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 PMTEST REPORTQuestion file: ILT 10 NRC EXAM BANKCopyright: 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: 01. 201001K6.06 001Unit 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 __________ . are NOT allowed to operate because the CRD Pump Seal Coolers have lost their coolingmedium are NOT allowed to operate because the CRD Pump Room Area Coolers have lost theircooling medium can be operated with a MAXIMUM allowable pumping medium temperature of 104°F can be operated with a MAXIMUM allowable pumping medium temperature of 249°F A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 1

ILT-10 RO NRC EXAM2. 201002A2.04 001Unit 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Withdraw Limit for the latched step is position 08 o Control rod 30-31 is currently selected When Control rod 30-31 is withdrawn, the rod DOUBLE NOTCHES to position 10.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" whitelight will be __________ .

IAW 34GO-OPS-065-0, Control Rod Movement, the RWM __________ REQUIRED to beBYPASSED to correct the Control rod 30-31 mis-position.ILLUMINATED; is ILLUMINATED; is NOT EXTINGUISHED; is EXTINGUISHED; is NOT A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 2

ILT-10 RO NRC EXAM3. 201003G2.1.30 001Unit 2 is operating at 100% RTP with the 2C11-F002A, Flow Control Valve, in service.Subsequently, Drywell pressure increases to 2.5 psig. One (1) minute later and based on the above indications/conditions, 2C11-F002A __________ responding correctly.

2C11-F002A indicating LIGHTS are located on __________ . is; 2H11-P603 and locally at the 2C82-P001, Remote Shutdown Panel is; 2H11-P603 Panel ONLY is NOT; 2H11-P603 and locally at the 2C82-P001, Remote Shutdown Panel is NOT; 2H11-P603 Panel ONLY A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 3

ILT-10 RO NRC EXAM4. 203000K5.01 001Unit 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. Secondary; will NOT Secondary; will Primary; will NOT Primary; will A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 4

ILT-10 RO NRC EXAM5. 204000K4.07 001The automatic closure setpoint for 2G31-FCV-F033, RWCU Blowdown Flow ControlValve, is met if __________ . RWCU pump flow decreases to 50 gpm RWCU Dump flow increases to 150 gpm 2G31-F033 upstream pressure decreases to 5 psig 2G31-F033 downstream pressure increases to 120 psig A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 5

ILT-10 RO NRC EXAM6. 205000K3.02 001Unit 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 bemaintained by the OATC is __________ . UP; 34 inches UP; 54 inches DOWN; 34 inches DOWN; 54 inches A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 6

ILT-10 RO NRC EXAM7. 205000K6.04 001Unit 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. closed; will closed; will NOT open; will open; will NOT A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 7

ILT-10 RO NRC EXAM8. 206000G2.4.50 001Unit 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 __________ . CST; Torus CST; CST Torus; Torus Torus; CST A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 8

ILT-10 RO NRC EXAM9. 209001A3.02 001Unit 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 __________ . 13:01 twelve (12) seconds after 13:01 13:10 twelve (12) seconds after 13:10 A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 9

ILT-10 RO NRC EXAM10. 211000G2.2.36 001Unit 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. 1R24-S011, Rx. Bldg. MCC 1C 1R24-S012, Rx. Bldg. MCC 1B 1R24-S013, Rx. Bldg. MCC 1A 1R24-S014, Rx. Bldg. MCC 1D A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 10 ILT-10 RO NRC EXAM11. 212000K1.03 001Unit 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. will NOT; less than will NOT; approximately the same as will continue to; less than will continue to; approximately the same as A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 11 ILT-10 RO NRC EXAM12. 215002K1.06 001Unit 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 __________ . downscale; 50%

downscale; 100%

to 100%;

50%

to 100%;

100% A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 12 ILT-10 RO NRC EXAM13. 215003K2.01 001Unit 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. 2A & 2C 2A & 2D 2B & 2C 2B & 2D A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 13 ILT-10 RO NRC EXAM14. 215004K3.04 001Unit 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 followingSRM 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 _________ . reduce to a lower value; 7x10 4 CPS reduce to a lower value; 3x10 5 CPS remain approximately the same; 7x10 4 CPS remain approximately the same; 3x10 5 CPS A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 14 ILT-10 RO NRC EXAM15. 215005K1.08 001Unit 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 __________ . green yellow orange magenta A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 15 ILT-10 RO NRC EXAM16. 217000K6.01 001RCIC 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. continue; has continue; has NOT stop; has stop; has NOT A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 16 ILT-10 RO NRC EXAM17. 218000A2.06 001Unit 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 OperatorAction is to __________ . ADS Low Water Level Timer; shutdown ADS per the system operating procedure ADS Low Water Level Timer; place the ADS INHIBIT switches to the INHIBIT position ADS Logic Timer; shutdown ADS per the system operating procedure ADS Logic Timer; place the ADS INHIBIT switches to the INHIBIT position A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 17 ILT-10 RO NRC EXAM18. 218000A3.09 001A 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, willAUTOMATICALLY reset (turn GREEN) if ___________ . RWL increases to -90 inches Drywell pressure decreases to 1.5 psig ALL of the RHR and CS pumps are secured the ADS Inhibit Switches are placed in the "INHIBIT" position A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 18 ILT-10 RO NRC EXAM19. 223002A1.04 001Unit 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 __________ . four (4);

zero (0) four (4);

four (4) eight (8);

zero (0) eight (8);

four (4) A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 19 ILT-10 RO NRC EXAM20. 223002A4.04 001RCIC ISOLATION VLV F007/F008 NOT FULLY OPEN, 602-336, will ILLUMINATEbased on exceeding the __________ setpoint, followed by a __________ minute time delay. RCIC Equipment Room Temp High; 14 RCIC Equipment Room Temp High; 29 Suppression Chamber Area Air Temp High; 14 Suppression Chamber Area Air Temp High; 29 A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 20 ILT-10 RO NRC EXAM21. 234000A3.01 001Unit 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 fuelbundle 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. will; will will; will NOT will NOT; will will NOT; will NOT A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 21 ILT-10 RO NRC EXAM22. 239002A2.06 001Unit 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 REQUIREDto be placed in Torus Cooling is __________ . eight (8);

one (1) eight (8):

two (2) four (4);

one (1) four (4);

two (2) A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 22 ILT-10 RO NRC EXAM23. 241000A4.08 001Unit 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. throttled open; NONE throttled open; ALL closed; NONE closed; ALL A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 23 ILT-10 RO NRC EXAM24. 259001A1.04 001Unit 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 leakequivalent 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 __________ . DECREASE; windmilling speed DECREASE; turning gear speed INCREASE; windmilling speed INCREASE; turning gear speed A.B.C.D.Wednesday, June 08, 2016 3:49:34 PM 24 ILT-10 RO NRC EXAM25. 259002K4.14 001Unit 2 is at 75% RTP with the following RWLC System indications: ILLUMINATEDEXTINGUISHEDNOTE: 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. instrument selected from the Reactor Water Level Select switch; Single Element instrument selected from the Reactor Water Level Select switch; Three Element Median Level Signal Processor, 2C32-K648 output; Single Element Median Level Signal Processor, 2C32-K648 output; Three Element A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 25 ILT-10 RO NRC EXAM26. 261000A4.01 001BOTH 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 automaticallyshutdown is __________ . 1B; 10:15 1B; 10:10 2B; 10:15 2B; 10:10 A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 26 ILT-10 RO NRC EXAM27. 262001A1.04 001Unit 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 theclose 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 Figure 1 Figure 2 Figure 3 Figure 4 A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 27 ILT-10 RO NRC EXAM28. 262002K4.01 001Unit 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 __________ automaticallytransfer to ANOTHER power source. the Vital AC batteries; will the Vital AC batteries; will NOT 600 V Bus 2D via Vital AC battery charger; will 600 V Bus 2D via Vital AC battery charger; will NOT A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 28 ILT-10 RO NRC EXAM29. 263000A1.01 001Unit 2 Division 1 125VDC Station Service Battery Chargers are being operated in theEQUALIZE Mode.

Based on the above conditions and IAW 34SO-R42-001-2, 125 VDC And 125/250 VDCSystem, In EQUALIZE Mode, the charger output voltage to the battery will be __________ thanwhen the charger is operating in the FLOAT Mode. Without re-charging, the 125 VDC Station Service batteries are sized to have adequatestorage capacity to carry the required load for approximately __________ . equal; 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> equal; 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> higher; 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> higher; 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 29 ILT-10 RO NRC EXAM30. 264000K1.05 001Which ONE of the following knobs can be used to completely shut off the fuel supply to arunning Plant Hatch Emergency Diesel Generator? LOAD LIMIT SYN INDICATOR SPEED DROOP SYNCHRONIZER A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 30 ILT-10 RO NRC EXAM31. 264000K5.05 001IAW 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 isREQUIRED 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. differential current; will differential current; will NOT reverse power; will reverse power; will NOT A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 31 ILT-10 RO NRC EXAM32. 272000K5.01 001Unit 2 is at 50% RTP increasing power to 100% RTP.The following conditions exist: o The Hydrogen Injection System controller is in AUTOMATIC/EXTERNALo 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 __________ . INCREASE; DECREASED INCREASE; INCREASED REMAIN the SAME; DECREASED REMAIN the SAME; INCREASED A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 32 ILT-10 RO NRC EXAM33. 286000K2.02 001IAW 34SO-X43-001-1, Fire Pumps Operating Procedure, The power supply to 1X43-C001, Electric Fire Pump, is __________ . 4160 VAC 1E, 1R22-S005 4160 VAC 1F, 1R22-S006 600 VAC 1A, 1R25-S051 600/208 VAC 1A, 1R24-S028 A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 33 ILT-10 RO NRC EXAM34.290002K5.01 001Unit 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 __________ .MFLPD;fuel rod transition boilingMFLPD;fuel cladding plastic strainMFLCPR;fuel rod transition boilingMFLCPR;fuel cladding plastic strainA.B.C.D.Wednesday, June 08, 2016 3:49:35 PM34 ILT-10 RO NRC EXAM35. 290003K3.02 001Unit 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 applicableto BOTH Units.

Main Control Room instrumentation cooling __________ been lost. is NOT; has is NOT; has NOT is; has is; has NOT A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 35 ILT-10 RO NRC EXAM36. 295001AK3.04 001Unit 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 __________ . 3%;

MCPR 3%;

MAPRAT 7%;

MCPR 7%;

MAPRAT A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 36 ILT-10 RO NRC EXAM37. 295003AK2.03 001Unit 1 is operating at 100% RTP when 1R25-S036, Essential Cabinet 1A, de-energizes andCANNOT 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, __________ . breakers ONLY; will automatically open breakers ONLY; must be manually opened breakers and disconnects; will automatically open breakers and disconnects; must be manually opened A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 37 ILT-10 RO NRC EXAM38. 295004AA1.03 001Unit 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. will automatically open; will will automatically open; will NOT must be manually opened; will must be manually opened; will NOT A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 38 ILT-10 RO NRC EXAM39. 295005G2.2.37 001Unit 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. will; must be manually transferred will; will automatically transfer will NOT; must be manually transferred will NOT; will automatically transfer A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 39 ILT-10 RO NRC EXAM40. 295006AK1.02 001Unit 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 Position26-31 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. is; are is; are NOT is NOT; are is NOT; are NOT A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 40 ILT-10 RO NRC EXAM41. 295007AA2.02 001Unit 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 isALLOWED to be manually ARMED is __________ .

At 10:11, based on SRV positions, Reactor Power is approximately __________ . 10:05; 6% RTP 10:05; 11% RTP 10:08; 6% RTP 10:08 11% RTP A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 41 ILT-10 RO NRC EXAM42. 295010AK3.01 001Unit 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 Drywellpressure 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 __________ . is NOT; 1T48-R615A is NOT; 1T48-F336A is; 1T48-R615A is; 1T48-F336A A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 42 ILT-10 RO NRC EXAM43. 295014G2.1.28 001Unit 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. WHEN the 2E41-F001, HPCI Turb Steam Supply valve, indicates full CLOSED; prevent HPCI from automatically restarting WHEN the 2E41-F001, HPCI Turb Steam Supply valve, indicates full CLOSED; allow HPCI to automatically restart ONLY after HPCI TURBINE BRG OIL PRESS LOW, 601-112, alarm is received; prevent HPCI from automatically restarting ONLY after HPCI TURBINE BRG OIL PRESS LOW, 601-112, alarm is received; allow HPCI to automatically restart A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 43 ILT-10 RO NRC EXAM44. 295016AA2.01 001The 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 ControlRoom, 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. ONLY one CRD pump; the Plant Process Computer ONLY one CRD pump; SPDS BOTH CRD pumps; the Plant Process Computer BOTH CRD pumps; SPDS A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 44 ILT-10 RO NRC EXAM45.295017AA1.05 001A Site Area Emergency has just been declared on Unit 2 due to a leak into secondarycontainment. A Prompt Offsite Dose Assessment is in progress but results are unavailable atthis time. SPDS "MIDAS" Screen is attached on the next page.

The following Table is from NMP-EP-111-002, Emergency Notification NetworkCommunicator Instructions - Hatch: Wind Direction From Rally Point Site Exit Route Evacuation Route/

State Reception Center 340º - 60º Gate 17 Main Access Road U.S. Hwy. 1 - North to Toombs Co. High School/ Lyons 61º - 110º PESB Road behind Low Level Radwaste Building U.S. Hwy. 1 - South to Appling Co. High School/ Baxley 111º - 225º PESB Main Access Road U.S. Hwy. 1 - South to Appling Co. High School/ Baxley 226º - 339º PESB Main Access Road EITHER direction on U.S. Hwy. 1 to Toombs Co. High School/ Lyons 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 __________ . have;US #1 North have;US #1 South have NOT;US #1 North have NOT;US #1 South A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 4 5 ILT-10 RO NRC EXAM295017AA1.05 002 Wednesday, June 08, 2016 3:49:35 PM 46 ILT-10 RO NRC EXAM46. 295018AA1.01 001Unit 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 ClosedCooling Water, the NPO will __________ the Standby RBCCW pump. A Standby RBCCW pump automatic start signal __________ when the condition clears. confirm the automatic start of; will automatically reset confirm the automatic start of; must be manually reset manually start; will automatically reset manually start; must be manually reset A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 47 ILT-10 RO NRC EXAM47.295019G2.1.32 001On Unit 2, IAW 34AB-P51-001-2, Loss of Instrument And Service Air System Or WaterInstrusion Into the Service Air System, 2P52-F565, Rx Bldg Inst N 2 To Non-Int Air El. 185 Isol Vlv, will FIRST open whenNon-Interruptible Essential Air Pressure DECREASES to __________ .IF 2P52-F565 is continuously cycling, THEN 2P52-F565 is OPENED and the supply breakeris turned OFF to __________ .90 psig; stabilize nitrogen system pressure90 psig;prevent failure of the valve motor80 psig;stabilize nitrogen system pressure80 psig;prevent failure of the valve motorA.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 4 8 ILT-10 RO NRC EXAM48. 295020AK2.01 001Unit 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. RPS Bus 2A; Outboard RPS Bus 2A; Inboard RPS Bus 2B; Outboard RPS Bus 2B; Inboard A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 49 ILT-10 RO NRC EXAM49.295021AA1.06 001Unit 2 is shutdown with RHR Loop A aligned for Shutdown Cooling with the followingconditions: oReactor ShutdownTwo (2) days ago oThe Drywell is open and available for accesso2B21-F003, Reactor Head Vent ValveOPEN o2B21-F004, Reactor Head Vent ValveOPEN o2B21-F005, Reactor Manual Head Vent Valve CLOSEDSubsequently, 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 isexpected to reach 212°F in approximately __________ . If Reactor bulk coolant temperature reaches 250°F, Drywell temperature indications will __________ . REFERENCE PROVIDED 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 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 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 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 A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 5 0 ILT-10 RO NRC EXAM50. 295023AK1.01 001Both 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 risingfrom 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 DuringHandling, is REQUIRED is __________ . has; 13:00 has; 13:03 has NOT; 13:00 has NOT; 13:03 A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 51 ILT-10 RO NRC EXAM51.295024EK2.13 001Unit 2 is operating at 75% RTP. Reactor power is being reduced due to a leaking SRV. The following conditions exist: oDrywell pressure 0.4 psigoTorus pressure0.2 psig oRHR pump 2Aoperating oTorus Coolingin service oTorus Sprayin 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. 13:05; is 13:05; is NOT 13:03; is 13:03; is NOT A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 5 2 ILT-10 RO NRC EXAM52. 295025EA2.01 00131EO-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 __________ . RAISE the setpoint on 2E41-R612, HPCI flow controller LOWER the setpoint on 2E41-R612, HPCI flow controller throttle 2E41-F011, Test to CST VLV, in the CLOSE direction throttle 2E41-F011, Test to CST VLV, in the OPEN direction A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 53 ILT-10 RO NRC EXAM53. 295026EK3.05 001Unit 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 Torustemperature reaches __________ limit. 106°F; the BIIT Curve 106°F; any ECCS NPSH 111°F; the BIIT Curve 111°F; any ECCS NPSH A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 54 ILT-10 RO NRC EXAM54.295028G2.4.31 001Unit 2 is operating at 100% RTP when a small pipe break in the Drywell occurs.oDrywell Pressure has increased to 2.5 psigoDrywell Temperature has increased to 130°FBased on the above conditions and IAW 31EO-EOP-100-2, Miscellaneous EmergencyOverrides,The HIGHEST listed Drywell temperature point at which the Drywell Chillers are allowed to be restarted is __________ . 149°F249°F279°F339°FA.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 5 5 ILT-10 RO NRC EXAM55.295030EK3.01 001Unit 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 pipingfrom the CST can be used. If the leak can NOT be isolated, the reason for performing an Emergency Depressurizationon low Torus water level is to prevent __________ . Core Spray; direct pressurization of the Torus air space Core Spray; excessive loading of the SRV tail pipes and supports HPCI; direct pressurization of the Torus air space HPCI; excessive loading of the SRV tail pipes and supports A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 5 6 ILT-10 RO NRC EXAM56.295031EK2.11 001Unit 1 is operating at 100% RTP.

An event occurs causing RWL to decrease and results in the following 1C32-R606A-C GEMAC, indications: Time RWL10:00 +40 inches and steady 10:01 +5 inches and decreasing 10:02 -5 inches and decreasing10:15 +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 __________ .

10:01; ILLUMINATE 10:01; EXTINGUISHED 10:02;

ILLUMINATED 10:02;

EXTINGUISHED A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM57 ILT-10 RO NRC EXAM57. 295032EA2.01 001Unit 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 toincrease. Time HPCI Room Temp01:00 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), willautomatically start is __________ .

The EARLIEST listed time that HPCI will have RECEIVED an automatic isolation signal is __________ . 01:00; 01:15 01:00; 01:20 01:05; 01:15 01:05; 01:20 A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 58 ILT-10 RO NRC EXAM58. 295037EA1.10 001Unit 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. 2C41-F034, SBLC Combined Drain Valve; closed 2C41-F034, SBLC Combined Drain Valve; open 2C41-F015, SBLC Suction Line Drain Valve; closed 2C41-F015, SBLC Suction Line Drain Valve; open A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 59 ILT-10 RO NRC EXAM59. 295038EK1.02 001Unit 2 was operating at 100% RTP when a radiological event occurred resulting in an automaticstart 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 _________ normallyREQUIRED to maintain adequate negative Reactor Building dP. 09:01; ONLY one (1) SBGT Train is 09:01; BOTH SBGT Trains are 10:01; ONLY one (1) SBGT Train is 10:01; BOTH SBGT Trains are A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 60 ILT-10 RO NRC EXAM60. 300000K2.01 001The power supply for Unit 2 Station Service Air Compressor (SSAC) 2A is __________ . The power supply for Unit 2 SSAC 2C is __________ . 600VAC Bus 2C; 600VAC Bus 2A 600VAC Bus 2C; 600VAC Bus 2BB 600VAC Bus 2D; 600VAC Bus 2A 600VAC Bus 2D; 600VAC Bus 2BB A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 61 ILT-10 RO NRC EXAM61. 400000A2.04 001The 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 __________ . will; Chemistry to sample Circulating Water to determine if effluent limits have been exceeded will; the Radwaste Operator to confirm closed / close this discharge flowpath will NOT; Chemistry to sample Circulating Water to determine if effluent limits have been exceeded will NOT; the Radwaste Operator to confirm closed / close this discharge flowpath A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 62 ILT-10 RO NRC EXAM62. 400000K3.01 001Unit 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 willresult in a RWCU system isolation is __________ . This isolation signal will result in automatic closure of ONLY the __________ , Rx Water Cleanup Valve. 130°F; 1G31-F001 130°F; 1G31-F004 140°F; 1G31-F001 140°F; 1G31-F004 A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 63 ILT-10 RO NRC EXAM63. 500000EK1.01 001The LOWEST listed Hydrogen concentration that will REQUIRE entry into31EO-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 __________ . 1.6%;

Torus 1.6%;

Drywell 1.9%;

Torus 1.9%;

Drywell A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 64 ILT-10 RO NRC EXAM64. 600000AA2.14 001Unit 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 toaid in suppressing the fire.

Based on the above conditions, Shutdown Cooling can be placed into service using __________ to achieve and maintain aCold Shutdown condition. RHR pump 1B and RHRSW pump 1C RHR pump 1B and RHRSW pump 1D RHR pump 1C and RHRSW pump 1C RHR pump 1C and RHRSW pump 1D A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 65 ILT-10 RO NRC EXAM65. 700000G2.4.45 001Unit 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. 1E; will 1E; will NOT 1G; will 1G; will NOT A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 66 ILT-10 RO NRC EXAM66. G2.1.5 001Both Units are operating at 100% RTP.

Based on the above conditions and IAW NMP-AD-016-003, Scheduling and Calculating WorkHours, 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 _________ . 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 /> 14 hours; 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 16 hours; 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> 16 hours; 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 67 ILT-10 RO NRC EXAM67. G2.1.44 001Unit 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. is; is is; is NOT is NOT; is is NOT; is NOT A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 68 ILT-10 RO NRC EXAM68. G2.2.38 001IAW the Unit 1 Facility Operating License, Southern Nuclear is authorized to operate Plant Hatch at a MAXIMUM steady-state reactor core power level of __________ . 2777 MWth 2790 MWth 2800 MWth 2804 MWth A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 69 ILT-10 RO NRC EXAM69. G2.2.40 001Unit 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 beoperable, without requiring entry into a Required Action Statement (RAS), is __________ . A RHR SDC subsystem __________ REQUIRED to be in operation. one (1);

is one (1);

is NOT two (2);

is two (2);

is NOT A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 70 ILT-10 RO NRC EXAM70. G2.2.43 001On 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 theannunciator number label under the annunciator window. The installed magnetic tile will be __________ . yellow; labeled with a "P" yellow; blank white; labeled with a "P" white; blank A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 71 ILT-10 RO NRC EXAM71. G2.3.7 001Unit 2 is operating at 100% RTP with a steam leak in the 2A SJAE room. A SO has beenassigned 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 ofinformation you would expect to find on this type of RWP. Specific; the current Reactor Mode Specific; Digital Alarming Dosimeter (DAD) settings General; the current Reactor Mode General; Digital Alarming Dosimeter (DAD) settings A.B.C.D.Wednesday, June 08, 2016 3:49:35 PM 72 ILT-10 RO NRC EXAM72. G2.3.11 001Unit 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 ofWaste Sample Tank A to the canal. will automatically terminate; ONLY one (1) restart is will automatically terminate; NO restarts are must be manually terminated; ONLY one (1) restart is must be manually terminated; NO restarts are A.B.C.D.Wednesday, June 08, 2016 3:49:36 PM 73 ILT-10 RO NRC EXAM73. G2.3.15 001The 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 __________ . RPS Bus B & Instrument Bus 1A; EXITING the Main Stack RPS Bus B & Instrument Bus 1A; ENTERING the Main Stack 24/48 VDC Cabinet 1A & 1B EXITING the Main Stack 24/48 VDC Cabinet 1A & 1B ENTERING the Main Stack A.B.C.D.Wednesday, June 08, 2016 3:49:36 PM 74 ILT-10 RO NRC EXAM74. 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 Power01:00 APRMs indicate 4% RTP 01:10 IRMs on Range 7 01:20 IRMs on Range 5 01:30 SRMs indicate 6.0 x 10 4 CPS Based on the above conditions and IAW the EOPs, The EARLIEST time the reactor can be declared SHUTDOWN with the reactorSUBCRITICAL is at __________ . 01:00 01:10 01:20 01:30 A.B.C.D.Wednesday, June 08, 2016 3:49:36 PM 75 ILT-10 RO NRC EXAM75. G2.4.42 001An 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 __________ . an Alert Emergency; Classroom 172, Simulator Building an Alert Emergency; the Main Control Room a Notification of Unusual Event; Classroom 172, Simulator Building a Notification of Unusual Event; the Main Control Room A.B.C.D.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: LOSS OF SHUTDOWN COOLING DOCUMENT NUMBER: 34AB-E11-001-2 Ver No: 6.15 ATTACHMENT 1 Att. Pg. TITLE: CORE FUEL IN UNFLOODED RPV 1 of 2 Case 1 : CORE FUEL in UNFLOODED RPV Days After Shutdown Heat Load (MBTU/hr) Saturation Time Evaporation Time Boil-Off 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