 K4.12 11.00MCSC 32005 K5.05 11.00MCSA 33006 A4.02 11.00MCSC 34007 K5.02 11.00MCSC 35008 A1.02 11.00MCSD 36008 K3.03 11.00MCSC 37010 K1.08 11.00MCSB 38012 A2.03 11.00MCSB 39012 A4.07 11.00MCSB 40013 K2.01 11.00MCSB 41022 A3.01 11.00MCSB 42026 G2.1.31 11.00MCSD 43039 A4.04 11.00MCSD 44059 A2.12 11.00MCSD 45061 K6.02 11.00MCSD 46062 A1.01 11.00MCSC 47062 K1.04 11.00MCSBTuesday, September 23, 2014 11:15:05 AM 1

ANSWER KEY REPORTfor ILC-14 RO NRC Exam Test Form: 0 Answers 0#IDPointsType48063 A1.01 11.00MCSA49064 A3.13 11.00MCSA 50064 G2.4.35 11.00MCSC 51073 K4.01 11.00MCSA 52076 K2.04 11.00MCSB 53078 K1.05 11.00MCSB 54078 K3.02 11.00MCSD 55103 K4.04 11.00MCSA 56002 K6.03 11.00MCSA 57014 K3.02 11.00MCSC 58017 A2.02 11.00MCSA 59027 K2.01 11.00MCSA 60029 K4.02 11.00MCSD 61033 G2.1.25 11.00MCSA 62034 A4.01 11.00MCSC 63035 A3.01 11.00MCSD 64068 K5.04 11.00MCSC 65079 K1.01 11.00MCSD 66G 2.1.1 11.00MCSC 67G 2.1.27 11.00MCSB 68G 2.2.2 11.00MCSD 69G 2.2.42 11.00MCSB 70G 2.3.11 11.00MCSC 71G 2.3.5 11.00MCSA 72G 2.3.7 11.00MCSB 73G 2.4.1 11.00MCSC 74G 2.4.32 11.00MCSD 75G 2.4.4 11.00MCSASECTION 1 ( 75 items)75.00Tuesday, September 23, 2014 11:15:05 AM 2