ML16214A180

Initial Exam 2016-301 Final RO Written Exam - Delay Release

ML16214A180
Person / Time
Site:	Hatch
Issue date:	08/01/2016
From:	Southern Nuclear Operating Co
To:
References
05000321, 366/2016301
Download: ML16214A180 (80)

Text

Date: Wednesday, June 08, 2016 Time: 3:49:34 PM TEST REPORT Question file: ILT 10 NRC EXAM BANK Copyright:

Test Date: 7/7/2016 Test Name: ILT-10 RO NRC EXAM Test Form: 0 Test Version: 0 Test Points: 75.00 Test File: ILT 10 RO NRC EXAM Test Path: O:\ILT 10\NRC EXAM\Written Exam\ILT 10 RO NRC EXAM.LXRTest

Name: ________________________________ ILT-10 RO NRC EXAM Form: 0 Version: 0

1. 201001K6.06 001 Unit 2 was operating at 100% RTP when a loss of RBCCW occurs.

A manual scram is inserted which results in the following:

o Reactor power is 6% RTP o None of the RBCCW pumps can be started Based on the above conditions and IAW 34AB-P42-001-2, Loss of RBCCW, The CRD pumps __________ .

A. are NOT allowed to operate because the CRD Pump Seal Coolers have lost their cooling medium B. are NOT allowed to operate because the CRD Pump Room Area Coolers have lost their cooling medium C. can be operated with a MAXIMUM allowable pumping medium temperature of 104°F D. can be operated with a MAXIMUM allowable pumping medium temperature of 249°F Wednesday, June 08, 2016 3:49:34 PM 1

ILT-10 RO NRC EXAM

2. 201002A2.04 001 Unit 1 is operating at 15% RTP and is performing a reactor startup.

All control rods in the currently latched RWM step are at their Insert Limit of position 04.

o The Withdraw Limit for the latched step is position 08 o Control rod 30-31 is currently selected When Control rod 30-31 is withdrawn, the rod DOUBLE NOTCHES to position 10.

Based on the above conditions, When Control rod 30-31 reaches position 10, the Rod Movement Control "Rod Out" white light will be __________ .

IAW 34GO-OPS-065-0, Control Rod Movement, the RWM __________ REQUIRED to be BYPASSED to correct the Control rod 30-31 mis-position.

A. ILLUMINATED; is B. ILLUMINATED; is NOT C. EXTINGUISHED; is D. EXTINGUISHED; is NOT Wednesday, June 08, 2016 3:49:34 PM 2

ILT-10 RO NRC EXAM

3. 201003G2.1.30 001 Unit 2 is operating at 100% RTP with the 2C11-F002A, Flow Control Valve, in service.

Subsequently, Drywell pressure increases to 2.5 psig.

Extinguished Illuminated One (1) minute later and based on the above indications/conditions, 2C11-F002A __________ responding correctly.

2C11-F002A indicating LIGHTS are located on __________ .

A. is; 2H11-P603 and locally at the 2C82-P001, Remote Shutdown Panel B. is; 2H11-P603 Panel ONLY C. is NOT; 2H11-P603 and locally at the 2C82-P001, Remote Shutdown Panel D. is NOT; 2H11-P603 Panel ONLY Wednesday, June 08, 2016 3:49:34 PM 3

ILT-10 RO NRC EXAM

4. 203000K5.01 001 Unit 2 has experienced a LOCA.

o RHR Loop 2B is injecting in the LPCI mode to maintain RWL o A leak develops on 2E11-F015B, RHR Inboard Injection valve Subsequently, all RHR Loop 2B pumps are secured.

Based on the above conditions, The water leaking from 2E11-F015B will be leaking into __________ Containment.

The water leaking from 2E11-F015B __________ be isolated by operation of 2E11-F050B, RHR Injection Check valve.

A. Secondary; will NOT B. Secondary; will C. Primary; will NOT D. Primary; will Wednesday, June 08, 2016 3:49:34 PM 4

ILT-10 RO NRC EXAM

5. 204000K4.07 001 The automatic closure setpoint for 2G31-FCV-F033, RWCU Blowdown Flow Control Valve, is met if __________ .

A. RWCU pump flow decreases to 50 gpm B. RWCU Dump flow increases to 150 gpm C. 2G31-F033 upstream pressure decreases to 5 psig D. 2G31-F033 downstream pressure increases to 120 psig Wednesday, June 08, 2016 3:49:34 PM 5

ILT-10 RO NRC EXAM

6. 205000K3.02 001 Unit 1 is in Mode 4 with both Recirc pumps off.

RHR Loop B is operating in Shutdown Cooling with a flowrate of 7300 gpm.

Subsequently, a tube rupture occurs in RHR Heat Exchanger 1B.

With the above conditions and NO operator actions, RWL will start going __________ .

IAW 34SO-E11-010-1, RHR System, the MINIMUM listed corrected RWL that must be maintained by the OATC is __________ .

A. UP; 34 inches B. UP; 54 inches C. DOWN; 34 inches D. DOWN; 54 inches Wednesday, June 08, 2016 3:49:34 PM 6

ILT-10 RO NRC EXAM

7. 205000K6.04 001 Unit 1 is in Mode 3 with RHR pump 1A in Shutdown Cooling (SDC).

Subsequently, RWL lowers to -10 inches and stabilizes.

Three (3) minutes later and based on the above conditions, 1E11-F015A, RHR Injection Valve, will be __________ .

RHR pump 1A __________ be running.

A. closed; will B. closed; will NOT C. open; will D. open; will NOT Wednesday, June 08, 2016 3:49:34 PM 7

ILT-10 RO NRC EXAM

8. 206000G2.4.50 001 Unit 2 is operating at 100% RTP when the following occurs:

o TORUS WATER LEVEL HIGH/LOW, 602-235, is ILLUMINATED o Torus water level 151.0 inches and stable Based on the above conditions and one (1) minute later, HPCI pump suction will be aligned to the __________ .

RCIC pump suction will be aligned to the __________ .

A. CST; Torus B. CST; CST C. Torus; Torus D. Torus; CST Wednesday, June 08, 2016 3:49:34 PM 8

ILT-10 RO NRC EXAM

9. 209001A3.02 001 Unit 2 is operating at 100% RTP.

At 13:01, a Loss of Offsite Power occurs to BOTH Units.

At 13:10, RWL is -101 inches and slowly lowering.

Based on the above conditions, The EARLIEST listed time that Core Spray pump 2A will be in operation is __________ .

A. 13:01 B. twelve (12) seconds after 13:01 C. 13:10 D. twelve (12) seconds after 13:10 Wednesday, June 08, 2016 3:49:34 PM 9

ILT-10 RO NRC EXAM

10. 211000G2.2.36 001 Unit 1 is operating at 100% RTP with the following:

o 1C41-C001B, SBLC pump 1B, is DANGER Tagged out of service for a pump leak Based on the above status of SBLC pump 1B, If a troubleshooting activity resulted in tripping the feeder breaker to __________ ,

an additional LCO entry would be required for the SBLC System.

A. 1R24-S011, Rx. Bldg. MCC 1C B. 1R24-S012, Rx. Bldg. MCC 1B C. 1R24-S013, Rx. Bldg. MCC 1A D. 1R24-S014, Rx. Bldg. MCC 1D Wednesday, June 08, 2016 3:49:34 PM 10

ILT-10 RO NRC EXAM

11. 212000K1.03 001 Unit 2 is operating at 75% RTP.

The following occurs at the listed time:

o 12:01 RPS MG Set 2A trips o 12:03 The Power Source Select switch (2H11-P610) is placed in the "ALT B" position Based on the above conditions, At 12:02, 2B31-R614, Recirc Drive Flow, recorder __________ indicate accurate flow.

At 12:05, Recirc Pump 2A Drive Flow will be __________ the Recirc Pump 2A Drive Flow at 12:00.

A. will NOT; less than B. will NOT; approximately the same as C. will continue to; less than D. will continue to; approximately the same as Wednesday, June 08, 2016 3:49:34 PM 11

ILT-10 RO NRC EXAM

12. 215002K1.06 001 Unit 2 is operating at 50% RTP.

A central control rod has just been selected for withdrawal.

Based on the above conditions, When the central control rod was selected, the RBM indication immediately went __________ .

After the RBM nulling sequence is complete, the RBM reading will be __________ .

A. downscale; 50%

B. downscale; 100%

C. to 100%;

50%

D. to 100%;

100%

Wednesday, June 08, 2016 3:49:34 PM 12

ILT-10 RO NRC EXAM

13. 215003K2.01 001 Unit 2 is starting up with Reactor power at 5% RTP.

24/48 VDC Cabinet 2A, 2R25-S015, de-energizes and can NOT be restored.

Based on the above conditions, IRM Channels __________ will have lost their power supply.

A. 2A & 2C B. 2A & 2D C. 2B & 2C D. 2B & 2D Wednesday, June 08, 2016 3:49:34 PM 13

ILT-10 RO NRC EXAM

14. 215004K3.04 001 Unit 2 is in a Refueling outage (NO fuel removed yet).

The following conditions exist:

o Reactor Mode Switch REFUEL o SRM Shorting Links REMOVED A Control rod located adjacent to SRM 2A is fully WITHDRAWN resulting in the following SRM indications:

o SRM 2A 20 CPS o SRM 2B 7 CPS o SRM 2C 8 CPS o SRM 2D 7 CPS Subsequently, a detector failure results in SRM 2D indication reading UPSCALE.

Based on the above conditions, SRM 2A reactor power indication will __________ .

The SRM RPS SCRAM Setpoint is _________ .

A. reduce to a lower value; 7x104 CPS B. reduce to a lower value; 3x105 CPS C. remain approximately the same; 7x104 CPS D. remain approximately the same; 3x105 CPS Wednesday, June 08, 2016 3:49:34 PM 14

ILT-10 RO NRC EXAM

15. 215005K1.08 001 Unit 2 is operating at 100% RTP with the following; o APRM 2B INOP and BYPASSED Subsequently, APRM 2C fails INOP.

Based on the above conditions, The "background" for Reactor power on the SPDS "Primary Display" will be __________ .

A. green B. yellow C. orange D. magenta Wednesday, June 08, 2016 3:49:34 PM 15

ILT-10 RO NRC EXAM

16. 217000K6.01 001 RCIC is injecting into Unit 2 following a transient.

Subsequently, 2R24-S021, 250V DC RX BLDG ESSEN. MCC 2A, DE-ENERGIZES.

Based on the above conditions, RCIC will __________ injecting into the RPV.

2E51-F008, Outboard Isolation Valve, __________ LOST power.

A. continue; has B. continue; has NOT C. stop; has D. stop; has NOT Wednesday, June 08, 2016 3:49:34 PM 16

ILT-10 RO NRC EXAM

17. 218000A2.06 001 Unit 1 is operating at 100% RTP when the ADS timer associated with the SPDS "Primary" Display screen INADVERTENTLY actuates.

The OATC reports ALL Key Parameters are NORMAL Based on the above conditions, The ADS timer that is counting down is the ___________ .

IAW 34AB-E10-001-1, Inadvertent Initiation Of ECCS/RCIC, the Immediate Operator Action is to __________ .

A. ADS Low Water Level Timer; shutdown ADS per the system operating procedure B. ADS Low Water Level Timer; place the ADS INHIBIT switches to the INHIBIT position C. ADS Logic Timer; shutdown ADS per the system operating procedure D. ADS Logic Timer; place the ADS INHIBIT switches to the INHIBIT position Wednesday, June 08, 2016 3:49:34 PM 17

ILT-10 RO NRC EXAM

18. 218000A3.09 001 A LOCA has occurred on Unit 2.

AUTO BLOWDOWN TIMERS INITIATED, 602-306, has just ILLUMINATED.

Based on the above conditions, One (1) minute later, the AUTO BLOWDOWN TIMERS INITIATED, 602-306, will AUTOMATICALLY reset (turn GREEN) if ___________ .

A. RWL increases to -90 inches B. Drywell pressure decreases to 1.5 psig C. ALL of the RHR and CS pumps are secured D. the ADS Inhibit Switches are placed in the "INHIBIT" position Wednesday, June 08, 2016 3:49:34 PM 18

ILT-10 RO NRC EXAM

19. 223002A1.04 001 Unit 2 is operating at 20% RTP when the following occurs:

At 10:00, 2B21-F022A, Inboard MSIV fully closes At 10:02, 2B21-F028B, Outboard MSIV fully closes At 10:04, 2B21-F022C, Inboard MSIV fully closes Based ONLY on the above conditions with respect to MSIV position input to the RPS Logic, At 10:03, the TOTAL number of 2C71-K14, RPS Scram Relays, that are ENERGIZED is __________ .

At 10:05, the TOTAL number of 2C71-K14, RPS Scram Relays, that are ENERGIZED is __________ .

A. four (4);

zero (0)

B. four (4);

four (4)

C. eight (8);

zero (0)

D. eight (8);

four (4)

Wednesday, June 08, 2016 3:49:34 PM 19

ILT-10 RO NRC EXAM

20. 223002A4.04 001 RCIC ISOLATION VLV F007/F008 NOT FULLY OPEN, 602-336, will ILLUMINATE based on exceeding the __________ setpoint, followed by a __________ minute time delay.

A. RCIC Equipment Room Temp High; 14 B. RCIC Equipment Room Temp High; 29 C. Suppression Chamber Area Air Temp High; 14 D. Suppression Chamber Area Air Temp High; 29 Wednesday, June 08, 2016 3:49:34 PM 20

ILT-10 RO NRC EXAM

21. 234000A3.01 001 Unit 2 is in a refueling outage with the following conditions.

o Rx Mode Switch ............ Locked in the REFUEL position o Control rods ................... One control rod is fully WITHDRAWN o Main Fuel Grapple ......... Lowered, but verified to be able to clear the cattle chute by 3 ft.

(Empty grapple move) o NO rod is selected The Refuel Bridge is over the Spent Fuel Pool and is moving toward the core to pick up the fuel bundle at position 17-42.

Based on the above conditions, The Refuel Bridge __________ move to the intended core location.

When the Refuel Bridge stops, if the Grapple Raise/Lower switch is placed in the "LOWER" position, the Main Grapple __________ lower.

A. will; will B. will; will NOT C. will NOT; will D. will NOT; will NOT Wednesday, June 08, 2016 3:49:34 PM 21

ILT-10 RO NRC EXAM

22. 239002A2.06 001 Unit 2 experienced a Main Turbine trip, resulting in a RPV Pressure INCREASE to 1135 psig.

The following conditions currently exist:

o Reactor Pressure 940 psig o Torus temp 96°F and steady Based on the above conditions, The MAXIMUM number of SRV's that will have automatically opened is __________ .

IAW 34SO-E11-010-2, RHR Sytem, the MINIMUM number of loop(s) of RHR REQUIRED to be placed in Torus Cooling is __________ .

A. eight (8);

one (1)

B. eight (8):

two (2)

C. four (4);

one (1)

D. four (4);

two (2)

Wednesday, June 08, 2016 3:49:34 PM 22

ILT-10 RO NRC EXAM

23. 241000A4.08 001 Unit 2 is operating at 25% RTP.

o Main Generator load is 150 MWE Based on the above plant conditions and IAW 34SO-N30-001-2, Main Turbine Operation, Turbine Control Valve (TCV) number 4 will be __________ .

If the "CLOSE VALVES" button on the "Control" "Speed" Screen is DEPRESSED,

__________ of the TCVs will CLOSE.

A. throttled open; NONE B. throttled open; ALL C. closed; NONE D. closed; ALL Wednesday, June 08, 2016 3:49:34 PM 23

ILT-10 RO NRC EXAM

24. 259001A1.04 001 Unit 2 is operating at 100% RTP with the following RWL indications:

o 2C32-R606A, GEMAC, indication: +36.9 inches o 2C32-R606B, GEMAC, indication: +36.0 inches o 2C32-R606C, GEMAC, indication: +37.9 inches Subsequently, the REFERENCE leg for RWL instrument 2C32-R606A develops a leak equivalent to a 5 inch per minute change on 2C32-R606A.

Based on the above conditions, INITIALLY, RFPT speeds will __________ .

Five (5) minutes later, FINAL RFPT speed will be equivalent to __________ .

A. DECREASE; windmilling speed B. DECREASE; turning gear speed C. INCREASE; windmilling speed D. INCREASE; turning gear speed Wednesday, June 08, 2016 3:49:34 PM 24

ILT-10 RO NRC EXAM

25. 259002K4.14 001 Unit 2 is at 75% RTP with the following RWLC System indications:

ILLUMINATED EXTINGUISHED NOTE: 2C32-R600, FW Master Controller, is operating in AUTOMATIC.

Based on the above conditions, 2C32-R600, FW Master Controller, is currently using the __________ as its value for RWL.

The FW Master Controller is currently operating in __________ Control.

A. instrument selected from the Reactor Water Level Select switch; Single Element B. instrument selected from the Reactor Water Level Select switch; Three Element C. Median Level Signal Processor, 2C32-K648 output; Single Element D. Median Level Signal Processor, 2C32-K648 output; Three Element Wednesday, June 08, 2016 3:49:35 PM 25

ILT-10 RO NRC EXAM

26. 261000A4.01 001 BOTH Units are operating at 100% RTP when a RWCU System break occurs in the Unit 2 Reactor Building.

At 10:05: 2D11-K609A-D, Rx. Bldg. Contaminated Area Radiation, monitors indicate 20 mR/hr Based on the above conditions and IAW 34SO-T46-001-1/2, Standby Gas Treatment System, The EARLIEST listed time that the __________ SBGT fan will have automatically shutdown is __________ .

A. 1B; 10:15 B. 1B; 10:10 C. 2B; 10:15 D. 2B; 10:10 Wednesday, June 08, 2016 3:49:35 PM 26

ILT-10 RO NRC EXAM

27. 262001A1.04 001 Unit 2 is at 70% RTP with an operator transferring 4160 VAC Bus 2D to its NORMAL supply.

The following conditions currently exist:

o Voltages are matched o Sync switch for the 4160 VAC 2D Normal breaker is in the ON position o Sync light is at its dimmest (12 O'Clock position and steady) o Station SVC Interlock Cutout switch for ACB 135484-135534 is in the OFF-(DOWN) position Subsequently, the operator places the control switch for 135484 (Normal supply breaker) in the close position for one (1) second and then releases the switch.

Based on the above conditions, The ampere indication will be as shown on __________ .

Figure 1 Figure 2 Figure 3 Figure 4 A. Figure 1 B. Figure 2 C. Figure 3 D. Figure 4 Wednesday, June 08, 2016 3:49:35 PM 27

ILT-10 RO NRC EXAM

28. 262002K4.01 001 Unit 2 was operating at 100% RTP when the following occured:

o Loss of Off-Site Power (LOSP) o EDG 2A fails to start Based on the above conditions and without any operator actions, After the LOSP, the Unit 2 Vital AC Bus will INITIALLY receive power from __________ .

Subsequently, if this power supply is lost, the Vital AC Bus __________ automatically transfer to ANOTHER power source.

A. the Vital AC batteries; will B. the Vital AC batteries; will NOT C. 600 V Bus 2D via Vital AC battery charger; will D. 600 V Bus 2D via Vital AC battery charger; will NOT Wednesday, June 08, 2016 3:49:35 PM 28

ILT-10 RO NRC EXAM

29. 263000A1.01 001 Unit 2 Division 1 125VDC Station Service Battery Chargers are being operated in the EQUALIZE Mode.

Based on the above conditions and IAW 34SO-R42-001-2, 125 VDC And 125/250 VDC System, In EQUALIZE Mode, the charger output voltage to the battery will be __________ than when the charger is operating in the FLOAT Mode.

Without re-charging, the 125 VDC Station Service batteries are sized to have adequate storage capacity to carry the required load for approximately __________ .

A. equal; 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> B. equal; 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> C. higher; 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D. higher; 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Wednesday, June 08, 2016 3:49:35 PM 29

ILT-10 RO NRC EXAM

30. 264000K1.05 001 Which ONE of the following knobs can be used to completely shut off the fuel supply to a running Plant Hatch Emergency Diesel Generator?

A. LOAD LIMIT B. SYN INDICATOR C. SPEED DROOP D. SYNCHRONIZER Wednesday, June 08, 2016 3:49:35 PM 30

ILT-10 RO NRC EXAM

31. 264000K5.05 001 IAW 34SO-R43-001-2, Diesel Generator Standby AC System, Section 7.2.1.2, Synchronizing Diesel Generator 2A to an Energized Bus, When manually synchronizing EDG 2A to an energized bus, the synchroscope is REQUIRED to be rotating in a direction which will REDUCE the probability of causing a _________ trip.

After EDG 2A output breaker is closed, exceeding the Crankcase pressure setpoint

__________ automatically trip EDG 2A.

A. differential current; will B. differential current; will NOT C. reverse power; will D. reverse power; will NOT Wednesday, June 08, 2016 3:49:35 PM 31

ILT-10 RO NRC EXAM

32. 272000K5.01 001 Unit 2 is at 50% RTP increasing power to 100% RTP.

The following conditions exist:

o The Hydrogen Injection System controller is in AUTOMATIC/EXTERNAL o The Hydrogen flow setpoint is set at 5 SCFM At 10:00, Reactor Power is 100% RTP.

At 10:30, Hydrogen flow is ISOLATED.

Based on the above conditions, As reactor power is increased, the Hydrogen flow rate will __________ .

At 10:35, the Main Steam Line radiation levels will have __________ .

A. INCREASE; DECREASED B. INCREASE; INCREASED C. REMAIN the SAME; DECREASED D. REMAIN the SAME; INCREASED Wednesday, June 08, 2016 3:49:35 PM 32

ILT-10 RO NRC EXAM

33. 286000K2.02 001 IAW 34SO-X43-001-1, Fire Pumps Operating Procedure, The power supply to 1X43-C001, Electric Fire Pump, is __________ .

A. 4160 VAC 1E, 1R22-S005 B. 4160 VAC 1F, 1R22-S006 C. 600 VAC 1A, 1R25-S051 D. 600/208 VAC 1A, 1R24-S028 Wednesday, June 08, 2016 3:49:35 PM 33

ILT-10 RO NRC EXAM

34. 290002K5.01 001 Unit 2 is operating at 100% RTP. The following information was obtained from a 3D MONICORE Monitor Case printout:

MFLCPR LOC MFLPD LOC 1.011 11-26 0.974 29-42-20 Based on the above conditions, At this time, the __________ thermal limit has been EXCEEDED.

The basis for the thermal limit identified above is to avoid the potential for __________ .

A. MFLPD; fuel rod transition boiling B. MFLPD; fuel cladding plastic strain C. MFLCPR; fuel rod transition boiling D. MFLCPR; fuel cladding plastic strain (Terms provided per applicant question during exam administration)

MFLPD - Maximum Fraction of Limiting Power Density MFLCPR - Maximum Fraction of Limiting Critical Power Ratio Wednesday, June 08, 2016 3:49:35 PM 34

ILT-10 RO NRC EXAM

35. 290003K3.02 001 Unit 1 is in Mode 3.

Unit 2 is in Mode 4, moving irradiated fuel in the Unit 2 Fuel Pool.

Subsequently, the following occurs; o 600 VAC Bus 1C DE-ENERGIZES o 600 VAC Bus 1D DE-ENERGIZES Based on the above conditions, LCO 3.7.5, Control Room Air Conditioning (AC) System, __________ currently applicable to BOTH Units.

Main Control Room instrumentation cooling __________ been lost.

A. is NOT; has B. is NOT; has NOT C. is; has D. is; has NOT Wednesday, June 08, 2016 3:49:35 PM 35

ILT-10 RO NRC EXAM

36. 295001AK3.04 001 Unit 2 is operating at 60% RTP.

Subsequently, ONE Recirc Pump trips.

Unit 2 stabilizes inside the Region of Potential Instabilities on the power to flow map.

APRM bandwidth oscillations are observed and are INCREASING.

Based on the above conditions, The LOWEST listed APRM peak to peak oscillation that REQUIRES a reactor scram is __________ .

The reason for the reactor scram is to avoid EXCEEDING the Limit for __________ .

A. 3%;

MCPR B. 3%;

MAPRAT C. 7%;

MCPR D. 7%;

MAPRAT Wednesday, June 08, 2016 3:49:35 PM 36

ILT-10 RO NRC EXAM

37. 295003AK2.03 001 Unit 1 is operating at 100% RTP when 1R25-S036, Essential Cabinet 1A, de-energizes and CANNOT be re-energized.

The SRO directs a NPO to cross connect Instrument Buses IAW 34AB-R25-002-1, Loss Of Instrument Buses.

Based on the above conditions and IAW 34AB-R25-002-1, To energize 1R25-S064, Instrument Bus 1A, from 1R25-S065, Instrument Bus 1B, the NPO must utilize __________ .

Once power is restored to 1R25-S064, 1N62-F527, Off Gas Stack Inlet Valve, __________ .

A. breakers ONLY; will automatically open B. breakers ONLY; must be manually opened C. breakers and disconnects; will automatically open D. breakers and disconnects; must be manually opened Wednesday, June 08, 2016 3:49:35 PM 37

ILT-10 RO NRC EXAM

38. 295004AA1.03 001 Unit 2 is operating at 100% RTP.

o A loss of 2R22-S016, 125/250VDC Switchgear 2A, occurs o Subsequently, a Main Turbine trip occurs Based on the above conditions and IAW 34AB-R22-001-2, Loss Of DC Buses, The Main Generator output breakers __________ .

The 4160 VAC Station Service Buses __________ automatically transfer to their alternate supply.

A. will automatically open; will B. will automatically open; will NOT C. must be manually opened; will D. must be manually opened; will NOT Wednesday, June 08, 2016 3:49:35 PM 38

ILT-10 RO NRC EXAM

39. 295005G2.2.37 001 Unit 2 was operating at 100% RTP with 4160 VAC 2G Emergency Bus on Alternate Supply.

Subsequently, the Unit 2 Main Turbine trips on Generator Differential Overcurrent.

Based on the above conditions and one (1) minute after the Main Turbine trips, The Recirc pumps __________ be operating.

4160 VAC 2C __________ to its Startup Auxiliary Transformer.

A. will; must be manually transferred B. will; will automatically transfer C. will NOT; must be manually transferred D. will NOT; will automatically transfer Wednesday, June 08, 2016 3:49:35 PM 39

ILT-10 RO NRC EXAM

40. 295006AK1.02 001 Unit 2 was at 100% RTP when a spurious reactor scram occurred.

ALL Control Rods fully inserted with the following EXCEPTIONS:

Control Rod Position Control Rod Position 26-31 02 10-27 02 26-23 02 30-11 02 22-35 02 30-47 02 22-27 02 46-19 02 50-27 02 02-31 02 Based on the above conditions, Based ONLY on the current rod positions, the reactor __________ in a Cold Shutdown Rod Configuration.

IAW Plant Procedures, ALL automatic scram signals __________ ALLOWED to be BYPASSED.

A. is; are B. is; are NOT C. is NOT; are D. is NOT; are NOT Wednesday, June 08, 2016 3:49:35 PM 40

ILT-10 RO NRC EXAM

41. 295007AA2.02 001 Unit 2 has experienced a transient.

The following conditions exist at the given time:

At 10:05, RPV pressure is 1056 psig At 10:08, RPV pressure is 1075 psig At 10:11, LLS is controlling RPV pressure with the following:

o 2B LLS valve continuously OPEN o 2G LLS valve cycling on LLS setpoint Based on the above conditions, IAW 34AB-C71-001-2, Scram Procedure, the EARLIEST listed time that LLS is ALLOWED to be manually ARMED is __________ .

At 10:11, based on SRV positions, Reactor Power is approximately __________ .

A. 10:05; 6% RTP B. 10:05; 11% RTP C. 10:08; 6% RTP D. 10:08 11% RTP Wednesday, June 08, 2016 3:49:35 PM 41

ILT-10 RO NRC EXAM

42. 295010AK3.01 001 Unit 1 is operating at 100% RTP when Drywell pressure starts slowly INCREASING.

Drywell venting is placed in service using:

o 1T48-R615A, Drwl Flow Controller o 1T48-F336A, Drywell Vent Flow Cntl Valve Based on the above conditions, The bases for placing Drywell venting in service __________ to prevent a high Drywell pressure reactor scram.

IAW 34SO-T48-002-1, Containment Atmospheric Control and Dilution Systems, DO NOT EXCEED 100% demand on Controller, 1T48-R615A, to prevent damaging __________ .

A. is NOT; 1T48-R615A B. is NOT; 1T48-F336A C. is; 1T48-R615A D. is; 1T48-F336A Wednesday, June 08, 2016 3:49:35 PM 42

ILT-10 RO NRC EXAM

43. 295014G2.1.28 001 Unit 2 is operating at 75% RTP when HPCI inadvertently starts.

34SO-E41-001-2, High Pressure Coolant Injection (HPCI) System, has been entered.

o HPCI Initiation signal WHITE light will NOT reset o A NPO has just depressed the HPCI Trip Pushbutton Based on the above conditions and IAW 34SO-E41-001-2, The HPCI Trip Pushbutton will be RELEASED __________ .

The purpose for this action is to __________ on a subsequent initiation signal.

A. WHEN the 2E41-F001, HPCI Turb Steam Supply valve, indicates full CLOSED; prevent HPCI from automatically restarting B. WHEN the 2E41-F001, HPCI Turb Steam Supply valve, indicates full CLOSED; allow HPCI to automatically restart C. ONLY after HPCI TURBINE BRG OIL PRESS LOW, 601-112, alarm is received; prevent HPCI from automatically restarting D. ONLY after HPCI TURBINE BRG OIL PRESS LOW, 601-112, alarm is received; allow HPCI to automatically restart Wednesday, June 08, 2016 3:49:35 PM 43

ILT-10 RO NRC EXAM

44. 295016AA2.01 001 The Main Control Room has been evacuated.

The Unit 2 reactor was NOT shutdown prior to leaving the Control Room.

o Local actions have been taken to scram the reactor o ALL RSDP transfer switches have been placed in the EMERGENCY position Based on the above conditions and IAW 31RS-OPS-001-2, Shutdown From Outside Control Room, From the Remote Shutdown Panel, __________ can be started.

An operator stationed in the TSC will utilize __________ to verify automatic actions, isolations and initiations will occur.

A. ONLY one CRD pump; the Plant Process Computer B. ONLY one CRD pump; SPDS C. BOTH CRD pumps; the Plant Process Computer D. BOTH CRD pumps; SPDS Wednesday, June 08, 2016 3:49:35 PM 44

ILT-10 RO NRC EXAM

45. 295017AA1.05 001 A Site Area Emergency has just been declared on Unit 2 due to a leak into secondary containment. A Prompt Offsite Dose Assessment is in progress but results are unavailable at this time.

SPDS "MIDAS" Screen is attached on the next page.

The following Table is from NMP-EP-111-002, Emergency Notification Network Communicator Instructions - Hatch:

Wind Direction Rally Site Exit Evacuation Route/

From Point Route State Reception Center Main Access U.S. Hwy. 1 - North to Toombs Co. High School/

340º - 60º Gate 17 Road Lyons Road behind Low Level U.S. Hwy. 1 - South to Appling Co. High School/

61º - 110º PESB Radwaste Baxley Building Main Access U.S. Hwy. 1 - South to Appling Co. High School/

111º - 225º PESB Road Baxley EITHER direction on U.S. Hwy. 1 Main Access 226º - 339º PESB to Toombs Co. High School/ Lyons Road OR Appling Co. High School/ Baxley Based on the above conditions, Radiation levels in the Main Stack __________ exceeded the HI-HI setpoint.

IAW NMP-EP-111-002, the site evacuation route is __________ .

A. have; US #1 North B. have; US #1 South C. have NOT; US #1 North D. have NOT; US #1 South Wednesday, June 08, 2016 3:49:35 PM 45

ILT-10 RO NRC EXAM 295017AA1.05 002 Wednesday, June 08, 2016 3:49:35 PM 46

ILT-10 RO NRC EXAM

46. 295018AA1.01 001 Unit 2 is operating at 50% RTP.

Subsequently, one (1) RBCCW pump and one (1) PSW pump trips.

Both RBCCW Header and PSW Header pressures stabilize at 93 psig.

Based on the above conditions and IAW 34AB-P42-001-2, Loss Of Reactor Building Closed Cooling Water, the NPO will __________ the Standby RBCCW pump.

A Standby RBCCW pump automatic start signal __________ when the condition clears.

A. confirm the automatic start of; will automatically reset B. confirm the automatic start of; must be manually reset C. manually start; will automatically reset D. manually start; must be manually reset Wednesday, June 08, 2016 3:49:35 PM 47

ILT-10 RO NRC EXAM

47. 295019G2.1.32 001 On Unit 2, IAW 34AB-P51-001-2, Loss of Instrument And Service Air System Or Water Instrusion Into the Service Air System, 2P52-F565, Rx Bldg Inst N2 To Non-Int Air El. 185 Isol Vlv, will FIRST open when Non-Interruptible Essential Air Pressure DECREASES to __________ .

IF 2P52-F565 is continuously cycling, THEN 2P52-F565 is OPENED and the supply breaker is turned OFF to __________ .

A. 90 psig; stabilize nitrogen system pressure B. 90 psig; prevent failure of the valve motor C. 80 psig; stabilize nitrogen system pressure D. 80 psig; prevent failure of the valve motor Wednesday, June 08, 2016 3:49:35 PM 48

ILT-10 RO NRC EXAM

48. 295020AK2.01 001 Unit 2 is operating at 100% RTP when the following occurs:

2R22-S017, 125/250 VDC Batt Swgr 2B, DE-ENERGIZES.

Based on the above electrical loss, A loss of __________ would result in an inadvertent __________ Group 1 Isolation.

A. RPS Bus 2A; Outboard B. RPS Bus 2A; Inboard C. RPS Bus 2B; Outboard D. RPS Bus 2B; Inboard Wednesday, June 08, 2016 3:49:35 PM 49

ILT-10 RO NRC EXAM

49. 295021AA1.06 001 Unit 2 is shutdown with RHR Loop A aligned for Shutdown Cooling with the following conditions:

o Reactor Shutdown Two (2) days ago o The Drywell is open and available for access o 2B21-F003, Reactor Head Vent Valve OPEN o 2B21-F004, Reactor Head Vent Valve OPEN o 2B21-F005, Reactor Manual Head Vent Valve CLOSED Subsequently, a loss of SDC occurs.

Based on the above conditions and with NO Operator actions, IAW 34AB-E11-001-2, Loss of Shutdown Cooling, Reactor bulk coolant temperature is expected to reach 212°F in approximately __________ .

If Reactor bulk coolant temperature reaches 250°F, Drywell temperature indications will __________ .

REFERENCE PROVIDED A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 5 minutes; be slowly increasing B. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 5 minutes; still be approximately the same C. 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 54 minutes; be slowly increasing D. 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 54 minutes; still be approximately the same Wednesday, June 08, 2016 3:49:35 PM 50

ILT-10 RO NRC EXAM

50. 295023AK1.01 001 Both Units are operating at 100% RTP with the following activities in progress:

o Irradiated fuel movement in progress between the Fuel Pools o Unit 1 Normal Drywell venting in progress o Unit 2 Normal Drywell venting in progress At 13:00, the Refuel Bridge reports that a bundle has been bent and visible gas bubbles are rising from the currently latched fuel bundle.

In the Main Control Room there are NO lit annunciators from this malfunction.

At 13:03, the following indications are observed in the Main Control Room:

o ALL Refueling Floor (RF) ARMs 30 mR/hr o 1D11-K611 A-D, RF Vent Exhaust Radiation 17 mR/hr o 2D11-K611 A-D, RF Vent Exhaust Radiation 15 mR/hr o 2D11-K634 A-D, RF Vent Exhaust Radiation 7 mR/hr o 2D11-K635 A-D, RF Vent Exhaust Radiation 7 mR/hr Based on the above conditions, Normal Drywell venting __________ isolated on BOTH Units.

The EARLIEST listed time that entry into 34AB-J11-001-2, Irradiated Fuel Damage During Handling, is REQUIRED is __________ .

A. has; 13:00 B. has; 13:03 C. has NOT; 13:00 D. has NOT; 13:03 Wednesday, June 08, 2016 3:49:35 PM 51

ILT-10 RO NRC EXAM

51. 295024EK2.13 001 Unit 2 is operating at 75% RTP. Reactor power is being reduced due to a leaking SRV.

The following conditions exist:

o Drywell pressure 0.4 psig o Torus pressure 0.2 psig o RHR pump 2A operating o Torus Cooling in service o Torus Spray in service At 13:00, Drywell pressure starts increasing at 0.3 psig/minute.

At 13:03, DRYWELL PRESS HIGH, 602-210, ILLUMINATED.

Based on the above conditions, The EARLIEST listed time that RHR Loop A in Torus Spray will automatically isolate is __________ .

At 13:10, to return Torus Spray to service, the Containment Spray Vlv Control switch __________ REQUIRED to be placed in the MANUAL position.

A. 13:05; is B. 13:05; is NOT C. 13:03; is D. 13:03; is NOT Wednesday, June 08, 2016 3:49:35 PM 52

ILT-10 RO NRC EXAM

52. 295025EA2.01 001 31EO-EOP-107-2, Altenate RPV Pressure Control, is in progress.

o RPV pressure 1060 psig and slowly rising o HPCI system is aligned in Pressure Control Mode o 2E41-R612, HPCI flow controller is in AUTOMATIC with the setpoint at 2500 gpm Based on the above conditions and IAW 31EO-EOP-107-2, To stabilize RPV pressure, the operator will __________ .

A. RAISE the setpoint on 2E41-R612, HPCI flow controller B. LOWER the setpoint on 2E41-R612, HPCI flow controller C. throttle 2E41-F011, Test to CST VLV, in the CLOSE direction D. throttle 2E41-F011, Test to CST VLV, in the OPEN direction Wednesday, June 08, 2016 3:49:35 PM 53

ILT-10 RO NRC EXAM

53. 295026EK3.05 001 Unit 2 is operating at 100% RTP with a SRV experiencing leakage.

31EO-EOP-012-2, PC Primary Containment Control, is in progress.

Based on the above conditions and IAW 31EO-EOP-012-2, The LOWEST listed Torus temperature REQUIRING a reactor scram is __________ .

The reason for the reactor scram is to ensure the reactor is shutdown before Torus temperature reaches __________ limit.

A. 106°F; the BIIT Curve B. 106°F; any ECCS NPSH C. 111°F; the BIIT Curve D. 111°F; any ECCS NPSH Wednesday, June 08, 2016 3:49:35 PM 54

ILT-10 RO NRC EXAM

54. 295028G2.4.31 001 Unit 2 is operating at 100% RTP when a small pipe break in the Drywell occurs.

o Drywell Pressure has increased to 2.5 psig o Drywell Temperature has increased to 130°F Based on the above conditions and IAW 31EO-EOP-100-2, Miscellaneous Emergency Overrides, The HIGHEST listed Drywell temperature point at which the Drywell Chillers are allowed to be restarted is __________ .

A. 149°F B. 249°F C. 279°F D. 339°F Wednesday, June 08, 2016 3:49:35 PM 55

ILT-10 RO NRC EXAM

55. 295030EK3.01 001 Unit 1 has experienced a leak resulting in Torus water level decreasing.

Based on the above conditions and IAW 31EO-EOP-012-1, Primary Containment Control, If the leak is isolated, to restore Torus water level, the __________ System suction piping from the CST can be used.

If the leak can NOT be isolated, the reason for performing an Emergency Depressurization on low Torus water level is to prevent __________ .

A. Core Spray; direct pressurization of the Torus air space B. Core Spray; excessive loading of the SRV tail pipes and supports C. HPCI; direct pressurization of the Torus air space D. HPCI; excessive loading of the SRV tail pipes and supports Wednesday, June 08, 2016 3:49:35 PM 56

ILT-10 RO NRC EXAM

56. 295031EK2.11 001 Unit 1 is operating at 100% RTP.

An event occurs causing RWL to decrease and results in the following 1C32-R606A-C GEMAC, indications:

Time RWL 10:00 +40 inches and steady 10:01 +5 inches and decreasing 10:02 -5 inches and decreasing 10:15 +35 inches and steady Based on the above conditions and ONLY on plant automatic response, The NPO is first REQUIRED to perform RWL control actions per Placard RC-2 at __________ .

At 10:15, alarm, REACTOR VESSEL WATER LEVEL HIGH/LOW, 603-141, will be __________ .

A. 10:01; ILLUMINATED (Revised to FLASHING WHITE)

B. 10:01; EXTINGUISHED (Revised to SOLID GREEN)

C. 10:02; ILLUMINATED (Revised to FLASHING WHITE)

D. 10:02; EXTINGUISHED (Revised to SOLID GREEN)

(Answer revisions provided per applicant question during exam administration)

Wednesday, June 08, 2016 3:49:35 PM 57

ILT-10 RO NRC EXAM

57. 295032EA2.01 001 Unit 2 is operating at 100% RTP with the following HPCI Pump Room Cooler alignment:

o HPCI Pump Room Cooler "A" (2T41-B005A) is operating with its control switch in the "RUN" position o HPCI Pump Room Cooler "B" (2T41-B005B) is NOT running with its control switch in the "AUTO" position Subsequently, a steam leak develops in the HPCI Room causing HPCI Area temperatures to increase.

Time HPCI Room Temp 01:00 95°F 01:05 105°F 01:15 135°F 01:20 170°F Based on the above conditions, The EARLIEST listed time that HPCI Pump Room Cooler B, (2T41-B005B), will automatically start is __________ .

The EARLIEST listed time that HPCI will have RECEIVED an automatic isolation signal is __________ .

A. 01:00; 01:15 B. 01:00; 01:20 C. 01:05; 01:15 D. 01:05; 01:20 Wednesday, June 08, 2016 3:49:35 PM 58

ILT-10 RO NRC EXAM

58. 295037EA1.10 001 Unit 2 was operating at 100% RTP when an ATWS results in the following:

o SBLC System fails to initiate from the Control Room o An Operator attempts to locally initiate SBLC, but SBLC fails to initiate Based on the above conditions and IAW 31EO-EOP-109-2, Alternate Boron Injection, To inject Boron into the RPV using the CRD System , the operator will DIRECTLY connect hoses to __________ .

When boron is being injected, 2C11-F015A & F015B, CRD Pump Minimum Flow valves, are REQUIRED to be in the __________ position.

A. 2C41-F034, SBLC Combined Drain Valve; closed B. 2C41-F034, SBLC Combined Drain Valve; open C. 2C41-F015, SBLC Suction Line Drain Valve; closed D. 2C41-F015, SBLC Suction Line Drain Valve; open Wednesday, June 08, 2016 3:49:35 PM 59

ILT-10 RO NRC EXAM

59. 295038EK1.02 001 Unit 2 was operating at 100% RTP when a radiological event occurred resulting in an automatic start of the SBGT system.

An emergency is declared based on a radiological release at the following times:

At 09:00, Alert (RA1)

At 10:00, Site Area (RS1)

Based on the above conditions, The EARLIEST listed time that an entry condition into the RR portion of 31EO-EOP-014-2, SC-Rad Release Control, EOP Flowchart, will exist is __________ .

IAW 34SO-T46-001-2, SBGT System Operation, operation of _________ normally REQUIRED to maintain adequate negative Reactor Building dP.

A. 09:01; ONLY one (1) SBGT Train is B. 09:01; BOTH SBGT Trains are C. 10:01; ONLY one (1) SBGT Train is D. 10:01; BOTH SBGT Trains are Wednesday, June 08, 2016 3:49:35 PM 60

ILT-10 RO NRC EXAM

60. 300000K2.01 001 The power supply for Unit 2 Station Service Air Compressor (SSAC) 2A is __________ .

The power supply for Unit 2 SSAC 2C is __________ .

A. 600VAC Bus 2C; 600VAC Bus 2A B. 600VAC Bus 2C; 600VAC Bus 2BB C. 600VAC Bus 2D; 600VAC Bus 2A D. 600VAC Bus 2D; 600VAC Bus 2BB Wednesday, June 08, 2016 3:49:35 PM 61

ILT-10 RO NRC EXAM

61. 400000A2.04 001 The following annunciator on Unit 1 is in the alarm condition:

o SERVICE WATER EFFLUENT RADIATION HIGH, 601-407 Based on the above condition, The flowpath containing this alarm __________ AUTOMATICALLY isolate.

IAW 601-407, the NPO will notify __________ .

A. will; Chemistry to sample Circulating Water to determine if effluent limits have been exceeded B. will; the Radwaste Operator to confirm closed / close this discharge flowpath C. will NOT; Chemistry to sample Circulating Water to determine if effluent limits have been exceeded D. will NOT; the Radwaste Operator to confirm closed / close this discharge flowpath Wednesday, June 08, 2016 3:49:35 PM 62

ILT-10 RO NRC EXAM

62. 400000K3.01 001 Unit 1 was operating at 100% RTP when a total loss of Reactor Building Closed Cooling Water (RBCCW) occurred.

Based on the above conditions, The LOWEST RWCU Non-Regenerative Heat Exchanger outlet temperature which will result in a RWCU system isolation is __________ .

This isolation signal will result in automatic closure of ONLY the __________ ,

Rx Water Cleanup Valve.

A. 130°F; 1G31-F001 B. 130°F; 1G31-F004 C. 140°F; 1G31-F001 D. 140°F; 1G31-F004 Wednesday, June 08, 2016 3:49:35 PM 63

ILT-10 RO NRC EXAM

63. 500000EK1.01 001 The LOWEST listed Hydrogen concentration that will REQUIRE entry into 31EO-EOP-012-1, PC Primary Containment Control, is __________ .

IAW 31EO-EOP-104-1, Primary Containment Venting for Hydrogen/Oxygen Control, the PREFERRED method to vent containment is to align the CAD System vent valves to the __________ .

A. 1.6%;

Torus B. 1.6%;

Drywell C. 1.9%;

Torus D. 1.9%;

Drywell Wednesday, June 08, 2016 3:49:35 PM 64

ILT-10 RO NRC EXAM

64. 600000AA2.14 001 Unit 1 is shutdown with RPV pressure at 100 psig.

Subsequently, a fire has started in Fire Zone 1408, Switchgear Room 1F.

The fire brigade has requested all electrical switchgear located in the room to be de-energized to aid in suppressing the fire.

Based on the above conditions, Shutdown Cooling can be placed into service using __________ to achieve and maintain a Cold Shutdown condition.

A. RHR pump 1B and RHRSW pump 1C B. RHR pump 1B and RHRSW pump 1D C. RHR pump 1C and RHRSW pump 1C D. RHR pump 1C and RHRSW pump 1D Wednesday, June 08, 2016 3:49:35 PM 65

ILT-10 RO NRC EXAM

65. 700000G2.4.45 001 Unit 1 is operating at 100% RTP when a grid disturbance results in all 4160 VAC Emergency Buses indicating 3700 VAC.

The load dispatcher reports that these conditions will exist for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Based on the above conditions, IAW 34AB-S11-001-0, Operation With Degraded Voltage, one (1) hour later, 4160 VAC Bus __________ is REQUIRED to be powered by its associated EDG on Unit 1.

When transferring the 4160 VAC Emergency Bus to its associated EDG, the respective LOSS OF OFF SITE POWER alarm on 1H11-P652 __________ be RECEIVED.

A. 1E; will B. 1E; will NOT C. 1G; will D. 1G; will NOT Wednesday, June 08, 2016 3:49:35 PM 66

ILT-10 RO NRC EXAM

66. G2.1.5 001 Both Units are operating at 100% RTP.

Based on the above conditions and IAW NMP-AD-016-003, Scheduling and Calculating Work Hours, The MAXIMUM number of hours that a Nuclear Plant Operator may work in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period is _________ .

The MAXIMUM number of hours that a Nuclear Plant Operator may work in any 7-day/168-hour period is _________ .

A. 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />; 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> B. 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />; 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C. 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />; 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> D. 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />; 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Wednesday, June 08, 2016 3:49:35 PM 67

ILT-10 RO NRC EXAM

67. G2.1.44 001 Unit 1 is in REFUEL with a core shuffle currently in progress.

Based on the above conditions and IAW 34FH-OPS-001-0, Fuel Movement Operation, The individual in the Main Control Room on the headset with the Refueling SRO __________ REQUIRED to have a NRC License.

The Reactor Mode Switch __________ REQUIRED to be locked in the REFUEL position.

A. is; is B. is; is NOT C. is NOT; is D. is NOT; is NOT Wednesday, June 08, 2016 3:49:35 PM 68

ILT-10 RO NRC EXAM

68. G2.2.38 001 IAW the Unit 1 Facility Operating License, Southern Nuclear is authorized to operate Plant Hatch at a MAXIMUM steady-state reactor core power level of __________ .

A. 2777 MWth B. 2790 MWth C. 2800 MWth D. 2804 MWth Wednesday, June 08, 2016 3:49:35 PM 69

ILT-10 RO NRC EXAM

69. G2.2.40 001 Unit 2 is shutdown with the following conditions:

o RPV pressure 134 psig o Recirculation pump 2A OFF o Recirculation pump 2B Running Based on the above conditions and IAW Tech Spec 3.4.7, Residual Heat Removal (RHR)

Shutdown Cooling System - Hot Shutdown, The MINIMUM number of RHR Shutdown Cooling (SDC) subsystems required to be operable, without requiring entry into a Required Action Statement (RAS), is __________ .

A RHR SDC subsystem __________ REQUIRED to be in operation.

A. one (1);

is B. one (1);

is NOT C. two (2);

is D. two (2);

is NOT Wednesday, June 08, 2016 3:49:35 PM 70

ILT-10 RO NRC EXAM

70. G2.2.43 001 On Unit 2 the annunciator card for the following has been PULLED and DE-ACTIVATED:

o TURBINE TROUBLE, 650-105 Based on the above condition and IAW 31GO-OPS-014-0, With 650-105 de-activated, a __________ magnetic tile will be installed beside the annunciator number label under the annunciator window.

The installed magnetic tile will be __________ .

A. yellow; labeled with a "P" B. yellow; blank C. white; labeled with a "P" D. white; blank Wednesday, June 08, 2016 3:49:35 PM 71

ILT-10 RO NRC EXAM

71. G2.3.7 001 Unit 2 is operating at 100% RTP with a steam leak in the 2A SJAE room. A SO has been assigned to investigate. RP reports that the general area radiation levels are 120 mR/hr.

Based on the above conditions, A __________ RWP will be used to enter the SJAE room and __________ is the type of information you would expect to find on this type of RWP.

A. Specific; the current Reactor Mode B. Specific; Digital Alarming Dosimeter (DAD) settings C. General; the current Reactor Mode D. General; Digital Alarming Dosimeter (DAD) settings Wednesday, June 08, 2016 3:49:35 PM 72

ILT-10 RO NRC EXAM

72. G2.3.11 001 Unit 2 Radwaste is discharging Waste Sample Tank A to the canal.

Subsequently, the following indication is received:

o 2G11-R045, Total Plant Dilution Flow, recorder indicates 9500 gpm Based on the above conditions, The Radwaste discharge to the canal __________ .

With the existing Specific Release Permit, __________ permitted to restart the discharge of Waste Sample Tank A to the canal.

A. will automatically terminate; ONLY one (1) restart is B. will automatically terminate; NO restarts are C. must be manually terminated; ONLY one (1) restart is D. must be manually terminated; NO restarts are Wednesday, June 08, 2016 3:49:36 PM 73

ILT-10 RO NRC EXAM

73. G2.3.15 001 The power supplies for the Unit 1 Post-Treatment Radiation monitors, 1D11-K615A & K615B, is __________ .

The location of the Unit 1 Post-Treatment Radiation detectors NORMAL sample point is just prior to __________ .

A. RPS Bus B & Instrument Bus 1A; EXITING the Main Stack B. RPS Bus B & Instrument Bus 1A; ENTERING the Main Stack C. 24/48 VDC Cabinet 1A & 1B EXITING the Main Stack D. 24/48 VDC Cabinet 1A & 1B ENTERING the Main Stack Wednesday, June 08, 2016 3:49:36 PM 74

ILT-10 RO NRC EXAM

74. G2.4.17 001 An ATWS exists on Unit 1.

o Reactor Power is slowly DECREASING o Boron has NOT been injected into the RPV o All SRMs and IRMs have been fully inserted The following conditions occur:

Time Reactor Power 01:00 APRMs indicate 4% RTP 01:10 IRMs on Range 7 01:20 IRMs on Range 5 01:30 SRMs indicate 6.0 x 104 CPS Based on the above conditions and IAW the EOPs, The EARLIEST time the reactor can be declared SHUTDOWN with the reactor SUBCRITICAL is at __________ .

A. 01:00 B. 01:10 C. 01:20 D. 01:30 Wednesday, June 08, 2016 3:49:36 PM 75

ILT-10 RO NRC EXAM

75. G2.4.42 001 An emergency has been declared at Plant Hatch.

Based on the above conditions, The LOWEST listed emergency classification that will REQUIRE activation of the Technical Support Center (TSC) is __________ .

The ALTERNATE location for the TSC is __________ .

A. an Alert Emergency; Classroom 172, Simulator Building B. an Alert Emergency; the Main Control Room C. a Notification of Unusual Event; Classroom 172, Simulator Building D. a Notification of Unusual Event; the Main Control Room You have completed the test!

Wednesday, June 08, 2016 3:49:36 PM 76

NRC RO REFERENCES RO EXAM

1. 34AB-E11-001-2, Loss Of Shutdown Cooling, Page 15 (Attachment 1)

SNC PLANT E. I. HATCH Pg 15 of 34 DOCUMENT TITLE: DOCUMENT NUMBER: Ver No:

LOSS OF SHUTDOWN COOLING 34AB-E11-001-2 6.15 ATTACHMENT 1 Att. Pg.

TITLE: CORE FUEL IN UNFLOODED RPV 1 of 2 Case 1 : CORE FUEL in UNFLOODED RPV Days After Heat Load Saturation Evaporation Boil-Off Shutdown (MBTU/hr) Time Time Time 1.0 57.275 52 min 4 hr 50 min 5 hr 42 min 2.0 47.051 1 hr 4 min 5 hr 53 min 6 hr 57 min 3.0 40.644 1 hr 14 min 6 hr 48 min 8 hr 3 min 4.0 36.112 1 hr 23 min 7 hr 40 min 9 hr 3 min 5.0 32.822 1 hr 32 min 8 hr 26 min 9 hr 58 min 6.0 30.372 1 hr 39 min 9 hr 6 min 10 hr 46 min 7.0 28.494 1 hr 45 min 9 hr 42 min 11 hr 29 min 8.0 27.011 1 hr 51 min 10 hr 14 min 12 hr 6 min 9.0 25.806 1 hr 57 min 10 hr 43 min 12 hr 40 min 10.0 24.799 2 hr 1 min 11 hr 9 min 13 hr 11 min 11.0 23.935 2 hr 6 min 11 hr 34 min 13 hr 40 min 12.0 23.177 2 hr 10 min 11 hr 56 min 14 hr 7 min 13.0 22.501 2 hr 14 min 12 hr 18 min 14 hr 32 min 14.0 21.887 2 hr 18 min 12 hr 38 min 14 hr 57 min 15.0 21.323 2 hr 21 min 12 hr 59 min 15 hr 20 min 16.0 20.800 2 hr 25 min 13 hr 18 min 15 hr 44 min 17.0 20.310 2 hr 28 min 13 hr 37 min 16 hr 6 min 18.0 19.850 2 hr 32 min 13 hr 56 min 16 hr 29 min 19.0 19.415 2 hr 35 min 14 hr 15 min 16 hr 51 min 20.0 19.002 2 hr 39 min 14 hr 34 min 17 hr 13 min 21.0 18.610 2 hr 42 min 14 hr 52 min 17 hr 35 min 22.0 18.235 2 hr 45 min 15 hr 10 min 17 hr 56 min 23.0 17.877 2 hr 49 min 15 hr 29 min 18 hr 18 min 24.0 17.535 2 hr 52 min 15 hr 47 min 18 hr 39min 25.0 17.207 2 hr 55 min 16 hr 5 min 19 hr 1 min

1 A B C 26 A C 0 C 0 76 B C D 2 A B C 27 A B 0 521 B C 77 A B 0 3 A C D 28 A C 0 53AB 78 B C 0 A C D 29 A B 0 79 A C C 4

5 A D 30 B C 0 80 A B C 6 A C D 31 A B 0 C 81 A B C C

7 A C D C 57 A 82 A B C B C D 58 C D 83 B C 0 81 9 A B D 59 C 0 84 A B 0 10 B C D 60 C D 11 A B D 61 A 0 12 A C D 62 A C C D 63 B C D 131 14 C D 64 A C D 15 C D 40 65 B C 0 161 B C D 66 A B C B 0 67 B C 0 B C 0 68 A B C B C C 69 A B C 2 B C 70 B C 0 21 A B C 71 A C C 22 B C 0 23 A B D 24 B C 0 25 A B 0