ML15316A134

Farley Initial Exam 2015-301 Final SRO Written Exam

ML15316A134
Person / Time
Site:	Farley
Issue date:	11/10/2015
From:	Division of Reactor Safety II
To:	Southern Nuclear Operating Co
References
50-348/15-301, 50-364/15-301
Download: ML15316A134 (108)

Text

ES-401, Page 38 of 50 ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet

U. S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name: Date: Facility / Unit Region: I II III IV Reactor Type: W CE BW GE Start Time: Finish Time: Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80 percent overall, with 70 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.

Applicant Certification

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

__________________________________

Applicant's Signature Results RO/SRO-Only/Total Examination Values ______ / ______ / ______

Points Applicant's Score ______ / ______ / ______

Points Applicant's Grade ______ / ______ / ______

Percent

1. Unit 1 is starting up IAW UOP-1.2, Startu p of Unit from Hot Standby to Minimum Load, with the following condition:* Reactor Power is 13%.

The CONTROL ROD MOT ION switch has been released following a rod withdrawal when the following occurs:

• Rods step out continuously.

Which one of the following co mpletes the statements below?

The first action directed by AOP-19.0, Malf unction of Rod Control System, is to (1) .With NO operator action t he C-1, IR Hi Flux Rod Stop, (2) stop the outward rod motion.

(1) manually Trip the Reactor (2) will NOT(1) place ROD CONTROL BANK SELECTOR SWITCH in AUTO (2) will NOT (1) manually Trip the Reactor (2) WILL(1) place ROD CONTROL BANK SELECTOR SWITCH in AUTO (2) WILLA.B.C.D.

2. Unit 1 is performing a Reactor start up at MOL with the fo llowing conditions:* UOP-1.2, Startup of Unit From Hot Standby to Minimum L oad, is in progress.* The OATC has stabilized Reactor power.* NI-35 and NI-36, INTERMEDIATE RANGE,

indicate 1x10

-8 AMPS.Subsequently, control rods are withdrawn 3 steps.

Which one of the following co mpletes the statements below?

Reactor Power will rise then stablize (1) the POAH.The first indication of reaching the POAH is rising (2) . (1)

(2) below Pressurizer Level at Pressurizer Level below S/G Pressure at S/G Pressure A.B.C.D.

3. Unit 1 is at 25% power w hen the following conditions occur:

At 1000:* 1A RX COOLANT PUMP AMPS indicates 700 AMPS.

At 1002:

• The 1A RCP motor experiences a Sheared Shaft.

Which one of the following co mpletes the statements below?

At 1002 the 1A RCP will draw (1) electrical current than it did at 1000. The crew is required to immediately enter (2) . (1)

(2) More EEP-0.0, Reactor Trip and Safety Injection Less EEP-0.0, Reactor Trip and Safety Injection More AOP-4.0, Loss of Reactor Coolant Flow Less AOP-4.0, Loss of Reactor Coolant Flow A.B.C.D.

4. Unit 1 is operating at 100% pow er with the following conditions:

• PK-145, LP LTDN PRESS, is set to maintain Letdow n Pressure at 275 psig.

Subsequently, the RCS filter becomes completely clogged and does not allow any flow.

Which one of the following co mpletes the statements below? PK-145 controller demand will (1) . AOP-16.0, CVCS Malfunction, entry conditions (2) been met.

(1)

(2) Rise HAVE Rise have NOT Lower HAVE Lower have NOT A.B.C.D.

5. Which one of the following co mpletes the statement below? Charging Pump Suctions will auto matically align to the RWST when (1) sense(s)

(2) VCT Level.

Level Transmitter Nomenclature LT-115, VCT LVL LT-112, VCT LVL (1)

(2) either LT-115 or LT-112 5% both LT-115 and LT-112 5% either LT-115 or LT-112 15% both LT-115 and LT-112 15%

A.B.C.D.

6. Unit 1 is in MODE 4 with the following conditions:

• Plant cooldown is in progress with the 'A' Train of RHR .

• The OATC raises demand on FK-605A,1A RHR HX BYP FLOW, by 25%.

Which one of the following co mpletes the statements below?

Raising demand on FK-605A will (1)

CCW temperature.

Per SOP-23.0, Component Cooling Water System, the maximum allowableCCW outlet temperature for the CCW HX used for cooldown is (2) . (1)

(2) raise 120°F raise 135°F lower 120°F lower 135°F A.B.C.D.

7. Unit 1 is shutdown when t he following conditions occur:

• The 1A CCW pump tripped.

• The 'A' Train is the ON SERVICE Train.

Which one of the following co mpletes the statement below? Cooling is lost to the (1) RHR Heat Exchanger. The affected RHR train (2) available for transfer to Cold Leg Recirculation.

(1)

(2) 1A is NOT 1A IS 1B is NOT 1B ISA.B.C.D.

8. Unit 1 has experienced a tube rupture on the 1A SG with the following conditions:

• A Loss of All Offsite Power has occurred.

• The operating crew is performing EEP-3, Steam Gener ator Tube Rupture.

• RCS cooldown is in progress.

• INTEGRITY Critical Safety Function Status Tree has turned ORANGE due to the 1A RCS LOOP cold leg temperature dropping rapidly.

Which one of the following co mpletes the statements below? The 1A RCS LOOP cold leg temperat ure drop was caused by increased (1) flow over the 1A RCS LO OP cold leg instrument.

(2) is the highest listed cold leg temperature that could lead to this ORANGE INTEGRITY condition.

(1)

(2) Natural Circulation 270°F Natural Circulation 225°F High Head Safety Injection 270°F High Head Safety Injection 225°F A.B.C.D.

9. A Safety Injection has just occurred on Unit 1.

Which one of the following co mpletes the statement below?

The minimum valve actuations that would lead to HHSI Pump cavitation are .Valve Nomenclature:

LCV-115C, VCT OUTLET ISO LCV-115E, VCT OUTLET ISO

LCV-115D, RWST TO CHG PUMP

LCV-115B, RWST TO CHG PUMP LCV-115C or LCV-115E opening LCV-115C and LCV-115E opening LCV-115B or LCV-115D closing LCV-115B and LCV-115D closing A.B.C.D.

10. Nitrogen addition to the PRT on Unit 1 is in progress when the following occurs:

• V-042, PRT N2 PRESS REG, fails causing PRT pressure to RISE.

• PI-472, PRT PRESS, st ablizes at 15.0 psig.

Which one of the following co mpletes the statements below? HE5, PRT PRESS HI, (1) in alarm. Per SOP-1.2, Reactor Coolant Pressure Relief System, normal nitrogen pressure prevents (2) . (1)

(2) IS excessive corr osion due to oxygen is NOT excessive co rrosion due to oxygen IS an explosive mixture of oxygen and hydrogen is NOT an explosive mi xture of oxygen and hydrogen A.B.C.D.

11. Unit 1 is operating at 100% power when the following conditions occur:

• A large break has occu rred at the inlet of a Pressurizer Safety Valve.

Subsequently, the followi ng condition exists:

• Pressurizer Pressure is 1600 psig.

• Charging Pump miniflow valves are open.Which one of the following co mpletes the statements below? Per EEP-0, Reactor Trip or Safety Injection, the crew (1) required to close the Charging Pump miniflow valves. Closing the Charging Pump miniflow valves when required will ensure (2) . (1)

(2) IS HHSI pump injecti on flow is maximized is NOT HHSI pump inject ion flow is maximized IS HHSI pump heat is removed is NOT HHSI pump heat is removed A.B.C.D.

12. Unit 1 is operating at 100% power with the following conditions:

• A dual unit LOSP occurs.

Subsequently, Unit 2 experiences a Safety Injection.

Which one of the following comp letes the statement below for Unit 1? The (1) CCW pump is being powered by the (2) DG. (1)

(2) 1A 1-2A 1A 1C 1C 1-2A 1C 1CA.B.C.D.

13. Unit 1 is in MODE 5 with the following conditions:

• A cooldown is in progress.

• RHR is on service.

Subsequently, the following conditions occur:

• V-8708A, RHR SUCTION RELIEF

, has lifted and is stuck open.

Which of the following tank levels will immediately rise due to the malfunction?

PRTRHTWHTRCDTA.B.C.D.

14. A Design Basis Large Break LO CA has occurred on Unit 1.

Which one of the following co mpletes the statements below? The Accumulators will inject directly to the (1) . The purpose of the Accumula tor design capacity is to (2) refill the Reactor Vessel fo llowing a design basis accident.

(1)

(2) Hot Legs partially Hot Legs

completely Cold Legs partially Cold Legs completely A.B.C.D.

15. Unit 1 is operating at 100% power and the following conditions exist:

• Pressurizer Pressure is 2240 psig.

• Tavg is 572°F.

• Pressurizer Level Control is in manual.

• Pressurizer Level is 60%.

• 600V LCC 1M has lost power.

Which one of the following co mpletes the statements below? Power has been lost to the (1) Pressurizer Heater Group. Pressurizer Heater Groups A and B are currently (2) . (1)

(2) D Energized D De-Energized E Energized E De-Energized A.B.C.D.

16. Unit 1 is operating at 100% Power when the following conditions occur:

• A short circuit occurs in PT-445, PRZR PRESS.

• Pressurizer Pressure remains stable.

Which one of the following co mpletes the statement below? The Pressurizer Pressure input to the Reactor Protection System will NOT be affected by this malfun ction due to the use of

.an independent control channel a median signal selector isolation devices de-energize to actuate bistables A.B.C.D.

17. Unit 1 is operating at 100% power and th e following occurs:

• A Safety Injection follow ed by an LOSP on Unit 1.

Several minutes following the safety in jection the following condition exists:

• The 1B DG is running with the output breaker open.

Which one of the following co mpletes the statements below? SOP-0.8, Transient Response Procedure User's Guide, (1) require a procedure be used prior to closing the 1B DG output breaker. The B1G sequencer (2) energize the 1C Air Compressor.

(1)

(2) DOES DOES DOES does NOT does NOT DOES does NOT does NOT A.B.C.D.

18. The 1D Vital Panel becomes de-energized on Unit 1.

Which one of the following co mpletes the statements below. The 'B' Train SI actuated MOVs (1) automatically stroke upon an SI actuation. 'B' Train ESF pumps (2) be started in LOCAL at the HSDP.

(1)

(2) WILL CAN WILL CANNOT will NOT CAN will NOT CANNOT A.B.C.D.

19. Which one of the following completes the statements below? The C-11, Bank D Stop, is actuated by input from (1) at a Bank D rod height of (2) steps. (1)

(2) Digital Rod Position Indication 220 Digital Rod Position Indication 228 the Pulse-to-Analog Converter 220 the Pulse-to-Analog Converter 228 A.B.C.D.

20. Unit 1 is in MODE 3 and the following RCP temperatures are observed:

MotorBearingTemperatureMotorStatorTemperature 1ARCP190°F235°F 1BRCP200°F220°F 1CRCP190°F230°F Which one of the following co mpletes the statement below? Only the is (are) required to be secured.

1A RCP 1B RCP1A and 1B RCPs 1A and 1C RCPs A.B.C.D.

21. Which one of the following conditions would cause a Core Exit Thermocouple (CETC)monitor alarm? 1. ANY CETC input disconnected. 2. ONLY 10 valid CETCs.

3. ANY CETC temperature at 650°F.

1 ONLY 1 AND 3 ONLY 2 ONLY1, 2, AND 3 A.B.C.D.

22. Unit 1 is operating at 100% power when the following conditions occurred:

• 1B Charging Pump is started.

• 1A Charging Pump is secured.

• 1B CHG PUMP AMPS, begins to oscillate.

• FI-122A, CHG FLOW, begins to oscillate.

Subsequently, the following annunc iators come into alarm:

• EA2, CHG HDR FLOW HI-LO.

• DD1, RCP SEAL INJ FLOW LO.

• DE1, REGEN HX LTDN FLOW DISCH TEMP HI.

Which one of the following co mpletes the statements below? The alarms above are indicative of (1) . The maximum 1A RCP seal injection flowrate that would cause DD1 to alarm is (2) . (1)

(2) FCV-122 closing 6 gpm 1B Charging Pump Cavitation 6 gpm FCV-122 closing 3 gpm 1B Charging Pump Cavitation 3 gpm A.B.C.D.

23. Unit 1 is operating at 100% power with the following conditions:

• A Large Break LOCA occurs.

Subsequently, a Loss of Offsite Power occurs.

Which one of the following co mpletes the statement below 5 minutes after theLoss of Offsite Power?

(1) Containment Cooler Fans are running in slow speed. The reduced speed prevents CTMT cooler (2) due to high moisture content in the Containment atmosphere. (1)

(2) 2 fan motor overload 4 fan motor overload 2 cooling coil impingement damage 4 cooling coil impingement damage A.B.C.D.

24. Unit 1 is in MODE 5 and the following condition exists:

• Both Trains of RHR are oper ating in the cooldown alignment.

• Power is aligned to the RHR suction valves.

• Tavg is 195°F.

Subsequently, the following condition occurs:

• PT-402, 1C LOOP RCS NR PRESS, fails to 500 psig.

Which one of the following co mpletes the statements below? MOV-8701A, 1C RCS L OOP TO 1A RHR PUMP, (1) automatically close. IF MOV-8701A closes, th en AOP-12.0, Residual Heat Removal System Malfunction, entry (2) required.

(1)

(2) DOES is NOT does NOT is NOT DOES IS does NOT IS A.B.C.D.

25. Unit 1 is Shutdown following a LOCA with the following conditions:

• PR-950, CTMT PRESS, peaked at 3.2 psig.

• ECP-1.1, Loss of Em ergency Coolant Recirculat ion, is in progress.

Which one of the following co mpletes the statments below: Per ECP-1.1, the minimum CTMT Sump Level that can supp ort Containment Spray pump operation is

. 2.0 ft3.8 ft 4.5 ft 5.3 ft A.B.C.D.

26. Unit 1 is operating at 100% power when the following condition occurs:

• PK-444A, PRZR PRESS REFE RENCE, demand fails to 0%.

Which one of the following co mpletes the statements below? Initially, (1) PORV(s) will OPEN automatically. PCV-444C, 1A LOOP SPRAY VLV, will (2) . (1)

(2) only ONE CLOSE only ONE OPEN BOTH CLOSE BOTH OPEN A.B.C.D.

27. Unit 1 is operating at 100% power with the following conditions:

• Containment Mini-P urge is in operation Subsequently, the following conditions occur:

• A Main Steam Line br eaks inside Containment

• PR-950Z, CTMT PRESS, stablizes at 14.5 psig.

Which one of the following co mpletes the statements below? CTMT Mini-Purge supp ly and exhaust fans (1) tripped automatically due to a Containment Ventilation Isolation signal. CTMT Mini-Purge supp ly and exhaust dampers (2) closed automatically due to a Containment Ventilation Isolation signal. (1)

(2) HAVE HAVE HAVE have NOT have NOT HAVE have NOT have NOT A.B.C.D.

28. Unit 1 is operating at 100% power with the following conditions:

• STP-33.2A, Reactor Trip Breaker Tr ain A Operability Test, is in progress.

• Reactor Trip Br eaker A is OPEN.

• Reactor Trip Bypass Breaker A is CLOSED.

• Reactor Trip Br eaker B is CLOSED.

Subsequently, the following conditions occur:

• An automatic reactor trip signal is generated.

• The Reactor does NOT trip.

Which one of the following co mpletes the statements below? When the RX TRIP ACTUATION switch is taken to TRIP (1) will OPEN. Per EEP-0, Reactor Trip or Safety Injection, if the RX TRIP ACTUATION switches fail to trip the Reactor, the next action required is to (2) . (1) ONLY Reactor Trip Breaker B (2) trip the MG set supply breakers (1) BOTH Reactor Trip Bypass Break er A and Reactor Trip Breaker B (2) trip the MG set supply breakers (1) ONLY Reactor Trip Breaker B(2) insert Control Rods manually (1) BOTH Reactor Trip Bypass Break er A and Reactor Trip Breaker B(2) insert Control Rods manually A.B.C.D.

29. Unit 2 is starting up per UOP-1.2, Startup of Unit From Hot Standby To Minimum Load, with the following conditions:

• Main Steam Header Warm Up is in Progress.

Which one of the following actions w ould cause the 2B SG Pressure tolower due to increased steam de mand from the 2B SG?

Lower PC-3371B, 2B MS ATMOS REL VLV, SETPT in AUTO.

Lower PC-3371B, 2B MS ATMOS REL VLV, OUTPUT in MAN.

Lower PK-464, STM HDR PR ESS, OUTPUT in MAN.

Lower PK-464, STM HDR PRESS, SETPT in AUTO.

A.B.C.D.

30. Unit 1 is responding to a SGTR in the 1A SG with the following conditions:

At 1000:

• HIGHEST CORE EXIT TEMP CHAN A and B on the IPC, indicates 530°F.

• 1A SG PRESS is 810 psig.

• PI-403A, 1A LOOP RCS WR PRESS, indicates 1230 psig.

• RCS cooldown is in progress.

At 1045:

• HIGHEST CORE EXIT TEMP CHAN A and B, on t he IPC indicates 450°F

.

• 1A SG PRESS is 300 psig.

• PI-403A, 1A LOOP RCS WR PRESS, indicates 565 psig.

Which one of the following co mpletes the statements below? Compared to the conditions at 1000, RCS subcooling at 1045 has (1) . Compared to the conditions at 1000, SG tube leakage rate at 1045 has (2) . Reference Provided (1)

(2) risen risen risen lowered lowered lowered lowered risen A.B.C.D.

31. Unit 1 is in Mode 3 at EOL with the following conditions:

• A Reactor Startup is being planned for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a reactor trip.

• Tavg is being maintained by the Atmospheric Relief Valves (ARVs).

• The Estimated Critical Condition (ECC) calculation predicts criticality at 100 steps on Control Bank D.

Which one of the following conditions will re sult in critical rod height being HIGHER than the value pred icted by the ECC?

For your answer, consider that no operator actions are taken to mitigate or compensate for the below events.

A dilution of 500 gallons is performed.

Auxiliary Feedwater flow is RAISED to all SGs.

A post maintenance test results in the closure of all ARVs.

Reactor startup occurs 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> s after the reactor trip.

A.B.C.D.

32. Unit 2 is at 68% power ramping down due to a problem with #4 Governor Valve with the following conditions:* EH is isolated to #4 Governor valve.

• A subsequent failure causes #2 Governor Valve to fail closed.* Turbine load drops to 450 MW.

Which one of the following co mpletes the statements below? The #2 governor valve closure results in (1) . Per SOP-72.0, General Instructions for DEH Operators Console, the operating crew is required to (2) .(1) automatic removal of the IMP Press Loop(2) trip the Main Turbine (1) automatic removal of the IMP Press Loop(2) match reactor power with turbine load (1) opposed governor valve closure(2) trip the Main Turbine (1) opposed governor valve closure(2) match reactor power with turbine load A.B.C.D.

33. Unit 1 is operating at 100% power with the following conditions:

AT 1000:

• 1A Circulating Water Pump Trips.

AT 1005:

• KK1, TURB COND VAC LO, comes into alarm Which one of the following co mpletes the statements below?

(1) is the earliest ti me AOP-8.0, Partial Loss of Condenser Vacuum, entry is required.

At 100% Reactor power, (2) is the lowest c ondenser pressure a manual Reactor Trip is required.

(1)

(2) 1000 3.800 psia 1005 3.800 psia 1000 2.901 psia 1005 2.901 psia A.B.C.D.

34. Unit 1 entered FRP-H.1, Response to Loss of Secondary Heat Sink, with the following conditions: Time1000101510301100 1AS/GWRLVL(%)37.0028.0018.0011.00 1BS/GWRLVL(%)32.0020.0010.006.00 1CS/GWRLVL(%)29.0019.009.003.00CNMTPRESS(PSIG)1.502.003.004.50 AFWTOTALFLOW(GPM)0000 Which one of the following is the EARLIEST time that a manual Safety Injection is required due to meeting Bleed and Feed criteria per FRP-H.1?

1000101510301100A.B.C.D.

35. Which one of the following is the purpose of depressurizing all intact SGs during the performance of ECP-0.0, Loss of All AC Power?

Rapidly reduces DP across SG U-tubes to minimize RCS inventory loss from a potential tube rupture.

Cools RCP seals in a cont rolled manner and minimizes loss of RCS inventory.Maximizes Natural Circulation flow before reflux cooling begins as theRCS becomes saturated.

Maximizes Natural Circula tion flow to allow r eactor vessel head to cool since CRDM cooling fans are unavailable.

A.B.C.D.

36. Unit 1 is operating at 100% power and the following condition exists:

• Main Condenser Pressure is rising due to a failure of the 1A SJAE.

Which one of the following co mpletes the statements below? Main Condenser Hotwell Te mperature w ill initially (1) . AOP-8.0, Partial Loss of Conden ser Vacuum, will direct placing (2) on service.

(1)

(2) RISE a Hogger LOWER a Hogger RISE the 1B SJAE LOWER the 1B SJAE A.B.C.D.

37. The following conditions exist:

• Unit 1 is in MODE 5.

• Unit 2 is operating at 100% power.

• The 1B DG is INOPERABLE.

Subsequently, the following occurs simultaneously:

• 4160V busses 1F, 1K, 1G, and 1L de-energize.

• 4160V busses 2F, 2K, 2G, and 2L de-energize.

• The 1-2A DG Trips and cannot be restored.

Which one of the following co mpletes the statement below? The first procedure the Unit 1 Operating Crew is required to enter is (1) . The Operating Crew will restore power to Unit 1 with the (2) .(1) AOP-5.0, Loss of A or B Train Electrical Power (2) 1C DG(1) ECP-0.0, Loss of All AC Power (2) 1C DG (1) AOP-5.0, Loss of A or B Train Electrical Power (2) 2C DG (1) ECP-0.0, Loss of All AC Power (2) 2C DG A.B.C.D.

38. Which one of the following completes the statement below? The Main Turbine exhaust hood sprays use (1) to automatically prevent excessive temperatures at the exhaust of the LP Turbine (2) 15% Turbine Load. (1)

(2) demin water above demin water below condensate above condensate below A.B.C.D.

39. Unit 1 is operating at 100% power when the following occurs:

• The 1C 120 VAC Vital Instrum entation Panel is de-energized.

Which one of the following co mpletes the statements below?

LCV-459, LTDN LINE ISO, (1) automatically close if a Pressurizer Low Level condition occurs. LCV-115A (2) immediately divert to the RHT. (1)

(2) WILL WILL WILL will NOT will NOT WILL will NOT will NOT A.B.C.D.

40. Unit 1 is operating at 8% power and the following conditions occur:* The Battery Input Breaker on the 1B inverter trips.

• WD2, 1B INV FAULT, annunciator alarms.

• No Other Annunciators are in Alarm due to the fault.

Subsequently, the Rover reports the followi ng indications from the 1B Inverter.

• INVERTER POWERING LOAD lamp NOT lit.

• BYPASS SOURCE AVAIL ABLE lamp is LIT.

Which one of the following co mpletes the statements below? The 1B 120V Vital AC panel is (1) . The 1B INVERTER AMPERES meter on the EPB indicates (2) .(1) Energized (2) 0 Amps (1) Energized (2) Full Load Amps(1) De-energized (2) 0 Amps. When the MANUA L BYPASS SWITCH is taken to BYPASS SOURCE TO LOAD positi on it will indicate Full Load Amps.(1) De-energized (2) 0 Amps. When the MANUA L BYPASS SWITCH is taken to BYPASS SOURCE TO LOAD position it will continue to indicate 0 Amps.

A.B.C.D.

41. Unit 1 is operating at 100% power when the following conditions occur:

• Annunciator KB4, SGFP SUCT PRESS LO, alarms

• PR-4039, SGFP SUCT PRESS, indicates 300 psig and lowering.

Which one of the following co mpletes the statement below? The earliest time the standby condensate pump will start is when

.KB4 has been in alarm for 10 seconds KB4 has been in alarm for 30 seconds SGFP suction pressure has rema ined below 275 PSIG for 10 seconds SGFP suction pressure has rema ined below 275 PSIG for 30 seconds A.B.C.D.

42. A gas transfer is in progress to the #8 Waste Gas Decay Tank on Unit 1 when the following conditions occur:

• The #8 Waste Gas Decay Tank relief valve lifts.

• The relief valve fails to reseat.

Which one of the following co mpletes the statements below?

The relief valve lifting will initially be detected by (1) . The release (2) be automatically isolated from the environment if an alarm condition exists. (1)

(2) R-13, WASTE GAS MONITOR WILL R-13, WASTE GAS MONITOR will NOT R-14, PLANT VENT MONITOR WILL R-14, PLANT VENT MONITOR will NOT A.B.C.D.

43. Unit 1 is Operating at 100% Reactor Power when the following conditions occur: Time1000100510101015 1AS/GNRLVL(%)26.0023.0021.007.00 1BS/GNRLVL(%)34.0027.0025.008.00 1CS/GNRLVL(%)35.0033.0031.0012.00 1ASGFPSTATUSRunningRunningTrippedTripped 1BSGFPSTATUSRunningRunningTrippedTripped Which one of the following is the earliest time when all AFW Pumps have recieved an AUTO START signal?

1000100510101015A.B.C.D.

44. Unit 1 is operating at 100% power with the following condition:

• An LOSP occurs.

Which one of the following co mpletes the statements below?

10 seconds after power is restored to the 1F 4160V bus: 1A CHG PUMP AMPS will indicate (1) AMPS.

1A MDAFWP AMPS will indicate (2) AMPS. (1)

(2) greater than zero greater than zero greater than zero zero zero greater than zero zero zero A.B.C.D.

45. Unit 1 is operating at 100% power when the following condition occurs:

• The Reactor Trips

Subsequently, the following indications are displayed continously on the MCB.* V-515, SW TO TURB BLDG ISO A TRN, RED and GREEN Lights are LIT.* V-517, SW TO TURB BLDG ISO B TRN, RED and GREEN Lights are LIT.

• V-516, SW TO TURB BLDG ISO A TRN, RED and GREEN Lights are LIT.* V-514, SW TO TURB BLDG ISO B TRN, RED and GREEN Lights are LIT.

Which one of the following co mpletes the statement below? The valve actuation was initiated by a (1) . The valve position prevents (2) .(1) Safety Injection (2) damage to turbine building auxiliaries.(1) Loss of Offsite Power (2) complete isolation of SW flow to the Air Compressors(1) Safety Injection (2) complete isolation of SW flow to the Air Compressors(1) Loss of Offsite Power (2) damage to turbine building auxiliaries.

A.B.C.D.

46. Which one of the following completes the statements below? The (1) RCP(s) can be powered from the 1A Startup Transformer. The (2) RCP(s) can be powered from the 2B Startup Transformer.

(1)

(2) 1A RCP 2A RCP 1A RCP 2B and 2C RCPs 1B and 1C RCPs 2A RCP 1B and 1C RCPs 2B and 2C RCPs A.B.C.D.

47. Unit 1 is at 100% power when the following condition occurs in the AuxBldg DC distribution system:

• The 125V DC Bus 1B has been de-energized.

Subsequently, an LOSP occurs on Unit 1.

Which one of the following co mpletes the statements below?The 1B DG (1) be started fr om the EPB. The B1G Sequencer (2) automatically sequence loads.

(1)

(2) CAN WILL CANNOT will NOT CANNOT WILL CAN will NOT A.B.C.D.

48. Which one of the following completes t he statement below for the 1B DG AirRecievers? The maximum Air Receiver pressure th at will cause an alarm on the 1B DG Local Control Panel is (1) .At the alarm setpoint t here is enough air pressure to ensure a maximum of (2) start attempts are available.

(1) (2) 200 psig 3 200 psig 5 350 psig 3 350 psig 5 A.B.C.D.

49. Unit 1 is operating at 100% power when the following conditions occur:

• MH1, FIRE, annunciator on the Unit 1 Main Control Board (MCB) alarms. * "Aux Bldg El 139 W Side Det 1A-39, 43, 46, 53 1A-55, 59, 106", light is lit on the Control Room Fire Panel.

• The Rover reports that the window fo r 1A-59 at the PYR-A-LARM panel is lit.What is (are) the minimum required action(s) to ens ure MH1, FIRE, will alarm again if 1A-39 co mes into alarm?

The Control Room Fire Panel alarm must be acknowledged.

and 1A-59 must be placed in OVE RRIDE on the PY R-A-LARM panel.

The Control Room Fire Panel alarm must be acknowledged.

and The Reflash Panel alarm for detection system 1A-59 must be acknowledged.

ONLY 1A-59 must be placed in OVERRIDE on the PYR-A-LARM panel.ONLY the Reflash Panel alarm for detection system 1A-59 must be acknowledged.

A.B.C.D.

50. AOP-28.0, Control Room Inaccessi bility, is in progress on Unit 1.

Which one of the following co mpletes the statements below?

The 1A MDAFWP will be oper ated in LOCAL at the (1) HSDP. Operator action is requi red to control the MDAFWP

FCVs in LOCAL at the HSDP in order to prevent (2) . (1)

(2) F low SG water level due to valve position F isolating letdown due to cooldown A low SG water level due to valve position A isolating letdown due to cooldown A.B.C.D.

51. Unit 2 is at 100% power with the following conditions:* A #1 Waste Monitor Tank (WMT) release is in progress with the #1 WMT pump running.

• RCV-18, WMT DISCH TO ENVIRONMENT, is open.

Subsequently R-18, LIQ WAST E DISCH, alarms HIGH.

Which one of the following co mpletes the statements below?RCV-18 will (1)

.The #1 WMT pump will (2)

. (1)

(2) remain open trip remain open continue to run close trip close continue to run A.B.C.D.

52. Unit 1 is operating at 100% power with the following condition:

• A SG Tube Leak is in progress.

• FCV-1152, SGBD HX Outlet Flow Control Valve, is stuck in the OPEN position.

Which one of the following radiation monitors is able to automatically stop a release to the environment due to the SG Tube Rupture?

R-23A, SGBD SRG TK INLET

R-23B, SGBD SRG TK DISCH R-19, SGBD SAMPLE R-70A, SG TUBE LEAK DET A.B.C.D.

53. Unit 1 is operating at 100% power when the following occurs:

• A Large Break LOCA o ccurs inside containment.

• Containment Pressure reaches 35 psig.

Which one of the following co mpletes the statements below? MOV-3024A, EMERG SW FROM 1A CTMT CLR, opened due to a(n)

(1) signal. Each CTMT Cooler will be supplied with approximately (2) GPM of Service Water flow. (1)

(2) Safety Injection 2000 Safety Injection 800 Containment Spray 2000 Containment Spray 800 A.B.C.D.

54. Unit 1 experienced a Safety Injection with LOSP.

Which one of the following co mpletes the statements below? The 1A Charging Pump Room Cooler will automatically start due to a signal generated by the 1A Charging Pump (1) . Controls for starting the Charging Pump Room Coolers (2) located on the BOP Panel. (1)

(2) Breaker ARE Breaker are NOT Room Thermostat ARE Room Thermostat are NOT A.B.C.D.

55. Unit 1 is operating at 100% power with the following conditions:

• The Gross Failed Fuel Detector (GFFD

) has steadily indicated 2500 cpm during the entire fuel cycle.

Subsequently, the following readings are recorded: Time1000110012001300 GFFDIndication(cpm)1.1X1041.5X1044.4X1041.3X105Which one of the following is the earliest time the GFFD will be in High Alarm?

1000110012001300A.B.C.D.

56. Unit 1 is operating at 100% power with the following conditions:

• AOP-5.2, Degraded Grid, has just been entered.

• Voltage on all emergency busses for both units is reading 3875 volts.

• MEGAVARS are reading (+) 100 on the MCB.

• The Shift Supervisor has directed the UO to maintain (+) 400 MVARs in accordance with the voltage schedule.

• The Unit 2 UO maintains MVARS st able on Unit 2 during the adjustment.

Which one of the following will occur when the Unit 1 UO performs the adjustment as directed by the Shift Supervisor?

The operator will (1)

Voltage, to reac h (+) 400 MVARs. After adjusting voltage, the te mperature of large pump motors, such as the RCP or CW pump motors, will (2)

. (1)

(2) raise lower raise rise lower lower lower rise A.B.C.D.

57. Unit 1 was manually tripped from 100% power and the following conditions exist:

• AOP-6.0, Loss of Instrument Air, is in progress.

• The TDAFW pump automatically started.

• BOTH MDAFW pumps failed to start.

• The MSVR is not accessible

.Subsequently, the following report is received from Mechanical Maintenance:

• Restoration of Instrum ent Air will take 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

Which one of the following describes the required AOP-6.0 operator action(s), if any, and the reason?

No action is required be cause the TDAFWP steam admission valves fail to the "as is" position.

Manually close the TDAFWP steam adm ission valves to avoid causing an uncontrolled cooldown.

Manually open the TDAFWP steam admission valves to provide an adequate heat sink.

Manually align emergency air to the TDAFW pum p steam admission valves to provide an adequate heat sink.

A.B.C.D.

58. Unit 1 is operating at 100% power when the following occurs:

At 1000

• An Instrument Air malfunction occurs.

At 1015

• PI-4004B, INST AIR PRESS, indicates 50 psig and stable Which one of the following co mpletes the statements below?

At 1015 V904, Instrument Air to the Service Building, is (1) . A(n) (2) maintains MSIV air pressure following loss of instrument air pressure. (1)

(2) OPEN accumulator OPEN compressed nitrogen cylinder CLOSED accumulator CLOSED compressed nitrogen cylinder A.B.C.D.

59. Unit 1 is shutdown following a LOCA with the following conditions:

• PI-402A and PI-403A, RCS WR PR ESS, indicate 600 psig and stable.

• PR-950Z, CTMT PRESS, indicate s 32 psig and slowly lowering.

Subsequently, ONLY the fo llowing actions are taken:

• SI BLOCK RESET A T RN pushbutton is depressed.

• SI BLOCK RESET B T RN pushbutton is depressed.

• PHASE B CTMT IS O RESET A TRN pushb utton is depressed.

• PHASE B CTMT IS O RESET B TRN pushb utton is depressed.

Which one of the following co mpletes the statements below: PHASE A CNMT ISO (1) reset. PHASE B CNMT ISO (2) reset. (1)

(2) IS is NOT IS IS is NOT is NOT is NOT IS A.B.C.D.

60. Unit 1 is operating at 100% power when the following conditions occur:

• Phase A is actuated using the MCB handswitches.

How has the Phase A signal affected the following valve positions?

Valve Nomenclature

HV-8152, LTDN LINE CTMT ISO

MOV-8112, RCP SEAL WTR RTN ISO

HV-8149A, LTDN ORIF ISO 45 GPM

MOV-3052, CCW TO RCP CLRS Only HV-8152, HV-8149A, and MOV-8112 have closed.

Only HV-8152, MOV-8112, and MOV-3052 have closed.

Only HV-8152, and HV-8149A have closed.

Only HV-8152 has closed.

A.B.C.D.

61. A Main Control Board Deficiency related to a MCB handswitch has been identified.

Which one of the following completes t he statements below IAW SOP-0.10, FNP Operations Site Specific Policies? A (1) is required to be creat ed to identify the deficiency. The identifier (Deficiency T ag/Control Room DOT) will be (2) . (1)

(2) Deficiency Tag affixed to the MCB handswitch Deficiency Tag placed in the deficiency notebook Control Room DOT affixe d to the MCB handswitch Control Room DOT placed in the deficiency notebook A.B.C.D.

62. Unit 1 experiences a Reactor Trip with Safety injection.

Subsequently, the following occurs:

• The UO directs the Turbine Buildi ng Systems Operator (TB SO) to perform the TB SO Actions Following a Reactor Trip or Safety Injection.

Which one of the following completes the statements below per SOP-0.0, Appendix A, TB SO Actions Following a Reacto r Trip and/or Safety Injection? The TB SO is required to close V-503A, 1A MSR 2ND STG STM SUPP ISO (1) . The TB SO is required to close V-905A, 1A MS LINE DRN POT TO COND ISO (2) . (1)

(2) following any Reactor trip followi ng any Reactor trip following any Reactor trip on ly when specifically directed only when specifically directed following any Reactor trip only when specifically directed only when specifically directed A.B.C.D.

63. Which one of the following completes the statements below per NMP-AP-001-003, Review and Appr oval of Site Procedures? The "Pen and Ink" Change Process may be used for (1) changes. A Condition Report (2) required following use of a procedure with "Pen and Ink" changes.

(1)

(2) editorial IS editorial is NOT temporary IS temporary is NOT A.B.C.D.

64. Unit 1 is in a Refueling Outage with fuel being loaded into the core.

Which one of the following co mpletes the statements below?

Per TRM 13.1.6, Borated Wate r Source - Shutdown, the minimum operable BAT Tank Temperature is (1) . Per TRM 13.1.6, the minimum operable BAT Tank Volume is (2) . (1)

(2) 35°F 2000 gallons 35°F 11336 gallons 65°F 2000 gallons 65°F 11336 gallons A.B.C.D.

65. Unit 1 is exiting a refueling outage with the following conditions: Time1000120014001600AverageCoolantTemp(°F)300450547547 RatedThermalPower(%)0026Keff<.99<.991.001.00 Which one of the following co mpletes the statements below? The earliest time Unit 1 is in MODE 4 is at (1) . The earliest time Unit 1 is in MODE 1 is at (2) . (1)

(2) 1000 1400 1000 1600 1200 1400 1200 1600 A.B.C.D.

66. A Plant Operator has been assigned a portable RAM 100 frisker for personnel monitoring when exiting the dry cask storage area with the following condition:

• The Frisker Response Checks were last performed 7 days ago.

Which one of the following co mpletes the statements below? The frisker detects (1) . The Frisker Response Checks for the assigned frisker are required to be performed (2) .(1) Beta and Gamma radiation(2) prior to use (1) Beta and Gamma radiation (2) 6 months from the date of the last response check (1) ONLY Gamma radiation(2) prior to use (1) ONLY Gamma radiation (2) 6 months from the date of the last response check A.B.C.D.

67. You are assigned a task:

• Your current TEDE is 1500 mrem.

• Dose rate in the area you ar e required to work is 1500 mr/hr.

Which one of the following is the maximum amount of time you can stay in the area without exceeding Farley Administrative TEDE limits with no additional approval?

20 minutes 100 minutes 120 minutes 140 minutes A.B.C.D.

68. EEP-0.0, Reactor Trip or Safety Injection, provides specific Reactor Coolant Pump (RCP) trip criteria on the foldout page.

Which one of the following is the reason fo r tripping the RCPs when these conditions occur?Conserves RCS inventory during a Small Break LOCA with subsequent LOSP.

Prevents RCP seal damage fo llowing a Small Break LOCA.

Prevents pump runout follo wing a Large Break LOCA.

Ensures core reflood followi ng a Large Break LOCA.

A.B.C.D.

69. Unit 1 and Unit 2 are operating at 100% power when the following condition occurs:* The Outside System Operat or reports a fire in the Liquid hydrogen storage tank vent stack.

Which one of the following co mpletes the statement below? Per AOP-29.0, Plant Fire, and SOP-34.0, Hydrogen-Oxygen System the fire will be extinguished by

.spraying water directly on the vent stack and isol ating the leak.

discharging a portable fire ex tinguisher into the vent stack and isolating the leak.

establishing a helium purge and isolating the leak.

isolating the leak ONLY.

A.B.C.D.

70. The following condition exist on Unit 1:

• The TSC is fully manned and is di recting the plant response to a NOUE.

Subsequently, the following occurs:

• The Emergency Director declares a SITE AREA EMERGENCY.

Which one of the following co mpletes the statements below? Per NMP-EP-111, Emergency Notifications, a (1) tone will be sounded prior to the onsite notification announcement.

Per NMP-EP-111, Emergency Notifications, the (2) is responsible for approving notifcations to State and Local Authorities of the emergency condition.

(1)

(2) YELP Emergency Director WARBLE Emergency Director YELP Shift Manager WARBLE Shift Manager A.B.C.D.

71. An RCS soak is in progress per FRP-P.1, Response to Imminent Pressurized Thermal Shock Condition, on Unit 1.

Which one of the following actions is permitted?

Start a Charging Pump.

Energize PZR heaters.

Start an RCP.

Isolate Accumulators.

A.B.C.D.

72. Unit 1 is shutdown following a Large Break LOCA followed by an LOSP. The following conditions occur:

At 1000:

• WA2, 1-2A DG GEN FAULT TRIP, alarms.

At 1015:* CF3, 1A OR 1B RHR PUMP OVERLOAD TRIP, alarms.

• RWST level is 3 ft.* Containment Spray pump sucti ons are aligned to the RWST.

Which one of the following co mpletes the statements below?

At 1015 (1) train(s) of emergency coolant recirculation capability has(have) been lost. The operating crew (2) required to secure all CTMT Spray at 1015. (1)

(2) ONLY one IS ONLY one is NOT BOTH IS BOTH is NOT A.B.C.D.

73. Unit 1 is shutdown with ECP-2.1, Uncontrolled Depressurization of All Steam Generators in progress. Th e following conditions exist:

• All MSIV - TRIP handswi tches have been taken to CLOSE.

• JH1, 1A SG MSIV CLOSED is NOT lit.

• JH2, 1B SG MSIV CLOSED is NOT lit.

• JH3, 1C SG MSIV CLOSED is NOT lit.

Which one of the following co mpletes the statements below? The next action the crew is re quired to take per ECP-2.1 is (1) . If an MSIV is closed, ECP-2.1 directs use of (2) to determine if a Steam Generator has been isolated.

(1) Place the MSIV -T EST handswitch to TEST (2) Cold Leg Temperature(1) Place the MSIV - T EST handswitch to TEST (2) SG Pressure(1) Manually remove air pressure from the MSIVs (2) Cold Leg Temperature(1) Manually remove air pressure from the MSIVs (2) SG Pressure A.B.C.D.

74. Unit 1 is shutdown with the following conditions:

• 1A SG Pressure is 1145 psig and rising.

• The 1A Atmospheric Relief Valve is mechanically bound and cannot be opened.

• All MSIV and MSIV Bypasses are closed.

Which one of the following co mpletes the statements below? Entry conditions for FRP-H.2, Response to Steam Generator Overpressure (1) been met When FRP-H.2 is entered, the crew would be directed to lower 1A SG Pressure by (2) . (1)

(2) have NOT dumping steam to the TDAFWP HAVE dumping steam to the TDAFWP have NOT opening MSIV bypasses HAVE opening MSIV bypasses A.B.C.D.

75. Unit 1 has experienced a Large Break LOCA with the following conditions:

• PR-0950Z, CTMT PRESS NR, indicates 30 psig.

• LI-3594A, CTMT SUMP LVL, indicates 8 FT.

• FI-958 A and B, CS FLOW

, indicate 1200 GPM each.

Which one of the following co mpletes the statements below? Per CSF-0.5, Containment, the cr ew is required to enter a(n)

(1) path FRP due to (2) . (1)

(2) RED CTMT Pressure RED CTMT Sump Level ORANGE CTMT Pressure ORANGE CTMT Sump Level A.B.C.D.

76. Unit 1 was operating at 100% power when the following occurred:

At 1000:

• All Control Banks are at 231 steps.

At 1010:* Rod K4 fell to 130 steps.* Rod M6 fell to 150 steps.

• RCS Tavg lowered.

• Pressurizer pressure lowered.

Which one of the following co mpletes the statement below?

Per AOP-19, Malfunction of Rod Control System, the operating crew is required to

.shutdown the unit using UO P-3.1, Power Operation trip the Reactor and go to EEP-0.0, Reactor Trip and Safety Injection reduce power to less than 75% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> using UOP-3.1, Power Operation address restoration of rods using SOP-41.0, Control Rod Drive and PositionIndication System A.B.C.D.

77. Unit 1 is operating at 100% power when the following occurs:

At 1000:

• HH4, RCP VIB TRBL (WHITE annunci ator window), comes into alarm.

• 1A RCP shaft vibration is reported as 21 mils and stable.

• DC2, RCP #1 SEAL LKOF FLOW HI (YELLOW annunciator window), comes into alarm.

• FR145A, RCP SEAL LKOF HIGH RANGE, for the 1A RCP indicates 6.5 gpm and stable.

At 1600:

• The Unit is in MODE 3.

• The Reactor Trip Breakers are open.

• 1B and 1C RCPs are running.

• 1A RCP is tagged out.

Which one of the following co mpletes the statements below?

At 1000, the operating crew is required to (1) , then secure the 1A RCP.

At 1600, RCS pressure control is via (2) . (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection(2) Normal Spray(1) perform a controlled shutdown per th e appropriate Unit Operating Procedures(2) Normal Spray(1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection(2) Auxiliary Spray(1) perform a controlled shutdown per th e appropriate Unit Operating Procedures(2) Auxiliary Spray A.B.C.D.

78. Unit 1 is operating at 100% power when the following occurs:

• Due to a Pressurizer pressure contro l malfunction, PCV-445A, PRZR PORV opens and reseats several times.

• PRT parameters are:

- Level: 84% and is stable.

- Temperature: 180°F and stable.

- Pressure: 30 psig and stable.

Which one of the following co mpletes the statements below? HE4, PRT LVL HI-LO, (1) in alarm.

Draining the PRT using the RCDT pump per Se ction 4.3, Filling and Draining the PRT, of SOP-1.2 (2) restore all PRT parameters to within normal log specifications.

Procedure name

SOP-1.2, Reactor Coolant Pressure Relief System (1)

(2) is NOT will NOT IS will NOT is NOT WILL IS WILLA.B.C.D.

79. Unit 1 is in MODE 3 with the following conditions:

At 1000:

• The Shutdown Banks are withdrawn.

At 1005:

• A complete loss of offsite power occurs.

Which one of the following co mpletes the statements below?

At 1005, manual action (1) required to generate a P-4 signal.

Per the BASES of Tech Spec 3.3.2, ESFAS Instru mentation, P-4 is required to be OPERABLE to prevent (2) .(1) IS(2) excessive Containment pressu re due to a steamline break(1) is NOT (2) excessive Containment pressu re due to a steamline break(1) IS (2) damage to the Main Steam lines and SG safeties due to SG overfill (1) is NOT (2) damage to the Main Steam lines and SG safeties due to SG overfill A.B.C.D.

80. Unit 1 is operating at 100% power with the following conditions:* A malfunction occurred result ing in PCV-444B, PRZR PORV, opening.Subsequently, the immediat e operator actions of AOP-100, Instrumentation Malfunction, were performed and the following conditions exist:* PCV-444B GREEN light is LIT.* MOV-8000B, PRZR PORV ISO, RED light is LIT.* RCS pressure is 2180 psig and stable.

• PRT pressure, level and temperature are stable.* HA4, PRZR SAFETY VLV TEMP HI, is in alarm.* HA5, PRZR PORV TEMP HI, is in alarm.

• HD1, PRZR PRESS REL VLV 445A OR B/U HTRS ON, is in alarm.

Which one of the following co mpletes the statements below?

PCV-444B (1) leaking by.

Per Tech Spec 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), PCV-444B (2) OPERABLE.

(1)

(2) IS IS IS is NOT is NOT IS is NOT is NOT A.B.C.D.

81. Unit 1 is at 100% power with the following conditions:

• PT-950, CTMT PRESS (Channel 1), was decla red INOPERABLE.

• PT-950 bistables were positioned as required by Tech Spec 3.3.2, Engineered Safety Feature Actuation S ystem (ESFAS) Instrumentation, for continuous operation with an inoperable channel.

Which one of the following co mpletes the statements below?The Safety Injection function (1) affected by the PT-950 malfunction.

Per Tech Spec 3.3.2, the RE QUIRED ACTION is to place the PT-950bistables in (2) . (1)

(2) IS TRIP IS BYPASS is NOT TRIP is NOT BYPASS A.B.C.D.

82. Unit 1 is in MODE 3 with the following conditions:

• All RCPs are running.

• A CCW leak occurs on the 1A RCP Oil Cooler inlet connection.

Which one of the following co mpletes the statements below?

The method used in the Main Control Room (MCR) to isolate the CCW leak is to (1) .Per the BASES of Tech Spec 3.7.7 - CCW System, once the CCW leak is isolatedfrom the MCR, the CCW System is (2) . (1) isolate CCW to ALL RCPs(2) INOPERABLE(1) isolate CCW to the 1A RCP ONLY (2) INOPERABLE(1) isolate CCW to ALL RCPs (2) OPERABLE(1) isolate CCW to the 1A RCP ONLY (2) OPERABLE A.B.C.D.

83. Unit 1 has experienced a LOCA. The following conditions exist:

• EEP-1.0, Loss of Reactor or Secondary Coolant, is in progress.

• Containment Hydrogen is 6%

by volume of dry air.

Which one of the following co mpletes the statements below?

The hydrogen concentration (1) exceed the lower FLAMMABILITY limit.Hydrogen concentration will be lowered using (2) .(1) DOES (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System (1) DOES(2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation (1) does NOT (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System (1) does NOT (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation A.B.C.D.

84. Unit 1 is operating at 100% when a Pressurizer level control malfunction occurs and the following conditions exist:

• Pressurizer level is 70% and rising.

• Charging flow is 120 gpm.

• Letdown is 60 gpm.

• RCP seal injection is 8 gpm to each RCP.

• RCP seal leakoff is 3 gpm per pump.

• Actions in the field are being taken to regain c ontrol of Charging.

• It will take 8 minutes to regain control of Charging.

Which one of the following co mpletes the statements below?

An automatic reactor trip (1) occur before control of Charging is regained.

Per the BASES of Tech Spec 3.3.

1, Reactor Trip System (RTS)

Instrumentation, the purpose of the automat ic Reactor Trip on Pressurizer Water Level - High is to (2) .Reference Provided (1) WILL(2) provide protection against water relief th rough the PORV's(1) WILL (2) prevent thermal shock of the Spray Nozzle (1) will NOT (2) provide protection against water relief th rough the PORV's (1) will NOT (2) prevent thermal shock of the Spray Nozzle A.B.C.D.

85. Unit 1 is conducting a fuel reload and the following occurs:

At 1015: An Intermediate Leg leak is in progress on the 1A RCS loop with the following conditions.

• R-2, CTMT 155 FT, is in alarm.

• EH2, SFP LVL HI-LO is in alarm.

• Both RHR pumps have been secured due to cavitation.

Which one of the following co mpletes the statements below?

At 1030, an emergency classification

, per NMP-EP-110, Emergency Classification Determinatio n and Initial Action, (1) required.

Per AOP-12, Residual Heat Remo val System Malfunction, themaximum time to complete Containment closure is (2) hour(s).

(1)

(2) IS 1 IS 2 is NOT 1 is NOT 2 A.B.C.D.

86. A fuel shuffle is in progress in the Unit 1 SFP with the following conditions:

At 1000:

• An 1800 lb. load is bei ng moved over spent fuel.

At 1015:

• The load is dropped causing damage to the spent fuel.

At 1015, which one of the fo llowing describes the minimum Radiation Monitor(s) required to be in alarm to meet AOP-30, Refueling Accident, entry conditions?

AND Which one of the following describes the the expected worst case consequences of dropping an 1800 lb. l oad onto the spent fuel Per t he Bases of TR 13.9.4, Crane Travel-Spent Fuel Storage Building?* R-5 OR R-25A* The activity release will be limited to that cont ained in a single fuel assembly.* R-5 OR R-25A* The offsite dose may be as high as but not more than the 10 CFR 100 limit.* R-5 AND R-25A* The activity release will be limited to that cont ained in a single fuel assembly.* R-5 AND R-25A* The offsite dose may be as high as but not more than the 10 CFR 100 limit.

A.B.C.D.

87. Unit 1 was operating at 100% power with the following conditions:

At 1000: A Loss of Offsite Power occurs.

At 1015: The following conditions exist -

• DG-02, 1G 4160 V bus tie to 1L 4160 V bus, has AMBER and GREEN Lights LIT.

• 4160V BUS 1L AC PWR AVAIL lights are NOT lit.

Which one of the following co mpletes the statements below?

At 1015: The 1B DG (1) have cooling water supplied.

At 1015: The REQUIRED ACTION(S) of

Tech Spec(s)

(2) is(are) required to be performed.Tech Spec nomenclature: 3.8.9, Distribution Systems - Operating 3.7.8, Service Water System (SWS)

(1)

(2) WILL 3.8.9 AND 3.7.8 will NOT 3.8.9 AND 3.7.8 WILL 3.8.9 ONLY will NOT 3.8.9 ONLY A.B.C.D.

88. Unit 1 is in Mode 3 with the following conditions:

• Pressurizer level is 22% and stable.

Subsequently, a rupture occurs on the Instru ment Air header piping in the MSVR and AOP-6.0, Loss of Instrum ent Air, is in progress.

Which one of the following co mpletes the statements below? Pressurizer level will (1) . Per AOP-6.0, to maintain Pressurizer level, the operating crew is required to perform actions of (2) in conjunction with AOP-6.0.

Procedure Names

AOP-16.0, CVCS Malfunction SOP-2.1, CVCS Pl ant Startup and Operation (1)

(2) lower AOP-16.0 rise AOP-16.0 lower SOP-2.1 rise SOP-2.1 A.B.C.D.

89. Unit 1 is operating at 100% power when the following occurs:

• R-27B, CTMT HIGH RANGE, is tagged out.

• The instrument power supply fuse to R-27A, CTMT HIGH RANGE, blows.

Which one of the following co mpletes the statements below?

R-27A indication will fail (1) .Per Tech Spec 3.3.3, Post Acciden t Monitoring Instrumentation, theREQUIRED ACTION is to (2) . Reference Provided(1) HIGH(2) immediately initiate action in accordance with S pecification 5.6.8(1) HIGH(2) restore R-27A OR R-27B to OPERABLE status in 7 days (1) LOW(2) immediately initiate action in accordance with S pecification 5.6.8 (1) LOW (2) restore R-27A OR R-27B to OPERABLE status in 7 days A.B.C.D.

90. Unit 1 is operating at 100% power and the following occurs:

• R-15A, SJAE EXH, power supply beco mes erratic causi ng its indication to become unreliable but it does not alarm.Per the ODCM, which one of t he following actions are requi red to continue the releasevia this pathway, if any?

No actions are required.

Continuously collect samples using auxiliary equipment.

Place SJAE filtration in service until R-15A is restored to operable.

Perform grab samples at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyze them within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

A.B.C.D.

91. Unit 1 is in MODE 6 with the following conditions:

• Core reload is complete.

• Control Rod Drive Shaft Latching and RCCA Drag Testing is about to begin per FHP-5.1, Control Rod Drive Shaft Latching/Unlatching Tool Operating Instruction.

Which one of the following co mpletes the statements below? Per FHP-0.0, Refuelin g Organization, the Fuel Handling Supervisor (1) . Per UOP-4.1, Controlling Procedure for Refueling, two Source Range Nuclear Instruments (2) required to be OPERABLE.

(1) is required to be in Containment(2) are NOT (1) is required to be in Containment (2) ARE(1) may be in the Control Room in direct Communicati on with Containment(2) are NOT (1) may be in the Control Room in direct Communicati on with Containment (2) AREA.B.C.D.

92. A tagout is required to be cleared during night shift and the Work Document Holder is not on site and cannot be contacted to gain their approval.

Per NMP-AD-003, Equipment Clearance and Tagging, which one of the following can sign off the Work Docu ment Holder?

Shift Manager Operations Director Maintenance Director Maintenance Manager A.B.C.D.

93. Unit 1 is at 6% power with the following conditions:

• The 1A SGFP has been started.

• AFW is secured.

• The Main Feed Regulating Valves are closed.

At 1000 on January 1, 2015:

• MOV-3232B, MAIN FW TO 1B SG ST OP VLV , is declared INOPERABLE.

At 1200 on January 1, 2015

• FCV-489, 1B SG FW BYP FLOW, is declared INOPERABLE.

Subsequently it is determined that r epairs will take 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> for each valve.

Which one of the following co mpletes the statement below?

Per Tech Spec 3.7.3, Main Feedwater St op Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves, the earliest time that feed flow to the 1B SG must be isolated is

.Reference Provided 1800 on January 1, 2015 2000 on January 1, 2015 1000 on January 4, 2015 1200 on January 4, 2015 A.B.C.D.

94. A General Emergency on Unit 1 has been declared with following conditions:

• An Emergency Response Team is required to be dispatched to isolate an offsite release source.

• The TSC has not yet been manned.

• The expected exposure for the job is 35 REM TEDE per person.

Which one of the following co mpletes the statements below?

To receive the dose listed above, operators (1) required to be volunteers. The (2) will authorize the exposure.

(1)

(2) are NOT RP Supervisor are NOT Shift Manager ARE RP Supervisor ARE Shift Manager A.B.C.D.

95. Unit 1 is in MODE 6 with core offload in progress with the following condition:

• A spent fuel assembly is being moved from its assigned location in the core to the upender.

Subsequently, AOP-30.0, Ref ueling Accident, is entered Which one of the following co mpletes the statements below?

Per AOP-30.0, the Refueling SRO will direct the fuel assembly to be (1) .Per the BASES of Tech Spec 3.9.6, Refueling Cavity Water Level, 23 ft of water is required to be maintained above the fuel to (2) .(1) placed in any empty fuel location in the core(2) provide back up decay heat removal(1) placed in any empty fuel location in the core(2) retain iodine fission product activity in the water during a f uel handling accident(1) returned to its assigned location in the core(2) provide back up decay heat removal(1) returned to its assigned location in the core(2) retain iodine fission product activity in the water during a f uel handling accident A.B.C.D.

96. Unit 2 reactor startup is in progress and the following conditions exist:

• NI31, SR1 COUNT RATE is 10 6 cps and stable.

• NI32, SR2 COUNT RATE is 10 4 cps and stable.

• TSLB-3 1-1, SR HI Q NC-31D is lit.

• TSLB-3 1-2, SR HI Q NC-32D is NOT lit.

• GA1, SR HI FLUX TRIP, is in alarm.

• The Reactor Trip breakers are closed.Subsequently, The Shift Supervisor directs a manual Reactor trip.

• The Reactor Trip breakers open.Which one of the following co mpletes the statements below?An emergency classifica tion threshold value (1) been exceeded per NMP-EP-110-GL01, FNP EALS - ICs, Threshold Values And Basis. The latest time the NRC can be notified is (2) hour(s) after the event / emergency declaration.

(1)

(2) has NOT 4 HAS 4 has NOT 1 HAS 1A.B.C.D.

97. Unit 1 is performing the actions of EEP-0.0, Reactor Trip or Safety Injection, and AOP-9, Loss of Component Cooling Wate

r. Conditions are as follows:

• 1F 4160V bus is de-energized.

• B Train CCW is the "on service" Train.

• 1B CCW pump is Tagged Out.

• 1A CCW pump tripped.

• 1C CHG PUMP is running.

Subsequently, the Shift Supervi sor determines that Firewate r is required to be aligned to the 1B Charging pump

.Which one of the following co mpletes the statements below? The 1C Charging pump will be (1) while aligning Firewater to the 1B Charging pump. (2) Charging pump CCW oil co oler piping will become ch emically contaminated.

(1)

(2) secured ONLY the 1B secured BOTH 1B and 1C maintained running ONLY the 1B maintained running BOTH 1B and 1C A.B.C.D.

98. Unit 1 operating crew has exited EEP-0.0, Reactor Trip or Safety Injection, and is now performing ECP-1.2, LOCA Outside Containment with the following conditions:

• The leak isolation steps are completed.

• RWST level is 12.5 ft.

• RCS pressure continues to lower.

Which one of the following co mpletes the statement below? The next procedure the operating crew is required to transition to is

.EEP-0.0, Reactor Trip or Safety Injection ESP-1.3, Transfer to Cold Leg Recirculation EEP-1.0, Loss of Reac tor or Secondary Coolant ECP-1.1, Loss of Emergency Coolant Recirculation A.B.C.D.

99. Unit 2 is performing the actions of FRP-H.1, Response to Loss of Secondary Heat Sink, and the following conditions exist:

• The TDAFW pump has been returned to service.

• Containment pressure is 0 psig.

• RCS Bleed and Feed was initiat ed, but has now been secured.

• RCS pressure is 1600 psig and rising.

• Pressurizer level is 23% and rising.

Which one of the following co mpletes the statements below?The minimum SG level that permitt ed securing Bleed and Feed was at least one SG (1) .The operating crew will transition to (2) from FRP-H.1. (1) Wide Range level at 14%

(2) ESP-1.1, SI Termination(1) Wide Range level at 14%

(2) EEP-1, Loss of Reactor or Secondary Coolant (1) Narrow Range level at 33%

(2) ESP-1.1, SI Termination (1) Narrow Range level at 33%

(2) EEP-1, Loss of Reactor or Secondary Coolant A.B.C.D.

100. Unit 1 is cooling down per ESP-0.2, Natural Circulation Cooldown to Prevent Reactor Vessel Head Steam Voiding, and the following conditions exist:

• RVLIS is not available.

• RCS Hot leg is 450°F and slowly lowering.

• RCS Cold leg is 425°F and slowly lowering.

• The crew is cooling down at t he maximum rate al lowed by procedure.

• Pressurizer level has just r apidly risen to 78% and is stable

• RCS pressure reduction is not required.

• CST level is 9ft.

Which one of the following co mpletes the statements below?

The operating crew will transition to ESP-0.4, Natural Circulation Cooldown with Allowance for Reactor Vessel Head Steam Voiding (Without RVLIS), based on (1) .The maximum allowable cooldown rate in ESP-0.4 is (2) .Reference Provided (1) CST Level (2) <100°F in any 60 minute period (1) CST Level(2) <50°F/hr (1) Reactor Vessel void formation being indicated (2) <100°F in any 60 minute period (1) Reactor Vessel void formation being indicated(2) <50°F/hr A.B.C.D.

PAM Instrumentation 3.3.3 Farley Units 1 and 2 3.3.3-1 Amendment No. 170 (Unit 1) Amendment No. 163 (Unit 2) 3.3 INSTRUMENTATION

3.3.3 Post Accident Monitoring (PAM) Instrumentation

LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

---

NOTE--------------------------------------------------------

Separate Condition entry is allowed for each Function.

---

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with one required

channel inoperable.

A.1 Restore required channel to OPERABLE status.

30 days B. Required Action and associated Completion

Time of Condition A

not met.

B.1 Initiate action in accordance with

Specification 5.6.8.

Immediately C. One or more Functions with two required

channels inoperable.

C.1 Restore one channel to OPERABLE status.

7 days PAM Instrumentation 3.3.3 Farley Units 1 and 2 3.3.3-2 Amendment No. 185 (Unit 1)

Amendment No. 180 (Unit 2)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion

Time of Condition C

not met. D.1 Enter the Condition referenced in

Table 3.3.3-1 for the

channel.

Immediately E. As required by Required Action D.1 and

referenced in

Table 3.3.3-1.

E.1 Be in MODE 3.

AND E.2 Be in MODE 4.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> F. As required by Required Action D.1 and

referenced in

Table 3.3.3-1. F.1 Initiate action in accordance with

Specification 5.6.8.

Immediately

SURVEILLANCE REQUIREMENTS

---

NOTE--------------------------------------------------------------

SR 3.3.3.1 and SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1.

---

SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required instrumentation channel that is normally energized.

In accordance with the Surveillance Frequency Control Program SR 3.3.3.2 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program PAM Instrumentation 3.3.3 Farley Units 1 and 2 3.3.3-3 Amendment No. 167 (Unit 1)

Amendment No. 159 (Unit 2) Table 3.3.3-1 (page 1 of 1) Post Accident Monitoring Instrumentation

FUNCTION

REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION D.1

1. RCS Hot Leg Temperature (Wide Range) 2 E 2. RCS Cold Leg Temperature (Wide Range) 2 E

3. RCS Pressure (Wide Range) 2 E

4. Steam Generator (SG) Water Level (Wide or Narrow Range) 2/SG E 5. Refueling Water Storage Tank Level 2 E 6. Containment Pressure (Narrow Range) 2 E

7. Pressurizer Water Level 2 E

8. Steam Line Pressure 2/SG E

9. Auxiliary Feedwater Flow Rate 2 E 10. RCS Subcooling Margin Monitor 2 E

11. Containment Water Level (Wide Range) 2 E

12. Core Exit Temperature - Quadrant 1 2 (a) E 13. Core Exit Temperature - Quadrant 2 2 (a) E 14. Core Exit Temperature - Quadrant 3 2 (a) E 15. Core Exit Temperature - Quadrant 4 2 (a) E 16. Reactor Vessel Level Indicating System 2 F

17. Condensate Storage Tank Level 2 E

18. Deleted

19. Containment Area Radiation (High Range) 2 F (a) A channel consists of two core exit thermocouples.

Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 Farley Units 1 and 2 3.7.3-1 Amendment No. 146 (Unit 1) Amendment No. 137 (Unit 2) 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves LCO 3.7.3 Three Main FW Stop Valves, three MFRVs, and associated bypass valves shall be OPERABLE. APPLICABILITY: MODES 1 and 2, except when all main feedwater lines are isolated by either a Main FW Stop Valve, a MFRV and its associated bypass valve or by a closed manual valve. ACTIONS --------------------------------------------------------NOTE------------------------------------------------------------- Separate Condition entry is allowed for each valve.

---

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Main FW Stop Valves inoperable. A.1 Close or isolate Main FW Stop Valve.

ANDA.2 Verify Main FW Stop Valve is closed or isolated. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Once per 7 days B. One or more MFRVs inoperable. B.1 Close or isolate MFRV.

ANDB.2 Verify MFRV is closed or isolated. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Once per 7 days Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 Farley Units 1 and 2 3.7.3-2 Amendment No. 146 (Unit 1) Amendment No. 137 (Unit 2) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One or more MFRV bypass valves inoperable. C.1 Close or isolate bypass valve. ANDC.2 Verify bypass valve is closed or isolated. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Once per 7 days D. Two valves in the same flow path inoperable. D.1 Isolate affected flow path. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> E. Required Action and associated Completion Time not met. E.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the closure time of each Main FW Stop Valve, MFRV, and associated bypass valve is in accordance with the time requirement in the Inservice Testing Plan. In accordance with the Inservice Testing Program.

1/22/201314:30 UNIT 1 ES-401, Page 38 of 50 ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet

U. S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name: Date: Facility / Unit Region: I II III IV Reactor Type: W CE BW GE Start Time: Finish Time: Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80 percent overall, with 70 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.

Applicant Certification

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

__________________________________

Applicant's Signature Results RO/SRO-Only/Total Examination Values ______ / ______ / ______

Points Applicant's Score ______ / ______ / ______

Points Applicant's Grade ______ / ______ / ______

Percent

1. Unit 1 is starting up IAW UOP-1.2, Startu p of Unit from Hot Standby to Minimum Load, with the following condition:* Reactor Power is 13%.

The CONTROL ROD MOT ION switch has been released following a rod withdrawal when the following occurs:

• Rods step out continuously.

Which one of the following co mpletes the statements below?

The first action directed by AOP-19.0, Malf unction of Rod Control System, is to (1) .With NO operator action t he C-1, IR Hi Flux Rod Stop, (2) stop the outward rod motion.

(1) manually Trip the Reactor (2) will NOT(1) place ROD CONTROL BANK SELECTOR SWITCH in AUTO (2) will NOT (1) manually Trip the Reactor (2) WILL(1) place ROD CONTROL BANK SELECTOR SWITCH in AUTO (2) WILLA.B.C.D.

2. Unit 1 is performing a Reactor start up at MOL with the fo llowing conditions:* UOP-1.2, Startup of Unit From Hot Standby to Minimum L oad, is in progress.* The OATC has stabilized Reactor power.* NI-35 and NI-36, INTERMEDIATE RANGE,

indicate 1x10

-8 AMPS.Subsequently, control rods are withdrawn 3 steps.

Which one of the following co mpletes the statements below?

Reactor Power will rise then stablize (1) the POAH.The first indication of reaching the POAH is rising (2) . (1)

(2) below Pressurizer Level at Pressurizer Level below S/G Pressure at S/G Pressure A.B.C.D.

3. Unit 1 is at 25% power w hen the following conditions occur:

At 1000:* 1A RX COOLANT PUMP AMPS indicates 700 AMPS.

At 1002:

• The 1A RCP motor experiences a Sheared Shaft.

Which one of the following co mpletes the statements below?

At 1002 the 1A RCP will draw (1) electrical current than it did at 1000. The crew is required to immediately enter (2) . (1)

(2) More EEP-0.0, Reactor Trip and Safety Injection Less EEP-0.0, Reactor Trip and Safety Injection More AOP-4.0, Loss of Reactor Coolant Flow Less AOP-4.0, Loss of Reactor Coolant Flow A.B.C.D.

4. Unit 1 is operating at 100% pow er with the following conditions:

• PK-145, LP LTDN PRESS, is set to maintain Letdow n Pressure at 275 psig.

Subsequently, the RCS filter becomes completely clogged and does not allow any flow.

Which one of the following co mpletes the statements below? PK-145 controller demand will (1) . AOP-16.0, CVCS Malfunction, entry conditions (2) been met.

(1)

(2) Rise HAVE Rise have NOT Lower HAVE Lower have NOT A.B.C.D.

5. Which one of the following co mpletes the statement below? Charging Pump Suctions will auto matically align to the RWST when (1) sense(s)

(2) VCT Level.

Level Transmitter Nomenclature LT-115, VCT LVL LT-112, VCT LVL (1)

(2) either LT-115 or LT-112 5% both LT-115 and LT-112 5% either LT-115 or LT-112 15% both LT-115 and LT-112 15%

A.B.C.D.

6. Unit 1 is in MODE 4 with the following conditions:

• Plant cooldown is in progress with the 'A' Train of RHR .

• The OATC raises demand on FK-605A,1A RHR HX BYP FLOW, by 25%.

Which one of the following co mpletes the statements below?

Raising demand on FK-605A will (1)

CCW temperature.

Per SOP-23.0, Component Cooling Water System, the maximum allowableCCW outlet temperature for the CCW HX used for cooldown is (2) . (1)

(2) raise 120°F raise 135°F lower 120°F lower 135°F A.B.C.D.

7. Unit 1 is shutdown when t he following conditions occur:

• The 1A CCW pump tripped.

• The 'A' Train is the ON SERVICE Train.

Which one of the following co mpletes the statement below? Cooling is lost to the (1) RHR Heat Exchanger. The affected RHR train (2) available for transfer to Cold Leg Recirculation.

(1)

(2) 1A is NOT 1A IS 1B is NOT 1B ISA.B.C.D.

8. Unit 1 has experienced a tube rupture on the 1A SG with the following conditions:

• A Loss of All Offsite Power has occurred.

• The operating crew is performing EEP-3, Steam Gener ator Tube Rupture.

• RCS cooldown is in progress.

• INTEGRITY Critical Safety Function Status Tree has turned ORANGE due to the 1A RCS LOOP cold leg temperature dropping rapidly.

Which one of the following co mpletes the statements below? The 1A RCS LOOP cold leg temperat ure drop was caused by increased (1) flow over the 1A RCS LO OP cold leg instrument.

(2) is the highest listed cold leg temperature that could lead to this ORANGE INTEGRITY condition.

(1)

(2) Natural Circulation 270°F Natural Circulation 225°F High Head Safety Injection 270°F High Head Safety Injection 225°F A.B.C.D.

9. A Safety Injection has just occurred on Unit 1.

Which one of the following co mpletes the statement below?

The minimum valve actuations that would lead to HHSI Pump cavitation are .Valve Nomenclature:

LCV-115C, VCT OUTLET ISO LCV-115E, VCT OUTLET ISO

LCV-115D, RWST TO CHG PUMP

LCV-115B, RWST TO CHG PUMP LCV-115C or LCV-115E opening LCV-115C and LCV-115E opening LCV-115B or LCV-115D closing LCV-115B and LCV-115D closing A.B.C.D.

10. Nitrogen addition to the PRT on Unit 1 is in progress when the following occurs:

• V-042, PRT N2 PRESS REG, fails causing PRT pressure to RISE.

• PI-472, PRT PRESS, st ablizes at 15.0 psig.

Which one of the following co mpletes the statements below? HE5, PRT PRESS HI, (1) in alarm. Per SOP-1.2, Reactor Coolant Pressure Relief System, normal nitrogen pressure prevents (2) . (1)

(2) IS excessive corr osion due to oxygen is NOT excessive co rrosion due to oxygen IS an explosive mixture of oxygen and hydrogen is NOT an explosive mi xture of oxygen and hydrogen A.B.C.D.

11. Unit 1 is operating at 100% power when the following conditions occur:

• A large break has occu rred at the inlet of a Pressurizer Safety Valve.

Subsequently, the followi ng condition exists:

• Pressurizer Pressure is 1600 psig.

• Charging Pump miniflow valves are open.Which one of the following co mpletes the statements below? Per EEP-0, Reactor Trip or Safety Injection, the crew (1) required to close the Charging Pump miniflow valves. Closing the Charging Pump miniflow valves when required will ensure (2) . (1)

(2) IS HHSI pump injecti on flow is maximized is NOT HHSI pump inject ion flow is maximized IS HHSI pump heat is removed is NOT HHSI pump heat is removed A.B.C.D.

12. Unit 1 is operating at 100% power with the following conditions:

• A dual unit LOSP occurs.

Subsequently, Unit 2 experiences a Safety Injection.

Which one of the following comp letes the statement below for Unit 1? The (1) CCW pump is being powered by the (2) DG. (1)

(2) 1A 1-2A 1A 1C 1C 1-2A 1C 1CA.B.C.D.

13. Unit 1 is in MODE 5 with the following conditions:

• A cooldown is in progress.

• RHR is on service.

Subsequently, the following conditions occur:

• V-8708A, RHR SUCTION RELIEF

, has lifted and is stuck open.

Which of the following tank levels will immediately rise due to the malfunction?

PRTRHTWHTRCDTA.B.C.D.

14. A Design Basis Large Break LO CA has occurred on Unit 1.

Which one of the following co mpletes the statements below? The Accumulators will inject directly to the (1) . The purpose of the Accumula tor design capacity is to (2) refill the Reactor Vessel fo llowing a design basis accident.

(1)

(2) Hot Legs partially Hot Legs

completely Cold Legs partially Cold Legs completely A.B.C.D.

15. Unit 1 is operating at 100% power and the following conditions exist:

• Pressurizer Pressure is 2240 psig.

• Tavg is 572°F.

• Pressurizer Level Control is in manual.

• Pressurizer Level is 60%.

• 600V LCC 1M has lost power.

Which one of the following co mpletes the statements below? Power has been lost to the (1) Pressurizer Heater Group. Pressurizer Heater Groups A and B are currently (2) . (1)

(2) D Energized D De-Energized E Energized E De-Energized A.B.C.D.

16. Unit 1 is operating at 100% Power when the following conditions occur:

• A short circuit occurs in PT-445, PRZR PRESS.

• Pressurizer Pressure remains stable.

Which one of the following co mpletes the statement below? The Pressurizer Pressure input to the Reactor Protection System will NOT be affected by this malfun ction due to the use of

.an independent control channel a median signal selector isolation devices de-energize to actuate bistables A.B.C.D.

17. Unit 1 is operating at 100% power and th e following occurs:

• A Safety Injection follow ed by an LOSP on Unit 1.

Several minutes following the safety in jection the following condition exists:

• The 1B DG is running with the output breaker open.

Which one of the following co mpletes the statements below? SOP-0.8, Transient Response Procedure User's Guide, (1) require a procedure be used prior to closing the 1B DG output breaker. The B1G sequencer (2) energize the 1C Air Compressor.

(1)

(2) DOES DOES DOES does NOT does NOT DOES does NOT does NOT A.B.C.D.

18. The 1D Vital Panel becomes de-energized on Unit 1.

Which one of the following co mpletes the statements below. The 'B' Train SI actuated MOVs (1) automatically stroke upon an SI actuation. 'B' Train ESF pumps (2) be started in LOCAL at the HSDP.

(1)

(2) WILL CAN WILL CANNOT will NOT CAN will NOT CANNOT A.B.C.D.

19. Which one of the following completes the statements below? The C-11, Bank D Stop, is actuated by input from (1) at a Bank D rod height of (2) steps. (1)

(2) Digital Rod Position Indication 220 Digital Rod Position Indication 228 the Pulse-to-Analog Converter 220 the Pulse-to-Analog Converter 228 A.B.C.D.

20. Unit 1 is in MODE 3 and the following RCP temperatures are observed:

MotorBearingTemperatureMotorStatorTemperature 1ARCP190°F235°F 1BRCP200°F220°F 1CRCP190°F230°F Which one of the following co mpletes the statement below? Only the is (are) required to be secured.

1A RCP 1B RCP1A and 1B RCPs 1A and 1C RCPs A.B.C.D.

21. Which one of the following conditions would cause a Core Exit Thermocouple (CETC)monitor alarm? 1. ANY CETC input disconnected. 2. ONLY 10 valid CETCs.

3. ANY CETC temperature at 650°F.

1 ONLY 1 AND 3 ONLY 2 ONLY1, 2, AND 3 A.B.C.D.

22. Unit 1 is operating at 100% power when the following conditions occurred:

• 1B Charging Pump is started.

• 1A Charging Pump is secured.

• 1B CHG PUMP AMPS, begins to oscillate.

• FI-122A, CHG FLOW, begins to oscillate.

Subsequently, the following annunc iators come into alarm:

• EA2, CHG HDR FLOW HI-LO.

• DD1, RCP SEAL INJ FLOW LO.

• DE1, REGEN HX LTDN FLOW DISCH TEMP HI.

Which one of the following co mpletes the statements below? The alarms above are indicative of (1) . The maximum 1A RCP seal injection flowrate that would cause DD1 to alarm is (2) . (1)

(2) FCV-122 closing 6 gpm 1B Charging Pump Cavitation 6 gpm FCV-122 closing 3 gpm 1B Charging Pump Cavitation 3 gpm A.B.C.D.

23. Unit 1 is operating at 100% power with the following conditions:

• A Large Break LOCA occurs.

Subsequently, a Loss of Offsite Power occurs.

Which one of the following co mpletes the statement below 5 minutes after theLoss of Offsite Power?

(1) Containment Cooler Fans are running in slow speed. The reduced speed prevents CTMT cooler (2) due to high moisture content in the Containment atmosphere. (1)

(2) 2 fan motor overload 4 fan motor overload 2 cooling coil impingement damage 4 cooling coil impingement damage A.B.C.D.

24. Unit 1 is in MODE 5 and the following condition exists:

• Both Trains of RHR are oper ating in the cooldown alignment.

• Power is aligned to the RHR suction valves.

• Tavg is 195°F.

Subsequently, the following condition occurs:

• PT-402, 1C LOOP RCS NR PRESS, fails to 500 psig.

Which one of the following co mpletes the statements below? MOV-8701A, 1C RCS L OOP TO 1A RHR PUMP, (1) automatically close. IF MOV-8701A closes, th en AOP-12.0, Residual Heat Removal System Malfunction, entry (2) required.

(1)

(2) DOES is NOT does NOT is NOT DOES IS does NOT IS A.B.C.D.

25. Unit 1 is Shutdown following a LOCA with the following conditions:

• PR-950, CTMT PRESS, peaked at 3.2 psig.

• ECP-1.1, Loss of Em ergency Coolant Recirculat ion, is in progress.

Which one of the following co mpletes the statments below: Per ECP-1.1, the minimum CTMT Sump Level that can supp ort Containment Spray pump operation is

. 2.0 ft3.8 ft 4.5 ft 5.3 ft A.B.C.D.

26. Unit 1 is operating at 100% power when the following condition occurs:

• PK-444A, PRZR PRESS REFE RENCE, demand fails to 0%.

Which one of the following co mpletes the statements below? Initially, (1) PORV(s) will OPEN automatically. PCV-444C, 1A LOOP SPRAY VLV, will (2) . (1)

(2) only ONE CLOSE only ONE OPEN BOTH CLOSE BOTH OPEN A.B.C.D.

27. Unit 1 is operating at 100% power with the following conditions:

• Containment Mini-P urge is in operation Subsequently, the following conditions occur:

• A Main Steam Line br eaks inside Containment

• PR-950Z, CTMT PRESS, stablizes at 14.5 psig.

Which one of the following co mpletes the statements below? CTMT Mini-Purge supp ly and exhaust fans (1) tripped automatically due to a Containment Ventilation Isolation signal. CTMT Mini-Purge supp ly and exhaust dampers (2) closed automatically due to a Containment Ventilation Isolation signal. (1)

(2) HAVE HAVE HAVE have NOT have NOT HAVE have NOT have NOT A.B.C.D.

28. Unit 1 is operating at 100% power with the following conditions:

• STP-33.2A, Reactor Trip Breaker Tr ain A Operability Test, is in progress.

• Reactor Trip Br eaker A is OPEN.

• Reactor Trip Bypass Breaker A is CLOSED.

• Reactor Trip Br eaker B is CLOSED.

Subsequently, the following conditions occur:

• An automatic reactor trip signal is generated.

• The Reactor does NOT trip.

Which one of the following co mpletes the statements below? When the RX TRIP ACTUATION switch is taken to TRIP (1) will OPEN. Per EEP-0, Reactor Trip or Safety Injection, if the RX TRIP ACTUATION switches fail to trip the Reactor, the next action required is to (2) . (1) ONLY Reactor Trip Breaker B (2) trip the MG set supply breakers (1) BOTH Reactor Trip Bypass Break er A and Reactor Trip Breaker B (2) trip the MG set supply breakers (1) ONLY Reactor Trip Breaker B(2) insert Control Rods manually (1) BOTH Reactor Trip Bypass Break er A and Reactor Trip Breaker B(2) insert Control Rods manually A.B.C.D.

29. Unit 2 is starting up per UOP-1.2, Startup of Unit From Hot Standby To Minimum Load, with the following conditions:

• Main Steam Header Warm Up is in Progress.

Which one of the following actions w ould cause the 2B SG Pressure tolower due to increased steam de mand from the 2B SG?

Lower PC-3371B, 2B MS ATMOS REL VLV, SETPT in AUTO.

Lower PC-3371B, 2B MS ATMOS REL VLV, OUTPUT in MAN.

Lower PK-464, STM HDR PR ESS, OUTPUT in MAN.

Lower PK-464, STM HDR PRESS, SETPT in AUTO.

A.B.C.D.

30. Unit 1 is responding to a SGTR in the 1A SG with the following conditions:

At 1000:

• HIGHEST CORE EXIT TEMP CHAN A and B on the IPC, indicates 530°F.

• 1A SG PRESS is 810 psig.

• PI-403A, 1A LOOP RCS WR PRESS, indicates 1230 psig.

• RCS cooldown is in progress.

At 1045:

• HIGHEST CORE EXIT TEMP CHAN A and B, on t he IPC indicates 450°F

.

• 1A SG PRESS is 300 psig.

• PI-403A, 1A LOOP RCS WR PRESS, indicates 565 psig.

Which one of the following co mpletes the statements below? Compared to the conditions at 1000, RCS subcooling at 1045 has (1) . Compared to the conditions at 1000, SG tube leakage rate at 1045 has (2) . Reference Provided (1)

(2) risen risen risen lowered lowered lowered lowered risen A.B.C.D.

31. Unit 1 is in Mode 3 at EOL with the following conditions:

• A Reactor Startup is being planned for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a reactor trip.

• Tavg is being maintained by the Atmospheric Relief Valves (ARVs).

• The Estimated Critical Condition (ECC) calculation predicts criticality at 100 steps on Control Bank D.

Which one of the following conditions will re sult in critical rod height being HIGHER than the value pred icted by the ECC?

For your answer, consider that no operator actions are taken to mitigate or compensate for the below events.

A dilution of 500 gallons is performed.

Auxiliary Feedwater flow is RAISED to all SGs.

A post maintenance test results in the closure of all ARVs.

Reactor startup occurs 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> s after the reactor trip.

A.B.C.D.

32. Unit 2 is at 68% power ramping down due to a problem with #4 Governor Valve with the following conditions:* EH is isolated to #4 Governor valve.

• A subsequent failure causes #2 Governor Valve to fail closed.* Turbine load drops to 450 MW.

Which one of the following co mpletes the statements below? The #2 governor valve closure results in (1) . Per SOP-72.0, General Instructions for DEH Operators Console, the operating crew is required to (2) .(1) automatic removal of the IMP Press Loop(2) trip the Main Turbine (1) automatic removal of the IMP Press Loop(2) match reactor power with turbine load (1) opposed governor valve closure(2) trip the Main Turbine (1) opposed governor valve closure(2) match reactor power with turbine load A.B.C.D.

33. Unit 1 is operating at 100% power with the following conditions:

AT 1000:

• 1A Circulating Water Pump Trips.

AT 1005:

• KK1, TURB COND VAC LO, comes into alarm Which one of the following co mpletes the statements below?

(1) is the earliest ti me AOP-8.0, Partial Loss of Condenser Vacuum, entry is required.

At 100% Reactor power, (2) is the lowest c ondenser pressure a manual Reactor Trip is required.

(1)

(2) 1000 3.800 psia 1005 3.800 psia 1000 2.901 psia 1005 2.901 psia A.B.C.D.

34. Unit 1 entered FRP-H.1, Response to Loss of Secondary Heat Sink, with the following conditions: Time1000101510301100 1AS/GWRLVL(%)37.0028.0018.0011.00 1BS/GWRLVL(%)32.0020.0010.006.00 1CS/GWRLVL(%)29.0019.009.003.00CNMTPRESS(PSIG)1.502.003.004.50 AFWTOTALFLOW(GPM)0000 Which one of the following is the EARLIEST time that a manual Safety Injection is required due to meeting Bleed and Feed criteria per FRP-H.1?

1000101510301100A.B.C.D.

35. Which one of the following is the purpose of depressurizing all intact SGs during the performance of ECP-0.0, Loss of All AC Power?

Rapidly reduces DP across SG U-tubes to minimize RCS inventory loss from a potential tube rupture.

Cools RCP seals in a cont rolled manner and minimizes loss of RCS inventory.Maximizes Natural Circulation flow before reflux cooling begins as theRCS becomes saturated.

Maximizes Natural Circula tion flow to allow r eactor vessel head to cool since CRDM cooling fans are unavailable.

A.B.C.D.

36. Unit 1 is operating at 100% power and the following condition exists:

• Main Condenser Pressure is rising due to a failure of the 1A SJAE.

Which one of the following co mpletes the statements below? Main Condenser Hotwell Te mperature w ill initially (1) . AOP-8.0, Partial Loss of Conden ser Vacuum, will direct placing (2) on service.

(1)

(2) RISE a Hogger LOWER a Hogger RISE the 1B SJAE LOWER the 1B SJAE A.B.C.D.

37. The following conditions exist:

• Unit 1 is in MODE 5.

• Unit 2 is operating at 100% power.

• The 1B DG is INOPERABLE.

Subsequently, the following occurs simultaneously:

• 4160V busses 1F, 1K, 1G, and 1L de-energize.

• 4160V busses 2F, 2K, 2G, and 2L de-energize.

• The 1-2A DG Trips and cannot be restored.

Which one of the following co mpletes the statement below? The first procedure the Unit 1 Operating Crew is required to enter is (1) . The Operating Crew will restore power to Unit 1 with the (2) .(1) AOP-5.0, Loss of A or B Train Electrical Power (2) 1C DG(1) ECP-0.0, Loss of All AC Power (2) 1C DG (1) AOP-5.0, Loss of A or B Train Electrical Power (2) 2C DG (1) ECP-0.0, Loss of All AC Power (2) 2C DG A.B.C.D.

38. Which one of the following completes the statement below? The Main Turbine exhaust hood sprays use (1) to automatically prevent excessive temperatures at the exhaust of the LP Turbine (2) 15% Turbine Load. (1)

(2) demin water above demin water below condensate above condensate below A.B.C.D.

39. Unit 1 is operating at 100% power when the following occurs:

• The 1C 120 VAC Vital Instrum entation Panel is de-energized.

Which one of the following co mpletes the statements below?

LCV-459, LTDN LINE ISO, (1) automatically close if a Pressurizer Low Level condition occurs. LCV-115A (2) immediately divert to the RHT. (1)

(2) WILL WILL WILL will NOT will NOT WILL will NOT will NOT A.B.C.D.

40. Unit 1 is operating at 8% power and the following conditions occur:* The Battery Input Breaker on the 1B inverter trips.

• WD2, 1B INV FAULT, annunciator alarms.

• No Other Annunciators are in Alarm due to the fault.

Subsequently, the Rover reports the followi ng indications from the 1B Inverter.

• INVERTER POWERING LOAD lamp NOT lit.

• BYPASS SOURCE AVAIL ABLE lamp is LIT.

Which one of the following co mpletes the statements below? The 1B 120V Vital AC panel is (1) . The 1B INVERTER AMPERES meter on the EPB indicates (2) .(1) Energized (2) 0 Amps (1) Energized (2) Full Load Amps(1) De-energized (2) 0 Amps. When the MANUA L BYPASS SWITCH is taken to BYPASS SOURCE TO LOAD positi on it will indicate Full Load Amps.(1) De-energized (2) 0 Amps. When the MANUA L BYPASS SWITCH is taken to BYPASS SOURCE TO LOAD position it will continue to indicate 0 Amps.

A.B.C.D.

41. Unit 1 is operating at 100% power when the following conditions occur:

• Annunciator KB4, SGFP SUCT PRESS LO, alarms

• PR-4039, SGFP SUCT PRESS, indicates 300 psig and lowering.

Which one of the following co mpletes the statement below? The earliest time the standby condensate pump will start is when

.KB4 has been in alarm for 10 seconds KB4 has been in alarm for 30 seconds SGFP suction pressure has rema ined below 275 PSIG for 10 seconds SGFP suction pressure has rema ined below 275 PSIG for 30 seconds A.B.C.D.

42. A gas transfer is in progress to the #8 Waste Gas Decay Tank on Unit 1 when the following conditions occur:

• The #8 Waste Gas Decay Tank relief valve lifts.

• The relief valve fails to reseat.

Which one of the following co mpletes the statements below?

The relief valve lifting will initially be detected by (1) . The release (2) be automatically isolated from the environment if an alarm condition exists. (1)

(2) R-13, WASTE GAS MONITOR WILL R-13, WASTE GAS MONITOR will NOT R-14, PLANT VENT MONITOR WILL R-14, PLANT VENT MONITOR will NOT A.B.C.D.

43. Unit 1 is Operating at 100% Reactor Power when the following conditions occur: Time1000100510101015 1AS/GNRLVL(%)26.0023.0021.007.00 1BS/GNRLVL(%)34.0027.0025.008.00 1CS/GNRLVL(%)35.0033.0031.0012.00 1ASGFPSTATUSRunningRunningTrippedTripped 1BSGFPSTATUSRunningRunningTrippedTripped Which one of the following is the earliest time when all AFW Pumps have recieved an AUTO START signal?

1000100510101015A.B.C.D.

44. Unit 1 is operating at 100% power with the following condition:

• An LOSP occurs.

Which one of the following co mpletes the statements below?

10 seconds after power is restored to the 1F 4160V bus: 1A CHG PUMP AMPS will indicate (1) AMPS.

1A MDAFWP AMPS will indicate (2) AMPS. (1)

(2) greater than zero greater than zero greater than zero zero zero greater than zero zero zero A.B.C.D.

45. Unit 1 is operating at 100% power when the following condition occurs:

• The Reactor Trips

Subsequently, the following indications are displayed continously on the MCB.* V-515, SW TO TURB BLDG ISO A TRN, RED and GREEN Lights are LIT.* V-517, SW TO TURB BLDG ISO B TRN, RED and GREEN Lights are LIT.

• V-516, SW TO TURB BLDG ISO A TRN, RED and GREEN Lights are LIT.* V-514, SW TO TURB BLDG ISO B TRN, RED and GREEN Lights are LIT.

Which one of the following co mpletes the statement below? The valve actuation was initiated by a (1) . The valve position prevents (2) .(1) Safety Injection (2) damage to turbine building auxiliaries.(1) Loss of Offsite Power (2) complete isolation of SW flow to the Air Compressors(1) Safety Injection (2) complete isolation of SW flow to the Air Compressors(1) Loss of Offsite Power (2) damage to turbine building auxiliaries.

A.B.C.D.

46. Which one of the following completes the statements below? The (1) RCP(s) can be powered from the 1A Startup Transformer. The (2) RCP(s) can be powered from the 2B Startup Transformer.

(1)

(2) 1A RCP 2A RCP 1A RCP 2B and 2C RCPs 1B and 1C RCPs 2A RCP 1B and 1C RCPs 2B and 2C RCPs A.B.C.D.

47. Unit 1 is at 100% power when the following condition occurs in the AuxBldg DC distribution system:

• The 125V DC Bus 1B has been de-energized.

Subsequently, an LOSP occurs on Unit 1.

Which one of the following co mpletes the statements below?The 1B DG (1) be started fr om the EPB. The B1G Sequencer (2) automatically sequence loads.

(1)

(2) CAN WILL CANNOT will NOT CANNOT WILL CAN will NOT A.B.C.D.

48. Which one of the following completes t he statement below for the 1B DG AirRecievers? The maximum Air Receiver pressure th at will cause an alarm on the 1B DG Local Control Panel is (1) .At the alarm setpoint t here is enough air pressure to ensure a maximum of (2) start attempts are available.

(1) (2) 200 psig 3 200 psig 5 350 psig 3 350 psig 5 A.B.C.D.

49. Unit 1 is operating at 100% power when the following conditions occur:

• MH1, FIRE, annunciator on the Unit 1 Main Control Board (MCB) alarms. * "Aux Bldg El 139 W Side Det 1A-39, 43, 46, 53 1A-55, 59, 106", light is lit on the Control Room Fire Panel.

• The Rover reports that the window fo r 1A-59 at the PYR-A-LARM panel is lit.What is (are) the minimum required action(s) to ens ure MH1, FIRE, will alarm again if 1A-39 co mes into alarm?

The Control Room Fire Panel alarm must be acknowledged.

and 1A-59 must be placed in OVE RRIDE on the PY R-A-LARM panel.

The Control Room Fire Panel alarm must be acknowledged.

and The Reflash Panel alarm for detection system 1A-59 must be acknowledged.

ONLY 1A-59 must be placed in OVERRIDE on the PYR-A-LARM panel.ONLY the Reflash Panel alarm for detection system 1A-59 must be acknowledged.

A.B.C.D.

50. AOP-28.0, Control Room Inaccessi bility, is in progress on Unit 1.

Which one of the following co mpletes the statements below?

The 1A MDAFWP will be oper ated in LOCAL at the (1) HSDP. Operator action is requi red to control the MDAFWP

FCVs in LOCAL at the HSDP in order to prevent (2) . (1)

(2) F low SG water level due to valve position F isolating letdown due to cooldown A low SG water level due to valve position A isolating letdown due to cooldown A.B.C.D.

51. Unit 2 is at 100% power with the following conditions:* A #1 Waste Monitor Tank (WMT) release is in progress with the #1 WMT pump running.

• RCV-18, WMT DISCH TO ENVIRONMENT, is open.

Subsequently R-18, LIQ WAST E DISCH, alarms HIGH.

Which one of the following co mpletes the statements below?RCV-18 will (1)

.The #1 WMT pump will (2)

. (1)

(2) remain open trip remain open continue to run close trip close continue to run A.B.C.D.

52. Unit 1 is operating at 100% power with the following condition:

• A SG Tube Leak is in progress.

• FCV-1152, SGBD HX Outlet Flow Control Valve, is stuck in the OPEN position.

Which one of the following radiation monitors is able to automatically stop a release to the environment due to the SG Tube Rupture?

R-23A, SGBD SRG TK INLET

R-23B, SGBD SRG TK DISCH R-19, SGBD SAMPLE R-70A, SG TUBE LEAK DET A.B.C.D.

53. Unit 1 is operating at 100% power when the following occurs:

• A Large Break LOCA o ccurs inside containment.

• Containment Pressure reaches 35 psig.

Which one of the following co mpletes the statements below? MOV-3024A, EMERG SW FROM 1A CTMT CLR, opened due to a(n)

(1) signal. Each CTMT Cooler will be supplied with approximately (2) GPM of Service Water flow. (1)

(2) Safety Injection 2000 Safety Injection 800 Containment Spray 2000 Containment Spray 800 A.B.C.D.

54. Unit 1 experienced a Safety Injection with LOSP.

Which one of the following co mpletes the statements below? The 1A Charging Pump Room Cooler will automatically start due to a signal generated by the 1A Charging Pump (1) . Controls for starting the Charging Pump Room Coolers (2) located on the BOP Panel. (1)

(2) Breaker ARE Breaker are NOT Room Thermostat ARE Room Thermostat are NOT A.B.C.D.

55. Unit 1 is operating at 100% power with the following conditions:

• The Gross Failed Fuel Detector (GFFD

) has steadily indicated 2500 cpm during the entire fuel cycle.

Subsequently, the following readings are recorded: Time1000110012001300 GFFDIndication(cpm)1.1X1041.5X1044.4X1041.3X105Which one of the following is the earliest time the GFFD will be in High Alarm?

1000110012001300A.B.C.D.

56. Unit 1 is operating at 100% power with the following conditions:

• AOP-5.2, Degraded Grid, has just been entered.

• Voltage on all emergency busses for both units is reading 3875 volts.

• MEGAVARS are reading (+) 100 on the MCB.

• The Shift Supervisor has directed the UO to maintain (+) 400 MVARs in accordance with the voltage schedule.

• The Unit 2 UO maintains MVARS st able on Unit 2 during the adjustment.

Which one of the following will occur when the Unit 1 UO performs the adjustment as directed by the Shift Supervisor?

The operator will (1)

Voltage, to reac h (+) 400 MVARs. After adjusting voltage, the te mperature of large pump motors, such as the RCP or CW pump motors, will (2)

. (1)

(2) raise lower raise rise lower lower lower rise A.B.C.D.

57. Unit 1 was manually tripped from 100% power and the following conditions exist:

• AOP-6.0, Loss of Instrument Air, is in progress.

• The TDAFW pump automatically started.

• BOTH MDAFW pumps failed to start.

• The MSVR is not accessible

.Subsequently, the following report is received from Mechanical Maintenance:

• Restoration of Instrum ent Air will take 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

Which one of the following describes the required AOP-6.0 operator action(s), if any, and the reason?

No action is required be cause the TDAFWP steam admission valves fail to the "as is" position.

Manually close the TDAFWP steam adm ission valves to avoid causing an uncontrolled cooldown.

Manually open the TDAFWP steam admission valves to provide an adequate heat sink.

Manually align emergency air to the TDAFW pum p steam admission valves to provide an adequate heat sink.

A.B.C.D.

58. Unit 1 is operating at 100% power when the following occurs:

At 1000

• An Instrument Air malfunction occurs.

At 1015

• PI-4004B, INST AIR PRESS, indicates 50 psig and stable Which one of the following co mpletes the statements below?

At 1015 V904, Instrument Air to the Service Building, is (1) . A(n) (2) maintains MSIV air pressure following loss of instrument air pressure. (1)

(2) OPEN accumulator OPEN compressed nitrogen cylinder CLOSED accumulator CLOSED compressed nitrogen cylinder A.B.C.D.

59. Unit 1 is shutdown following a LOCA with the following conditions:

• PI-402A and PI-403A, RCS WR PR ESS, indicate 600 psig and stable.

• PR-950Z, CTMT PRESS, indicate s 32 psig and slowly lowering.

Subsequently, ONLY the fo llowing actions are taken:

• SI BLOCK RESET A T RN pushbutton is depressed.

• SI BLOCK RESET B T RN pushbutton is depressed.

• PHASE B CTMT IS O RESET A TRN pushb utton is depressed.

• PHASE B CTMT IS O RESET B TRN pushb utton is depressed.

Which one of the following co mpletes the statements below: PHASE A CNMT ISO (1) reset. PHASE B CNMT ISO (2) reset. (1)

(2) IS is NOT IS IS is NOT is NOT is NOT IS A.B.C.D.

60. Unit 1 is operating at 100% power when the following conditions occur:

• Phase A is actuated using the MCB handswitches.

How has the Phase A signal affected the following valve positions?

Valve Nomenclature

HV-8152, LTDN LINE CTMT ISO

MOV-8112, RCP SEAL WTR RTN ISO

HV-8149A, LTDN ORIF ISO 45 GPM

MOV-3052, CCW TO RCP CLRS Only HV-8152, HV-8149A, and MOV-8112 have closed.

Only HV-8152, MOV-8112, and MOV-3052 have closed.

Only HV-8152, and HV-8149A have closed.

Only HV-8152 has closed.

A.B.C.D.

61. A Main Control Board Deficiency related to a MCB handswitch has been identified.

Which one of the following completes t he statements below IAW SOP-0.10, FNP Operations Site Specific Policies? A (1) is required to be creat ed to identify the deficiency. The identifier (Deficiency T ag/Control Room DOT) will be (2) . (1)

(2) Deficiency Tag affixed to the MCB handswitch Deficiency Tag placed in the deficiency notebook Control Room DOT affixe d to the MCB handswitch Control Room DOT placed in the deficiency notebook A.B.C.D.

62. Unit 1 experiences a Reactor Trip with Safety injection.

Subsequently, the following occurs:

• The UO directs the Turbine Buildi ng Systems Operator (TB SO) to perform the TB SO Actions Following a Reactor Trip or Safety Injection.

Which one of the following completes the statements below per SOP-0.0, Appendix A, TB SO Actions Following a Reacto r Trip and/or Safety Injection? The TB SO is required to close V-503A, 1A MSR 2ND STG STM SUPP ISO (1) . The TB SO is required to close V-905A, 1A MS LINE DRN POT TO COND ISO (2) . (1)

(2) following any Reactor trip followi ng any Reactor trip following any Reactor trip on ly when specifically directed only when specifically directed following any Reactor trip only when specifically directed only when specifically directed A.B.C.D.

63. Which one of the following completes the statements below per NMP-AP-001-003, Review and Appr oval of Site Procedures? The "Pen and Ink" Change Process may be used for (1) changes. A Condition Report (2) required following use of a procedure with "Pen and Ink" changes.

(1)

(2) editorial IS editorial is NOT temporary IS temporary is NOT A.B.C.D.

64. Unit 1 is in a Refueling Outage with fuel being loaded into the core.

Which one of the following co mpletes the statements below?

Per TRM 13.1.6, Borated Wate r Source - Shutdown, the minimum operable BAT Tank Temperature is (1) . Per TRM 13.1.6, the minimum operable BAT Tank Volume is (2) . (1)

(2) 35°F 2000 gallons 35°F 11336 gallons 65°F 2000 gallons 65°F 11336 gallons A.B.C.D.

65. Unit 1 is exiting a refueling outage with the following conditions: Time1000120014001600AverageCoolantTemp(°F)300450547547 RatedThermalPower(%)0026Keff<.99<.991.001.00 Which one of the following co mpletes the statements below? The earliest time Unit 1 is in MODE 4 is at (1) . The earliest time Unit 1 is in MODE 1 is at (2) . (1)

(2) 1000 1400 1000 1600 1200 1400 1200 1600 A.B.C.D.

66. A Plant Operator has been assigned a portable RAM 100 frisker for personnel monitoring when exiting the dry cask storage area with the following condition:

• The Frisker Response Checks were last performed 7 days ago.

Which one of the following co mpletes the statements below? The frisker detects (1) . The Frisker Response Checks for the assigned frisker are required to be performed (2) .(1) Beta and Gamma radiation(2) prior to use (1) Beta and Gamma radiation (2) 6 months from the date of the last response check (1) ONLY Gamma radiation(2) prior to use (1) ONLY Gamma radiation (2) 6 months from the date of the last response check A.B.C.D.

67. You are assigned a task:

• Your current TEDE is 1500 mrem.

• Dose rate in the area you ar e required to work is 1500 mr/hr.

Which one of the following is the maximum amount of time you can stay in the area without exceeding Farley Administrative TEDE limits with no additional approval?

20 minutes 100 minutes 120 minutes 140 minutes A.B.C.D.

68. EEP-0.0, Reactor Trip or Safety Injection, provides specific Reactor Coolant Pump (RCP) trip criteria on the foldout page.

Which one of the following is the reason fo r tripping the RCPs when these conditions occur?Conserves RCS inventory during a Small Break LOCA with subsequent LOSP.

Prevents RCP seal damage fo llowing a Small Break LOCA.

Prevents pump runout follo wing a Large Break LOCA.

Ensures core reflood followi ng a Large Break LOCA.

A.B.C.D.

69. Unit 1 and Unit 2 are operating at 100% power when the following condition occurs:* The Outside System Operat or reports a fire in the Liquid hydrogen storage tank vent stack.

Which one of the following co mpletes the statement below? Per AOP-29.0, Plant Fire, and SOP-34.0, Hydrogen-Oxygen System the fire will be extinguished by

.spraying water directly on the vent stack and isol ating the leak.

discharging a portable fire ex tinguisher into the vent stack and isolating the leak.

establishing a helium purge and isolating the leak.

isolating the leak ONLY.

A.B.C.D.

70. The following condition exist on Unit 1:

• The TSC is fully manned and is di recting the plant response to a NOUE.

Subsequently, the following occurs:

• The Emergency Director declares a SITE AREA EMERGENCY.

Which one of the following co mpletes the statements below? Per NMP-EP-111, Emergency Notifications, a (1) tone will be sounded prior to the onsite notification announcement.

Per NMP-EP-111, Emergency Notifications, the (2) is responsible for approving notifcations to State and Local Authorities of the emergency condition.

(1)

(2) YELP Emergency Director WARBLE Emergency Director YELP Shift Manager WARBLE Shift Manager A.B.C.D.

71. An RCS soak is in progress per FRP-P.1, Response to Imminent Pressurized Thermal Shock Condition, on Unit 1.

Which one of the following actions is permitted?

Start a Charging Pump.

Energize PZR heaters.

Start an RCP.

Isolate Accumulators.

A.B.C.D.

72. Unit 1 is shutdown following a Large Break LOCA followed by an LOSP. The following conditions occur:

At 1000:

• WA2, 1-2A DG GEN FAULT TRIP, alarms.

At 1015:* CF3, 1A OR 1B RHR PUMP OVERLOAD TRIP, alarms.

• RWST level is 3 ft.* Containment Spray pump sucti ons are aligned to the RWST.

Which one of the following co mpletes the statements below?

At 1015 (1) train(s) of emergency coolant recirculation capability has(have) been lost. The operating crew (2) required to secure all CTMT Spray at 1015. (1)

(2) ONLY one IS ONLY one is NOT BOTH IS BOTH is NOT A.B.C.D.

73. Unit 1 is shutdown with ECP-2.1, Uncontrolled Depressurization of All Steam Generators in progress. Th e following conditions exist:

• All MSIV - TRIP handswi tches have been taken to CLOSE.

• JH1, 1A SG MSIV CLOSED is NOT lit.

• JH2, 1B SG MSIV CLOSED is NOT lit.

• JH3, 1C SG MSIV CLOSED is NOT lit.

Which one of the following co mpletes the statements below? The next action the crew is re quired to take per ECP-2.1 is (1) . If an MSIV is closed, ECP-2.1 directs use of (2) to determine if a Steam Generator has been isolated.

(1) Place the MSIV -T EST handswitch to TEST (2) Cold Leg Temperature(1) Place the MSIV - T EST handswitch to TEST (2) SG Pressure(1) Manually remove air pressure from the MSIVs (2) Cold Leg Temperature(1) Manually remove air pressure from the MSIVs (2) SG Pressure A.B.C.D.

74. Unit 1 is shutdown with the following conditions:

• 1A SG Pressure is 1145 psig and rising.

• The 1A Atmospheric Relief Valve is mechanically bound and cannot be opened.

• All MSIV and MSIV Bypasses are closed.

Which one of the following co mpletes the statements below? Entry conditions for FRP-H.2, Response to Steam Generator Overpressure (1) been met When FRP-H.2 is entered, the crew would be directed to lower 1A SG Pressure by (2) . (1)

(2) have NOT dumping steam to the TDAFWP HAVE dumping steam to the TDAFWP have NOT opening MSIV bypasses HAVE opening MSIV bypasses A.B.C.D.

75. Unit 1 has experienced a Large Break LOCA with the following conditions:

• PR-0950Z, CTMT PRESS NR, indicates 30 psig.

• LI-3594A, CTMT SUMP LVL, indicates 8 FT.

• FI-958 A and B, CS FLOW

, indicate 1200 GPM each.

Which one of the following co mpletes the statements below? Per CSF-0.5, Containment, the cr ew is required to enter a(n)

(1) path FRP due to (2) . (1)

(2) RED CTMT Pressure RED CTMT Sump Level ORANGE CTMT Pressure ORANGE CTMT Sump Level A.B.C.D.

76. Unit 1 was operating at 100% power when the following occurred:

At 1000:

• All Control Banks are at 231 steps.

At 1010:* Rod K4 fell to 130 steps.* Rod M6 fell to 150 steps.

• RCS Tavg lowered.

• Pressurizer pressure lowered.

Which one of the following co mpletes the statement below?

Per AOP-19, Malfunction of Rod Control System, the operating crew is required to

.shutdown the unit using UO P-3.1, Power Operation trip the Reactor and go to EEP-0.0, Reactor Trip and Safety Injection reduce power to less than 75% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> using UOP-3.1, Power Operation address restoration of rods using SOP-41.0, Control Rod Drive and PositionIndication System A.B.C.D.

77. Unit 1 is operating at 100% power when the following occurs:

At 1000:

• HH4, RCP VIB TRBL (WHITE annunci ator window), comes into alarm.

• 1A RCP shaft vibration is reported as 21 mils and stable.

• DC2, RCP #1 SEAL LKOF FLOW HI (YELLOW annunciator window), comes into alarm.

• FR145A, RCP SEAL LKOF HIGH RANGE, for the 1A RCP indicates 6.5 gpm and stable.

At 1600:

• The Unit is in MODE 3.

• The Reactor Trip Breakers are open.

• 1B and 1C RCPs are running.

• 1A RCP is tagged out.

Which one of the following co mpletes the statements below?

At 1000, the operating crew is required to (1) , then secure the 1A RCP.

At 1600, RCS pressure control is via (2) . (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection(2) Normal Spray(1) perform a controlled shutdown per th e appropriate Unit Operating Procedures(2) Normal Spray(1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection(2) Auxiliary Spray(1) perform a controlled shutdown per th e appropriate Unit Operating Procedures(2) Auxiliary Spray A.B.C.D.

78. Unit 1 is operating at 100% power when the following occurs:

• Due to a Pressurizer pressure contro l malfunction, PCV-445A, PRZR PORV opens and reseats several times.

• PRT parameters are:

- Level: 84% and is stable.

- Temperature: 180°F and stable.

- Pressure: 30 psig and stable.

Which one of the following co mpletes the statements below? HE4, PRT LVL HI-LO, (1) in alarm.

Draining the PRT using the RCDT pump per Se ction 4.3, Filling and Draining the PRT, of SOP-1.2 (2) restore all PRT parameters to within normal log specifications.

Procedure name

SOP-1.2, Reactor Coolant Pressure Relief System (1)

(2) is NOT will NOT IS will NOT is NOT WILL IS WILLA.B.C.D.

79. Unit 1 is in MODE 3 with the following conditions:

At 1000:

• The Shutdown Banks are withdrawn.

At 1005:

• A complete loss of offsite power occurs.

Which one of the following co mpletes the statements below?

At 1005, manual action (1) required to generate a P-4 signal.

Per the BASES of Tech Spec 3.3.2, ESFAS Instru mentation, P-4 is required to be OPERABLE to prevent (2) .(1) IS(2) excessive Containment pressu re due to a steamline break(1) is NOT (2) excessive Containment pressu re due to a steamline break(1) IS (2) damage to the Main Steam lines and SG safeties due to SG overfill (1) is NOT (2) damage to the Main Steam lines and SG safeties due to SG overfill A.B.C.D.

80. Unit 1 is operating at 100% power with the following conditions:* A malfunction occurred result ing in PCV-444B, PRZR PORV, opening.Subsequently, the immediat e operator actions of AOP-100, Instrumentation Malfunction, were performed and the following conditions exist:* PCV-444B GREEN light is LIT.* MOV-8000B, PRZR PORV ISO, RED light is LIT.* RCS pressure is 2180 psig and stable.

• PRT pressure, level and temperature are stable.* HA4, PRZR SAFETY VLV TEMP HI, is in alarm.* HA5, PRZR PORV TEMP HI, is in alarm.

• HD1, PRZR PRESS REL VLV 445A OR B/U HTRS ON, is in alarm.

Which one of the following co mpletes the statements below?

PCV-444B (1) leaking by.

Per Tech Spec 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), PCV-444B (2) OPERABLE.

(1)

(2) IS IS IS is NOT is NOT IS is NOT is NOT A.B.C.D.

81. Unit 1 is at 100% power with the following conditions:

• PT-950, CTMT PRESS (Channel 1), was decla red INOPERABLE.

• PT-950 bistables were positioned as required by Tech Spec 3.3.2, Engineered Safety Feature Actuation S ystem (ESFAS) Instrumentation, for continuous operation with an inoperable channel.

Which one of the following co mpletes the statements below?The Safety Injection function (1) affected by the PT-950 malfunction.

Per Tech Spec 3.3.2, the RE QUIRED ACTION is to place the PT-950bistables in (2) . (1)

(2) IS TRIP IS BYPASS is NOT TRIP is NOT BYPASS A.B.C.D.

82. Unit 1 is in MODE 3 with the following conditions:

• All RCPs are running.

• A CCW leak occurs on the 1A RCP Oil Cooler inlet connection.

Which one of the following co mpletes the statements below?

The method used in the Main Control Room (MCR) to isolate the CCW leak is to (1) .Per the BASES of Tech Spec 3.7.7 - CCW System, once the CCW leak is isolatedfrom the MCR, the CCW System is (2) . (1) isolate CCW to ALL RCPs(2) INOPERABLE(1) isolate CCW to the 1A RCP ONLY (2) INOPERABLE(1) isolate CCW to ALL RCPs (2) OPERABLE(1) isolate CCW to the 1A RCP ONLY (2) OPERABLE A.B.C.D.

83. Unit 1 has experienced a LOCA. The following conditions exist:

• EEP-1.0, Loss of Reactor or Secondary Coolant, is in progress.

• Containment Hydrogen is 6%

by volume of dry air.

Which one of the following co mpletes the statements below?

The hydrogen concentration (1) exceed the lower FLAMMABILITY limit.Hydrogen concentration will be lowered using (2) .(1) DOES (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System (1) DOES(2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation (1) does NOT (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System (1) does NOT (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation A.B.C.D.

84. Unit 1 is operating at 100% when a Pressurizer level control malfunction occurs and the following conditions exist:

• Pressurizer level is 70% and rising.

• Charging flow is 120 gpm.

• Letdown is 60 gpm.

• RCP seal injection is 8 gpm to each RCP.

• RCP seal leakoff is 3 gpm per pump.

• Actions in the field are being taken to regain c ontrol of Charging.

• It will take 8 minutes to regain control of Charging.

Which one of the following co mpletes the statements below?

An automatic reactor trip (1) occur before control of Charging is regained.

Per the BASES of Tech Spec 3.3.

1, Reactor Trip System (RTS)

Instrumentation, the purpose of the automat ic Reactor Trip on Pressurizer Water Level - High is to (2) .Reference Provided (1) WILL(2) provide protection against water relief th rough the PORV's(1) WILL (2) prevent thermal shock of the Spray Nozzle (1) will NOT (2) provide protection against water relief th rough the PORV's (1) will NOT (2) prevent thermal shock of the Spray Nozzle A.B.C.D.

85. Unit 1 is conducting a fuel reload and the following occurs:

At 1015: An Intermediate Leg leak is in progress on the 1A RCS loop with the following conditions.

• R-2, CTMT 155 FT, is in alarm.

• EH2, SFP LVL HI-LO is in alarm.

• Both RHR pumps have been secured due to cavitation.

Which one of the following co mpletes the statements below?

At 1030, an emergency classification

, per NMP-EP-110, Emergency Classification Determinatio n and Initial Action, (1) required.

Per AOP-12, Residual Heat Remo val System Malfunction, themaximum time to complete Containment closure is (2) hour(s).

(1)

(2) IS 1 IS 2 is NOT 1 is NOT 2 A.B.C.D.

86. A fuel shuffle is in progress in the Unit 1 SFP with the following conditions:

At 1000:

• An 1800 lb. load is bei ng moved over spent fuel.

At 1015:

• The load is dropped causing damage to the spent fuel.

At 1015, which one of the fo llowing describes the minimum Radiation Monitor(s) required to be in alarm to meet AOP-30, Refueling Accident, entry conditions?

AND Which one of the following describes the the expected worst case consequences of dropping an 1800 lb. l oad onto the spent fuel Per t he Bases of TR 13.9.4, Crane Travel-Spent Fuel Storage Building?* R-5 OR R-25A* The activity release will be limited to that cont ained in a single fuel assembly.* R-5 OR R-25A* The offsite dose may be as high as but not more than the 10 CFR 100 limit.* R-5 AND R-25A* The activity release will be limited to that cont ained in a single fuel assembly.* R-5 AND R-25A* The offsite dose may be as high as but not more than the 10 CFR 100 limit.

A.B.C.D.

87. Unit 1 was operating at 100% power with the following conditions:

At 1000: A Loss of Offsite Power occurs.

At 1015: The following conditions exist -

• DG-02, 1G 4160 V bus tie to 1L 4160 V bus, has AMBER and GREEN Lights LIT.

• 4160V BUS 1L AC PWR AVAIL lights are NOT lit.

Which one of the following co mpletes the statements below?

At 1015: The 1B DG (1) have cooling water supplied.

At 1015: The REQUIRED ACTION(S) of

Tech Spec(s)

(2) is(are) required to be performed.Tech Spec nomenclature: 3.8.9, Distribution Systems - Operating 3.7.8, Service Water System (SWS)

(1)

(2) WILL 3.8.9 AND 3.7.8 will NOT 3.8.9 AND 3.7.8 WILL 3.8.9 ONLY will NOT 3.8.9 ONLY A.B.C.D.

88. Unit 1 is in Mode 3 with the following conditions:

• Pressurizer level is 22% and stable.

Subsequently, a rupture occurs on the Instru ment Air header piping in the MSVR and AOP-6.0, Loss of Instrum ent Air, is in progress.

Which one of the following co mpletes the statements below? Pressurizer level will (1) . Per AOP-6.0, to maintain Pressurizer level, the operating crew is required to perform actions of (2) in conjunction with AOP-6.0.

Procedure Names

AOP-16.0, CVCS Malfunction SOP-2.1, CVCS Pl ant Startup and Operation (1)

(2) lower AOP-16.0 rise AOP-16.0 lower SOP-2.1 rise SOP-2.1 A.B.C.D.

89. Unit 1 is operating at 100% power when the following occurs:

• R-27B, CTMT HIGH RANGE, is tagged out.

• The instrument power supply fuse to R-27A, CTMT HIGH RANGE, blows.

Which one of the following co mpletes the statements below?

R-27A indication will fail (1) .Per Tech Spec 3.3.3, Post Acciden t Monitoring Instrumentation, theREQUIRED ACTION is to (2) . Reference Provided(1) HIGH(2) immediately initiate action in accordance with S pecification 5.6.8(1) HIGH(2) restore R-27A OR R-27B to OPERABLE status in 7 days (1) LOW(2) immediately initiate action in accordance with S pecification 5.6.8 (1) LOW (2) restore R-27A OR R-27B to OPERABLE status in 7 days A.B.C.D.

90. Unit 1 is operating at 100% power and the following occurs:

• R-15A, SJAE EXH, power supply beco mes erratic causi ng its indication to become unreliable but it does not alarm.Per the ODCM, which one of t he following actions are requi red to continue the releasevia this pathway, if any?

No actions are required.

Continuously collect samples using auxiliary equipment.

Place SJAE filtration in service until R-15A is restored to operable.

Perform grab samples at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyze them within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

A.B.C.D.

91. Unit 1 is in MODE 6 with the following conditions:

• Core reload is complete.

• Control Rod Drive Shaft Latching and RCCA Drag Testing is about to begin per FHP-5.1, Control Rod Drive Shaft Latching/Unlatching Tool Operating Instruction.

Which one of the following co mpletes the statements below? Per FHP-0.0, Refuelin g Organization, the Fuel Handling Supervisor (1) . Per UOP-4.1, Controlling Procedure for Refueling, two Source Range Nuclear Instruments (2) required to be OPERABLE.

(1) is required to be in Containment(2) are NOT (1) is required to be in Containment (2) ARE(1) may be in the Control Room in direct Communicati on with Containment(2) are NOT (1) may be in the Control Room in direct Communicati on with Containment (2) AREA.B.C.D.

92. A tagout is required to be cleared during night shift and the Work Document Holder is not on site and cannot be contacted to gain their approval.

Per NMP-AD-003, Equipment Clearance and Tagging, which one of the following can sign off the Work Docu ment Holder?

Shift Manager Operations Director Maintenance Director Maintenance Manager A.B.C.D.

93. Unit 1 is at 6% power with the following conditions:

• The 1A SGFP has been started.

• AFW is secured.

• The Main Feed Regulating Valves are closed.

At 1000 on January 1, 2015:

• MOV-3232B, MAIN FW TO 1B SG ST OP VLV , is declared INOPERABLE.

At 1200 on January 1, 2015

• FCV-489, 1B SG FW BYP FLOW, is declared INOPERABLE.

Subsequently it is determined that r epairs will take 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> for each valve.

Which one of the following co mpletes the statement below?

Per Tech Spec 3.7.3, Main Feedwater St op Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves, the earliest time that feed flow to the 1B SG must be isolated is

.Reference Provided 1800 on January 1, 2015 2000 on January 1, 2015 1000 on January 4, 2015 1200 on January 4, 2015 A.B.C.D.

94. A General Emergency on Unit 1 has been declared with following conditions:

• An Emergency Response Team is required to be dispatched to isolate an offsite release source.

• The TSC has not yet been manned.

• The expected exposure for the job is 35 REM TEDE per person.

Which one of the following co mpletes the statements below?

To receive the dose listed above, operators (1) required to be volunteers. The (2) will authorize the exposure.

(1)

(2) are NOT RP Supervisor are NOT Shift Manager ARE RP Supervisor ARE Shift Manager A.B.C.D.

95. Unit 1 is in MODE 6 with core offload in progress with the following condition:

• A spent fuel assembly is being moved from its assigned location in the core to the upender.

Subsequently, AOP-30.0, Ref ueling Accident, is entered Which one of the following co mpletes the statements below?

Per AOP-30.0, the Refueling SRO will direct the fuel assembly to be (1) .Per the BASES of Tech Spec 3.9.6, Refueling Cavity Water Level, 23 ft of water is required to be maintained above the fuel to (2) .(1) placed in any empty fuel location in the core(2) provide back up decay heat removal(1) placed in any empty fuel location in the core(2) retain iodine fission product activity in the water during a f uel handling accident(1) returned to its assigned location in the core(2) provide back up decay heat removal(1) returned to its assigned location in the core(2) retain iodine fission product activity in the water during a f uel handling accident A.B.C.D.

96. Unit 2 reactor startup is in progress and the following conditions exist:

• NI31, SR1 COUNT RATE is 10 6 cps and stable.

• NI32, SR2 COUNT RATE is 10 4 cps and stable.

• TSLB-3 1-1, SR HI Q NC-31D is lit.

• TSLB-3 1-2, SR HI Q NC-32D is NOT lit.

• GA1, SR HI FLUX TRIP, is in alarm.

• The Reactor Trip breakers are closed.Subsequently, The Shift Supervisor directs a manual Reactor trip.

• The Reactor Trip breakers open.Which one of the following co mpletes the statements below?An emergency classifica tion threshold value (1) been exceeded per NMP-EP-110-GL01, FNP EALS - ICs, Threshold Values And Basis. The latest time the NRC can be notified is (2) hour(s) after the event / emergency declaration.

(1)

(2) has NOT 4 HAS 4 has NOT 1 HAS 1A.B.C.D.

97. Unit 1 is performing the actions of EEP-0.0, Reactor Trip or Safety Injection, and AOP-9, Loss of Component Cooling Wate

r. Conditions are as follows:

• 1F 4160V bus is de-energized.

• B Train CCW is the "on service" Train.

• 1B CCW pump is Tagged Out.

• 1A CCW pump tripped.

• 1C CHG PUMP is running.

Subsequently, the Shift Supervi sor determines that Firewate r is required to be aligned to the 1B Charging pump

.Which one of the following co mpletes the statements below? The 1C Charging pump will be (1) while aligning Firewater to the 1B Charging pump. (2) Charging pump CCW oil co oler piping will become ch emically contaminated.

(1)

(2) secured ONLY the 1B secured BOTH 1B and 1C maintained running ONLY the 1B maintained running BOTH 1B and 1C A.B.C.D.

98. Unit 1 operating crew has exited EEP-0.0, Reactor Trip or Safety Injection, and is now performing ECP-1.2, LOCA Outside Containment with the following conditions:

• The leak isolation steps are completed.

• RWST level is 12.5 ft.

• RCS pressure continues to lower.

Which one of the following co mpletes the statement below? The next procedure the operating crew is required to transition to is

.EEP-0.0, Reactor Trip or Safety Injection ESP-1.3, Transfer to Cold Leg Recirculation EEP-1.0, Loss of Reac tor or Secondary Coolant ECP-1.1, Loss of Emergency Coolant Recirculation A.B.C.D.

99. Unit 2 is performing the actions of FRP-H.1, Response to Loss of Secondary Heat Sink, and the following conditions exist:

• The TDAFW pump has been returned to service.

• Containment pressure is 0 psig.

• RCS Bleed and Feed was initiat ed, but has now been secured.

• RCS pressure is 1600 psig and rising.

• Pressurizer level is 23% and rising.

Which one of the following co mpletes the statements below?The minimum SG level that permitt ed securing Bleed and Feed was at least one SG (1) .The operating crew will transition to (2) from FRP-H.1. (1) Wide Range level at 14%

(2) ESP-1.1, SI Termination(1) Wide Range level at 14%

(2) EEP-1, Loss of Reactor or Secondary Coolant (1) Narrow Range level at 33%

(2) ESP-1.1, SI Termination (1) Narrow Range level at 33%

(2) EEP-1, Loss of Reactor or Secondary Coolant A.B.C.D.

100. Unit 1 is cooling down per ESP-0.2, Natural Circulation Cooldown to Prevent Reactor Vessel Head Steam Voiding, and the following conditions exist:

• RVLIS is not available.

• RCS Hot leg is 450°F and slowly lowering.

• RCS Cold leg is 425°F and slowly lowering.

• The crew is cooling down at t he maximum rate al lowed by procedure.

• Pressurizer level has just r apidly risen to 78% and is stable

• RCS pressure reduction is not required.

• CST level is 9ft.

Which one of the following co mpletes the statements below?

The operating crew will transition to ESP-0.4, Natural Circulation Cooldown with Allowance for Reactor Vessel Head Steam Voiding (Without RVLIS), based on (1) .The maximum allowable cooldown rate in ESP-0.4 is (2) .Reference Provided (1) CST Level (2) <100°F in any 60 minute period (1) CST Level(2) <50°F/hr (1) Reactor Vessel void formation being indicated (2) <100°F in any 60 minute period (1) Reactor Vessel void formation being indicated(2) <50°F/hr A.B.C.D.

PAM Instrumentation 3.3.3 Farley Units 1 and 2 3.3.3-1 Amendment No. 170 (Unit 1) Amendment No. 163 (Unit 2) 3.3 INSTRUMENTATION

3.3.3 Post Accident Monitoring (PAM) Instrumentation

LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

---

NOTE--------------------------------------------------------

Separate Condition entry is allowed for each Function.

---

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with one required

channel inoperable.

A.1 Restore required channel to OPERABLE status.

30 days B. Required Action and associated Completion

Time of Condition A

not met.

B.1 Initiate action in accordance with

Specification 5.6.8.

Immediately C. One or more Functions with two required

channels inoperable.

C.1 Restore one channel to OPERABLE status.

7 days PAM Instrumentation 3.3.3 Farley Units 1 and 2 3.3.3-2 Amendment No. 185 (Unit 1)

Amendment No. 180 (Unit 2)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion

Time of Condition C

not met. D.1 Enter the Condition referenced in

Table 3.3.3-1 for the

channel.

Immediately E. As required by Required Action D.1 and

referenced in

Table 3.3.3-1.

E.1 Be in MODE 3.

AND E.2 Be in MODE 4.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> F. As required by Required Action D.1 and

referenced in

Table 3.3.3-1. F.1 Initiate action in accordance with

Specification 5.6.8.

Immediately

SURVEILLANCE REQUIREMENTS

---

NOTE--------------------------------------------------------------

SR 3.3.3.1 and SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1.

---

SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required instrumentation channel that is normally energized.

In accordance with the Surveillance Frequency Control Program SR 3.3.3.2 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program PAM Instrumentation 3.3.3 Farley Units 1 and 2 3.3.3-3 Amendment No. 167 (Unit 1)

Amendment No. 159 (Unit 2) Table 3.3.3-1 (page 1 of 1) Post Accident Monitoring Instrumentation

FUNCTION

REQUIRED CHANNELS CONDITION REFERENCED FROM REQUIRED ACTION D.1

1. RCS Hot Leg Temperature (Wide Range) 2 E 2. RCS Cold Leg Temperature (Wide Range) 2 E

3. RCS Pressure (Wide Range) 2 E

4. Steam Generator (SG) Water Level (Wide or Narrow Range) 2/SG E 5. Refueling Water Storage Tank Level 2 E 6. Containment Pressure (Narrow Range) 2 E

7. Pressurizer Water Level 2 E

8. Steam Line Pressure 2/SG E

9. Auxiliary Feedwater Flow Rate 2 E 10. RCS Subcooling Margin Monitor 2 E

11. Containment Water Level (Wide Range) 2 E

12. Core Exit Temperature - Quadrant 1 2 (a) E 13. Core Exit Temperature - Quadrant 2 2 (a) E 14. Core Exit Temperature - Quadrant 3 2 (a) E 15. Core Exit Temperature - Quadrant 4 2 (a) E 16. Reactor Vessel Level Indicating System 2 F

17. Condensate Storage Tank Level 2 E

18. Deleted

19. Containment Area Radiation (High Range) 2 F (a) A channel consists of two core exit thermocouples.

Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 Farley Units 1 and 2 3.7.3-1 Amendment No. 146 (Unit 1) Amendment No. 137 (Unit 2) 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves LCO 3.7.3 Three Main FW Stop Valves, three MFRVs, and associated bypass valves shall be OPERABLE. APPLICABILITY: MODES 1 and 2, except when all main feedwater lines are isolated by either a Main FW Stop Valve, a MFRV and its associated bypass valve or by a closed manual valve. ACTIONS --------------------------------------------------------NOTE------------------------------------------------------------- Separate Condition entry is allowed for each valve.

---

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Main FW Stop Valves inoperable. A.1 Close or isolate Main FW Stop Valve.

ANDA.2 Verify Main FW Stop Valve is closed or isolated. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Once per 7 days B. One or more MFRVs inoperable. B.1 Close or isolate MFRV.

ANDB.2 Verify MFRV is closed or isolated. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Once per 7 days Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 Farley Units 1 and 2 3.7.3-2 Amendment No. 146 (Unit 1) Amendment No. 137 (Unit 2) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One or more MFRV bypass valves inoperable. C.1 Close or isolate bypass valve. ANDC.2 Verify bypass valve is closed or isolated. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Once per 7 days D. Two valves in the same flow path inoperable. D.1 Isolate affected flow path. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> E. Required Action and associated Completion Time not met. E.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the closure time of each Main FW Stop Valve, MFRV, and associated bypass valve is in accordance with the time requirement in the Inservice Testing Plan. In accordance with the Inservice Testing Program.

1/22/201314:30 UNIT 1