ML112170233

Initial Exam 2011-301 Final RO Written Exam

ML112170233
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Site:	Harris
Issue date:	08/02/2011
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ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet US. Nuclear Regulatory Commission 2011 HNP NRC Site-Specific RO Written Examination Applicant Information Name:

Date: Facility/Unit: Shearon Harris / Unit 1 Region: I fl ll niQ IV ReactorType: W CEEIBWLZGELI Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers.

Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.

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

Applicants Signature Results Examination Value 75 Points Applicants Score Points Applicants Grade Percent

2011 HNP SRO NRC Written Exam

1. Given the following plant conditions:

- The plant was operating at 100% for 30 days and has just tripped

- The crew is implementing EPP-004, Rea ctor Trip Response The SRO is directing the OAC to check Source Range detector status (1) What flux level will the Intermediate Range detectors indicate when the Sou Range instruments energize? rce (2) How long after the Reactor trip will it be before the Intermediate Range detectors reach this level?

A. (1) 5 x 10.11 Amps (2) <15 minutes B. (1)5x10iiAmps (2) >20 minutes C. (1) 1 x 1010 Amps (2) <15 minutes D. (1) 1 x 10-10 Amps (2) >20 minutes 1

2011 HNP SRO NRC Written Exam

2. Given the following plant conditions:

- The plant was operating at 100% power The crew performed a manual Reactor Trip and Safety Injection due to RCS leakage in excess of makeup capability

- They have secured one CSIP and have just completed realigning the CSIP discharge from the BIT to the normal Charging line per EPP-008, SI Termination The CRS has directed the OAC to maintain PZR level Which ONE of the following completes the statement below?

Charging flow must NOT exceed (1) gpm to prevent (2) lAW the EPP-008 caution.

A. (1) 120 (2) exceeding normal RCS makeup capability B. (1) 120 (2) damage to the Regenerative Heat Exchanger C. (1) 150 (2) exceeding normal RCS makeup capability D. (1) 150 (2) damage to the Regenerative Heat Exchanger 2

2011 HNP SRO NRC Written Exam

3. Given the following plant conditions:

- The plant was operating at 100% power

- A LOCA occurred Current conditions are:

The crew has just completed checking Main Steam Isolation per step 9 of PATH

-i

- The A and B CSIP will not start

- All RCPs are operating

- Containment pressure is 11 .3 psig and rising

- RCS pressure is 1050 psig

- A Containment Spray pump has tripped, B Containment Spray pump is running

- Pressurizer level is offscale low

- RCS subcooling is 0°F Which ONE of the following describes the crew response to this situation?

A. Trip all RCPs and continue with PATH-I B. Leave all RCPs running and continue with PATH-i C. Trip all RCPs and immediately transition to FRP-J.1, Response to High Containment Pressure D. Leave all RCPs running and immediately transition to FRP-J.i, Response to High Containment Pressure 3

2011 HNP SRO NRC Written Exam

4. Given the following plant conditions:

- The plant is operating at 55% power

- Annunciator ALB-010-1-5, RCP-B TROUBLE has alarmed The crew is implementing AOP-018, Reactor Coolant Pump Abnormal Conditions The OAC identifies that the red light on the B RCP shaft vibration monito r is lit and frame vibrations are increasing Which ONE of the following completes the statements below?

lAW AOP-018, the B RCP has reached its trip limit when shaft vibration levels exceed (1) mils. The reason that the Reactor would be tripped prior to tripping the affected RCP is (2)

A. (1)5 (2) the plant will be in an unanalyzed condition if the RCP is tripped with Reactor power greater than P-8.

B. (1)5 (2) operators are expected to take manual actions prior to reaching the automatic setpoint for prescribed RPS actuations.

C. (1)20 (2) the plant will be in an unanalyzed condition if the RCP is tripped with Reactor power greater than P-8.

D. (1)20 (2) operators are expected to take manual actions prior to reaching the automatic setpoint for prescribed RPS actuations.

4

2011 HNP SRO NRC Written Exam

5. Given the following plant conditions:

- The plant is operating at 100% power

- Rod Control is in Manual Automatic makeup to the VCT secured approximately 10 minutes ago and the system is in AUTO

- The OAC notices that Tavg started to decrease Which ONE of the following identifies the cause of the decr ease in RCS temperature?

A. FCV-1 14B, REACTOR MAKEUP WATER TO BORIC ACID BLENDER, had a loss of air to the valve during the Auto Makeup.

B. FK-1 13, BORIC ACID MKUP FLOW, controller has failed low during the Auto Makeup.

C. A newly replaced CVCS mixed bed demineralizer was put in service.

D. The mixed bed demineralizer is exhausted.

5

2011 HNP SRO NRC Written Exam

6. Given the following plant conditions:

- The plant is in Mode 5

- RHR Train A is in service in shutdown cooling mode

- FK-605A1, RHR Heat Exchanger A Bypass Flow Controller (1 RH-20), is in AUTO

- A rupture has occurred in RHR piping just upstream of FT-605A Compared to prior to the rupture, A-SA RHR current indication will (1) and FK-605A1 output will (2)

A. (1) decrease (2) decrease B. (1) decrease (2) increase C. (1) increase (2) decrease D. (1) increase (2) increase 6

2011 HNP SRO NRC Written Exam

7. Given the following plant conditions:

- The plant is operating at 100% power

- The temperature input to TK-144, LTDN Temperature (1CC-337) fails low Which ONE of the following describes the impact on the plant and the action that is required by the appropriate Annunciator Panel Procedure (APP)?

A. High temperature letdown diversion to VCT; Place TK-144 in manual and adjust flow to restore normal cooling.

B. High temperature letdown diversion to VCT; Isolate letdown and place Excess Letdown in service.

C. Low Letdown temperature causing Tavg to rise.

Place TK-144 in manual and adjust flow to restore normal cooling.

D. Low Letdown temperature causing Tavg to rise.

Isolate letdown and place Excess Letdown in service.

7

2011 HNP SRO NRC Written Exam

8. With the plant operating at 100% power which ONE of the following PZR Pressure Control System Malfunctions will cause PZR Saturation Temperature to RISE?

A. PZR Spray Valve failed open B. PZR Master Controller output fails low C. PZR Master Controller setpoint fails low D. PZR Pressure input to Master Controller fails high 8

2011 HNP SRO NRC Written Exam

9. Given the following plant conditions:

- Reactor Trip testing is in progress on Train A Reactor Trip Breaker A is open

- Reactor Trip Bypass Breaker A is closed

- A transient occurs requiring a Reactor Trip

- The OAC attempts to manually trip the Reactor but the Reactor does NOT trip Which ONE of the following describes the problem that has caused the failure of the Reactor to trip?

A. Reactor trip Bypass Breaker A Undervoltage trip coil failed to deenergize.

B. Reactor trip Bypass Breaker A Shunt trip coil failed to deenergize.

C. Reactor trip Breaker B Undervoltage. trip coil failed to energize.

D. Reactor trip Breaker B Shunt trip coil failed to deenergize.

9

2011 HNP SRO NRC Written Exam

10. Given the following plant conditions:

- PATH-2 is being performed.

- The MSIV on the ruptured SG is mechanically stuck open.

- The Main Steam Isolation Valves (MSIVs) onthe intact SGs are closed.

- A cooldown from 557°F to 485°F at the maximum rate is required.

Which ONE of the following describes the method to accomplish this cooldown in accordance with PATH-2 and the EOP Users Guide?

A. Fully open the intact SG PORVs as fast as possible B. Fully open the Steam Dumps as fast as possible without causing a Main Steam Line Isolation signal C. Fully open the Steam Dumps as fast as possible D. Fully open the intact SG PORVs as fast as possible without causing a Main Steam Line Isolation signal 10

2011 HNP SRO NRC Written Exam

11. Given the following plant conditions:

- The plant was operating at 100% power when a Main Steam line break occurred

- A Reactor Trip and Safety Injection has been actuated

- The crew is implementing EPP-015, Uncontrolled Depressurization of All Steam Generators

- Attempts to close the MSIVs have failed

- Safety Injection has NOT been reset Which ONE of the following:

(1) provides indication in the MCR that a MSLI signal has been generated AND (2) if a MSIV can be closed, what plant parameter is monitored to determine when EPP-015 can be exited?

A. (1) A first out annunciator exists for MSLI actuation (2) RCS loop T-hots B. (1) Lights are available on the Bypass Permissive Panel for MSLI actuation (2) RCS loop T-hots C. (1) A first out annunciator exists for MSLI actuation (2) S/G Pressure D. (1) Lights are available on the Bypass Permissive Panel for MSLI actuation (2) S/G Pressure 11

2011 HNP SRO NRC Written Exam

12. Given the following plant conditions:

- The plant was operating at 100% power

- A Reactor trip and Safety Injection have occurred

- The crew has just reached Entry Point C of PATH-i Current conditions are:

- RCS pressure 1155 psig

- Core Exist T/Cs 564°F

- SG A NR level 42%

- SG B and C NR level 30%

- AFW flow 60 KPPH to each SG

- Containment pressure 3.5 psig

- RWST level 90%

- CST level 7%

- RVLIS Full Range 47%

Which ONE of the following actions is required to be performed next?

A. Implement FRP-H.1, Response To Loss of Secondary Heat Sink B. Implement FRP-C.2, Response To Degraded Core Cooling C. Maintain seal injection flow between 8 and i3gpm D. Align ESW to the AFW pumps 12

2011 HNP SRO NRC Written Exam

13. Given the following plant conditions:

- A LOCA has occurred

- A ESW Booster pump has tripped

- The Crew is implementing FRP-J.1, Response to High Containment Pressure

- Containment pressure is 28 psig Which ONE of the following identifies why ESW to the A Train Containment Fan Coolers is isolated?

A. To prevent an unmonitored release from Containment to the ESW system.

B. To prevent damage to the containment fan coolers from water hammer due to ESW flashing to steam in piping inside Containment due to low fan cooler flow.

C. To prevent damage to the Containment fan coolers from water hammer if the ESW Booster pump is restarted.

D. To prevent infusion of hydrogen into the ESW system from the Containment atmosphere.

13

2011 HNP SRO NRC Written Exam

14. Given the following plant conditions:

- The plant is operating at 100% power

- Instrument Air is aligned in SEQUENCE 2 with all Air Compressors available The following alarms are received sequentially within 1 minute of each other:

ALB-002-8-5, COMPUTER ALARM AIR SYSTEMS

- ALB-002-8-4, SERVICE AIR LOW PRESS

- ALB-002-8-1, INSTRUMENT AIR LOW PRESS Assuming Instrument Air Header pressure is at the setpoint of the last alarm received, which of the following (1) describes the expected operation of the Instrument Air Compressors and (2) the Instrument Air header pressure that would shut I SA-506, Service Air Header Isolation Valve?

A. (1) 1A and lB running ONLY; (2) 90 psig B. (1) IA and lB running ONLY; (2) 75 psig C. (1) IA, lB, and IC running; (2) 90 psig D. (I) 1A, IB, and IC running; (2) 75 psig 14

2011 HNP SRO NRC Written Exam

15. Given the following plant conditions:

- The plant is operating at 50% power with B Safety Train equipment in service

- The crew is implementing AOP-028, Grid Instability, due to degraded grid voltage

- A Emergency bus has been energized from the A EDG lAW AOP-028 Which ONE of the following is correct related to equipment operability under the current conditions?

A. RM-3502A-SA, Cnmt RCS Leak Detection Monitor, is inoperable due to a CVIS.

B. Both Containment Vacuum Breakers are inoperable due to a CVIS.

C. Only the A-SA Train Containment Vacuum Breaker is inoperable due to a CVIS.

D. Only the A-SA Train Containment Vacuum Breaker is inoperable due to a failed closed containment isolation valve on loss of power.

15

2011 HNP SRO NRC Written Exam

16. Given the following plant conditions:

- A Reactor Trip and Safety Injection has occu red

- PATH-I is being implemented and SI has been reset

- RCS Pressure is 1500 psig and stable

- PZR level is off scale low

- Subcooling is 3°F

- Containment pressure 0.2 psig

- Rad monitor, RM-IRR-3597, RHR Pump lB is in high alarm and trending up

- Window 6-3, RAB Equip CID Sump Alert Lvl, is lit on MLB-4A-SA and MLB-4B-SB

- SG levels are: A 23%, B 24%, C 15%

- The operator has reduced total AFW flow to 215 KPPH Based on this information, which ONE of the following procedures will be implemented when exiting PATH-I?

A. FRP-H.1, Response to Loss of Secondary Heat Sink B. EPP-013, LOCA Outside Containment C. EPP-008, SI Termination D: EPP-009, Post LOCA Cooldown and Depressurization 16

2011 HNP SRO NRC Written Exam

17. Why does EPP-012, Loss of Emergency Coolant Recirculation take precedence over FRP-J.1, Response to High Containment Pressure for operation of the Containment Spray Pumps?

The reason is based on A. maintaining Containment heat removal.

B. conserving RWST inventory.

C. limiting Containment pressure.

D. maintaining Containment iodine removal.

17

2011 HNP SRO NRC Written Exam

18. Given the following plant conditions:

- A loss of Feedwater has resulted in a Reactor Trip

- The crew is performing actions of FRP-H.1, Response to Loss of Secondary Heat Sink.

Which ONE of the following describes the operation of the PZR PORVs during this event?

A. Will be operated manually to depressurize the RCS so that Low Steam Pressure and Low PZR Pressure SI signals can be blocked prior to resetting FWIS to allow establishing Main Feedwater flow.

B. Will be operated manually to depressurize the RCS so that Low Steam Pressure and Low PZR Pressure SI signals can be blocked prior to performing action to establish Condensate flow.

C. Manually open all PZR PORVs to depressurize the RCS during Bleed and Feed.

D. All PZR PORVs remain in automatic during Bleed and Feed.

18

2011 HNP SRO NRC Written Exam

19. Given the following plant conditions:

Time = 1000

- Reactor Power is 75% and stable

- Tavg Tref deviation is 0°F and stable

- PZR level is 51% and stable

- Control Bank D step counters are at 165 steps Time =1 002

- Reactor Power is approximately 76% and rising (no load change is in progress)

- Tavg Tref deviation is approximately +2°F and rising

- PZR level 52% and rising

- PZR spray valves have throttled open

- Control Bank D step counters are at 174 steps and stepping out at 8 steps per minute Which ONE of the following describes (1) the event in progress AND (2) the FIRST action that must be performed lAW AOP-00i, Malfunction of Rod Control and Indication System?

A. (1) selected first stage pressure channel high failure (2) Trip the Reactor and go to EOP PATH-i, Reactor Trip or Safety Injection B. (1) selected first stage pressure channel high faHure (2) Place the Rod Bank Selector Switch to MAN.

C. (1) Continuous Spurious Control Bank Withdrawal (2) Trip the Reactor and go to EOP. PATH-i, Reactor Trip or Safety Injection.

D. (1) Continuous Spurious Control Bank Withdrawal (2) Place the Rod Bank Selector Switch to MAN.

19

2011 HNP SRO NRC Written Exam

20. Given the following plant conditions:

- The plant is at 60% power with T-avg at T-ref

- The PZR level channel selector switch (LS-459Z) is in the 460/461 position Which ONE of the following describes the impact of PZ.R level Transmitter LT-460 failing to 55% with these conditions?

(Assume PZR pressure remains constant)

FK-122.1 (ICS-231)

Charging Flow Controller Output PZR backup heaters A. Remains the same energize B. Remains the same remain off C. Decreases energize D. Decreases remain off 20

2011 HNP SRO NRC Written Exam

21. Given the following plant conditions:

- A SG tube leak is in progress on the B SG

- HP estimated the tube leak to be 155 gallons per day

- The crew is implementing AOP-016, Excessive Primary Plant Leakage

- Turbine Building Vent Stack and CVPETS Rad Monitor are in high alarm Which ONE of the following describes the operation of CVPETS?

A. A CVPETS Exhaust Fan started automatically on high radiation and all dampers repositioned automatically on the fan start.

B. A CVPETS Exhaust Fan started automatically on high radiation and the dampers are normally aligned for operation.

C. A CVPETS ExhaUst Fan is started manually on high radiation and all dampers repositioned automatically on fan start.

D. A CVPETS Exhaust Fan is started manually on high radiation and the dampers are normally aligned for operation.

21

2011 HNP SRO NRC Written Exam

22. Given the following plant conditions:

- The plant is operating at 100% power

- A complete loss of Zone I and Zone 2 vacuum occurs Which ONE of the following will (1) automatically operate to stabilize RCS temperature instead of Condenser Steam Dumps AND (2) why does C-9 prevent Condenser Steam Dump operation?

A. (1) Atmospheric Steam Dumps (2) Prevent over-heating of the condenser boot seals B. (1) Atmospheric Steam Dumps (2) Protect the Condenser from an overpressure condition C. (1) Steam Generator PORVs (2) Prevent over-heating of the condenser boot seals D. (1) Steam Generator PORVs (2) Protect the Condenser from an overpressure condition 22

2011 HNP SRO NRC Written Exam

23. Given the following plant conditions:

- A liquid release was planned from the Treated Laundry and Hot Shower (TL&HS)

Tank A

- A resulting Human Performance error inadvertantly lined up the non-sampled TL&HS Tank B for release

- During the release REM-I WL-3540, TL&HS Tank Pump Discharge went into HIGH Alarm Which ONE of the following describes (I) how the accidental release is terminated AND (2) the reason for terminating the release?

A. (1) the running TL&HS Tank Pump will aqtomatically trip (2) to prevent contamination of the cooling tower basin B. (I) 3LHS-296, TREATED L&HS TKS DISCH ISOL VLV, will automatically close (2) to prevent contamination of the cooling tower basin C. (I) the running TL&HS Tank Pump will automatically trip (2) to ensure the release is less than the regulatory limits D. (1) 3LHS-296, TREATED L&HS TKS DISCH ISOL VLV, will automatically close (2) to ensure the release is less than the regulatory limits 23

2011 HNP SRO NRC Written Exam

24. Given the following plant conditions:

- An electrical fire in the MCR has resulted in the evacuation of the MCR to the ACP

- You have been directed to monitor in core thermocouple temperatures from outside the MCR per AOP-004, Remote Shutdown Which ONE of the following (1) identifies the location of the Inadequate Core Cooling Monitor local microprocessor panel AND (2) the method of obtaining readings at the panel?

A. (1) PlC Room C-17 RAB 286 (2) Using CRT monitor and keyboard.

B. (1) PlC Room C-17 RAB 286 (2) Using thumbwheels set to specific points identified by a legend.

C. (1) Main Termination Cabinet RAB 305 (2) Using CRT monitor and keyboard.

D. (1) Main Termination Cabinet RAB 305 (2) Using thumbwheels set to specific points identified by a legend.

24

2011 HNPSRQ NRC Written Exam

25. Given the following plant conditions:

- A cold leg break LOCA has occurred and the crew is implementing PATH-I

- ALL RCPs are stopped

- Containment pressure is 8 psig

- ERFIS is NOT available Time Core Exit TCs RCS Pressure RVLIS Full Range 0000 450°F 800 psig 55%

0030 550°F 900 psig 45%

0100 700°F 700 psig 35%

0130 800°F 600 psig 25%

0200 1220°F 500 psig 20%

Based on the values of the Core Exit TCs, RCS pressure, and RVLIS Full Range level above at given times; at what time does the transition to:

1.) degraded core cooling first occur.

2.) inadequate core cooling first occur.

A. (1) 0030 (2) 0130 B. (1)0030 (2) 0200 C. (1)0100 (2) 0130 D. (1)0100 (2) 0200 25

2011 HNP SRO NRC Written Exam

26. Given the following plant conditions:

- At 0530, RCS temperature was being maintained at 557°F with the plant in Mode 3 when a Small Break LOCA occurred

- At 0545, RCS temperature is 550°F

- The crew is ready to commence a cooldown to cold shutdown lAW EPP-009, Post LOCA Cooldown and Depressurization Which ONE of the following identifies (1) the lowest allowable temperature of the RCS at 0630 if the crew begins the MAXIMUM permissible cooldown rate AND (2) the basis for this temperature limit?

A. (1)457°F (2) to ensure that Tech Spec cooldown limits are NOT exceeded B. (1)457°F (2)to ensure that a transition is NOT required to be made to FRP-P.1, Response to Imminent Pressurized Thermal Shock C. (1)450°F (2) to ensure that Tech Spec cooldown limits are NOT exceeded D. (1)450°F (2) to ensure that a transition is NOT required to be made to FRP-P.1, Response to Imminent Pressurized Thermal Shock 26

2011 HNP SRO NRC Written Exam

27. Given the following plant conditions:

- A Reactor trip occurred due to a Loss of Offsite Power

- The plant is being cooled down on RHR per EPP-006, Natural Circulation Cooldown with Steam Void in Vessel With RVLIS

- RCS cold leg temperatures are 190°F

- Steam generator pressures are <50 psig

- RVLIS upper range indicates greater than 100%

- Two CRDM fans have been running during the entire cooldown lAW EPP-006, steam should be dumped from all SGs to ensure...

A. RCS temperatures do NOT increase during the required 29 hour3.356481e-4 days <br />0.00806 hours <br />4.794974e-5 weeks <br />1.10345e-5 months <br /> vessel soak period.

B. boron concentration is equalized throughout the RCS prior to taking a sample to verify cold shutdown boron conditions.

C. all inactive portions of the RCS are below 200° F prior to complete RCS depressurization.

D. secondary side water temperatures are less than 50°F above RCS cold leg temperatures prior to any subsequent RCP restart if off-site power is restored.

27

2011 HNP SRO NRC Written Exam

28. Given the following plant conditions:

At 0955

- A Unit startup is in progress lAW GP-004, Reactor Startup (Mode 3 to Mode 2)

- Reactor trip breakers are CLOSED

- All Shutdown banks are fully inserted

- Annunciator ALB-01 0-2-3, RCP-A Trouble, alarmed

- AOP-01 8, Reactor Coolant Pumps Abnormal Conditions was entered At 1005 the crew secured A RCP when its motor bearing temperatures approached the pump trip limit At 1020 Start Up XFMR A to Aux Bus A breaker 107 tripped open Which ONE of the following completes the statement below?

At (1) Tech Spec 3.4.1.2 LCO is NOT met and the Reactor Trip breakers must be opened (2) per the Tech Spec required action.

A. (1) 1005 (2) immediately B. (1) 1005 (2) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. (1) 1020 (2) immediately D. (1) 1020 (2) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 28

2011 HNP SRO NRC Written Exam

29. Given the following plant conditions:

- The plant is in Mode 4

- Preparations are underway to start the A RCP Which ONE of the following conditions does NOT meet the RCP starting requirements lAW OP-I 00, Reactor Coolant System?

A. VCT pressure is 11 psig B. RCS pressure is 330 psig C. RCP #1 seal leakoff flow is 0.85 gpm D. RCP #1 seal Delta P is 210 psid 29

2011 HNP S RQ t4RC Written Exam

30. Given the following plant conditions:

- The plant is operating at 100% power

- The OAC provides a crew update that PZR level is trending DOWN and VCT level is trending UP

- RCS temperature and pressure are stable Which ONE of the following describes the event in progress AND action required?

A. Charging line leak outside Containment. Isolate the leak lAW AOP-016, Excessive Primary Plant Leakage.

B. Letdown line leak outside Containment. Isolate the leak lAW AOP-016, Excessive Primary Plant Leakage.

C. Letdown pressure control valve, ICS-38 (PCV-145), has failed shut. Isolate letdown lAW the applicable Annunciator Panel Procedures.

D. Charging flowcontroller failed to minimum. Establish Manual control of Charging flow or isolate Letdown lAW the applicable Annunciator Panel Procedures.

30

2011 [-INP SRQ NRC Written Exam

31. Given the following plant conditions:

- The plant is operating in Mode 1

- 1 RH-I and 1 RH-2,RHR Hot Leg Loop 1 Isolation Valves are closed Which ONE of the following describes (I) the power supply AND (2) breaker status for 1 RH-I and I RH-2?

A. (I) 1RH1 is powered from 1A21-SA, 1RH2 is powered from 1B21-SB.

(2) breakers are CLOSED B. (I) IRH1 is powered from 1A21-SA, 1RH2, is powered from 1B21-SB.

(2) breakers are OPEN C. (I) 1RHI is powered from 1B21-SB, IRH2, is powered from 1A21-SA (2) breakers are CLOSED D. (I) 1RH1 is powered from 1B21-SB, 1RH2, is powered from 1A21-SA (2) breakers are OPEN 31

2011 1-INP SRÜ NRC WritteftExarn.

32. Given the following plant conditions:

- The plant is in Mode 6 and core reload has just commenced

- A Train RHR is in service

- B Train RHR is under clearance for breaker overhaul and not expected to be returned for service for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

- Cavity level is 23 feet 4 inches above the Reactor Vessel Flange

- RCS temperature is 80°F

- A RHR Pump trips for an unknown reason Which ONE of the following describes, the actions required associated with this event?

A. Actuate Phase A Isolation B. Immediately suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System.

C. Refueling activities are permitted for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> while repairs are initiated to A RHR Pump.

D. Immediately close or verify closed all Containment penetrations providing direct access from the containment atmosphere to the outside atmosphere 32

201t HNP SRO 1tRCWritten Exam

33. Which ONE of the following completes the statements below?

lAW PATH-I Foldout A:

- The minimum RCS pressure that the CSIP alternate miniflow isolation or miniflow block valves are verified closed is (I) psig

- The maximum RCS pressure that the CSIP alternate miniflow isolation or miniflow block valves are verified open is (2) psig A. (1)1400 (2) 2200 B. (1) 1400 (2) 2000 C. (1) 1800 (2) 2200 D. (1)1800 (2) 2000 33

2Q11 HNP SRO NRC Written Exam

34. Given the following plant conditions:

- The plant has experienced a Large Break LOCA

- RWST level has decreased to 23%

- The operating crew has implemented plant procedures to transfer to Cold Leg Recirculation lAW EPP-O1O, Transfer to Cold Leg Recirculation Which ONE of the following conditions is consistent with the desired lineup of the Residual Heat Removal system for this condition?

A. 1Sl-359 SA, Low Head SI Trains A & B to Hot Leg is OPEN B. 1SI-340 SA, Low Head SI Train A to Cold Leg AND 1SI-341 SB, Low Head SI Train B to Cold Leg are OPEN C. 1 RH-25, Suction from RHR Heat Exchanger A-SA AND 1 RH-63, Suction from RHR Heat Exchanger B-SB are OPEN D. 1 S 1-326 SA, Low Head SI Train A to Hot Leg Crossover AND 1SI-327 SB, Low Head SI Train B to Hot Leg Crossover are SHUT 34

2011 KNPSRG11RCWrittertExani

35. Given the following plant conditions:

- A PZR safety valve is leaking by its seat PRT pressure is currently 28 psig and increasing

- PRT level is 72% and increasing IF the present conditions continue, (I) when will the PRT high level alarm first occur AND (2) lAW OP-I 00, Reactor Coolant System, in order to prevent the PRT from going water solid, which pump will the operator use to transfer the PRT to the RHT?

A. (1) 78%

(2) the Reactor Coolant Drain Tank Pump B. (1) 83%

(2) the Reactor Coolant Drain Tank Pump C. (1) 78%

(2) the Boron Recycle Evaporator Feed Pump D. (1) 83%

(2) the Boron Recycle Evaporator Feed Pump 35

2011 RNP SRO NRCWrtten Exam

36. Which ONE of the following describes (1) the power supplies that the C CCW pump can be aligned to AND (2) which design feature prevents two CCW pumps from being aligned to the same power supply?

A. (1) Either Emergency Bus IA-SA or Emergency Bus lB-SB (2) A key-operated interlock B. (1) Either Emergency Bus 1A2-SA or Emergency Bus 1 B2-SB (2) A key-operated interlock C. (1) Either Emergency Bus I A-SA or Emergency Bus 1 B-SB (2) A manual transfer switch must be aligned to the appropriate power supply.

D. (1) Either Emergency Bus 1A2-SA or Emergency Bus 1 B2-SB (2) A manual transfer switch must be aligned to the appropriate power supply.

36

2011 l4NPSRGNRGWritten Exam

37. Given the following plant conditions:

The plant is operating at 100% power

- An inadvertent Containment Isolation Phase B has actuated lAW AOP-018, Reactor Coolant Pump Abnormal Condition, which ONE of the following describes the operational impact on the RCPs if Phase B cannot be reset?

A. RCP operation may continue provided that RCP radial bearing temperatures remain less than 230°F B. RCP operation may continue provided that normal seal injection flow is maintained C. RCPs must be stopped within 10 minutes D. RCPs must be stopped immediately 37

2011.EINPSRQNRCWrIItenExam

38. The plant is operating at 100% power when the following sequence of events occurs:

- PZR Power Operated Relief Valve (PORV) 1 RC-1 18 opens and sticks open.

- The associated PZR PORV Block valve, I RC-1 17 cannot be closed.

- Pressurizer Relief Tank (PRT) pressure is increasing.

Which ONE of the following completes the statement below?

The PRT rupture disc will release prior to the PRT exceeding a design pressure of after which point Pressurizer Power Operated Relief Valve tailpipe temperature will PRT Rupture Disc Setpoint PORV Tailpipe Temperature A. 100 psig Lower B. 100 psig Remain the same C. 150 psig Lower D. 150 psig Remain the same 38

.2011 I-IN? SRQ NR WritteftExam

39. With Reactor power stable at 45%, (1) what is the coincidence for the RCS Loop Lo Flow Reactor.trip and (2) what is the basis for this Reactor trip?

A. (1) 2 of 3 bistables on 1 of 3 loops (2) loss of fuel integrity B. (1) 2 of 3 bistables on 2 of 3 loops (2) loss of fuel integrity C. (1) 2 of 3 bistables on 1 of 3 loops (2) DNB protectIon D. (1) 2 of 3 bistables on 2 of 3 loops (2) DNB protection 39

2Q11 HNP SRQ NRC WrittenExam

40. Given the following plant conditions

- The plant was operating at 100% power

- A LOCA has occurred and the crew is implementing PATH-I.

- The crew incorrectly resets the SI Suction Auto Switchover signal vice the SI signal when directed to reset SI in PATH-I.

Which ONE of the foNowing completes the statement below?

The recirc sump suction valves to the (1) will not automatically open when the RWST low-low level setpoint is reached and the CSIP alternate miniflow isolation valves (2) automatically open and shut on RCS pressure.

A. (1) RHR pumps ONLY (2) will NOT B. (1) RHR pumps and Containment Spray pumps (2) will NOT C. (1) RHR pumps ONLY (2) will D. (1) RHR pumps and Containment Spray pumps (2) will 40

2011 HNP SRQ NRC Written Exam

41. Which ONE of the following identifies the earliest time that Tech Spec 3.6.1.5, Containment Systems Air Temperature, is required to be entered?

HIGHEST AVERAGE TIME Cnmt Air Temp Cnmt Air Temp A 1000 122°F 118°F B. 1010 121°F 116°F C 1020 124°F 119°F D. 1030 126°F 121°F 41

2O1tI-tPSRQNRCWri1tenExani

42. Which ONE of the foflowing identifies the minimum required logic for MANUAL actuation of the Containment Spray System using the MCB Containment Spray activation switches?

A. Any ONE of the FOUR switches B. Any TWO of the FOUR switches C. Either the inside TWO switches OR the outside TWO switches D. Either the left TWO switches OR the right TWO switches 42

2011 HNP SRO NRC Wrtten Exam

43. Given the following plant conditions:

- A Unit startup is in progress following a mid-cycle outage

- The Reactor is critical at 10-8 amps

- A SG PORV valve failed open Which ONE of the following describes the initial response of SG level after the PORV pens and final Reactor power?

(Assuming NO action by the operating crew)

SG Level Reactor Power A. goes down at the Point of Adding Heat B. goes down exceed the POAH C. goes up at the Point of Adding Heat D. goes up exceed the POAH 43

2Q11 HNP SRO NRC Written Exam

44. Given the following plant conditions:

- A plant startup is in progress with Reactor power at 8%

- The B Main Feed Pump is in operation The following events occur:

- B Main Feed Pump trips on overcurrent

- A Main Feed Pump automatically starts but trips on low oil pressure

- The crew has entered AOP-01O, Feedwater Malfunctions

- Steam Generator Levels are as follows:

A SIG 30% NR and decreasing B SIG 29% NR and decreasing C SIG 28% NR and decreasing Which ONE of the following describes (1) the current status of the AFW system and (2) how will the plant be stabilized?

A. (1) ONLY Motor Driven AFW pumps have auto started (2) the Reactor must be manually tripped lAW AOP-01 0 B. (1) ONLY Motor Driven AFW pumps have auto started (2) Reactor power must be reduced to maintain SG levels 52% 62% using AFW flow C. (1) Currently AFW pumps must be MANUALLY started (2) the Reactor must be manually tripped lAW AOP-01 0 D. (1) Currently AFW pumps must be MANUALLY started (2) Reactor power must be reduced to maintain SG levels 52% 62% using AFW flow 44

2011 HNP SRO NRC Written Exam -,

45. Given the following plant conditions:

- The plant is operating at 100% power

- A feed flow instrument on the C SG causes the Main Feed Regulating Valve to go full open.

- C SG level reaches 80%

- An automatic Reactor and Turbine trip occurs.

Current plant conditions:

- The A Reactor Trip Breaker failed to open

- RCS temperature is 553°F For the above listed conditions, what are the positions of the following feedwater components for the C SG?

IFW-191 IFW-217 (Main FW C Regulator) (Main FW C Isolation)

A. Open Closed B. Open Open C. Closed Open D. Closed Closed 45

2011 HNP SRO NRC Written Exam

46. Given the following plant conditions;

- The plant experienced a Reactor trip from 100% power.

- The Operators have not operated any controls post-trip.

- The crew completed PATH-i, Reactor Trip and Safety Injection, and has entered EPP-004, Reactor Trip Response.

- Pressurizer level is 25% and slowly decreasing.

- All Steam Generator levels are between 12% and 18% narrow range and slowly rising.

- Steam Generators pressures are approximately 990 psig and slowly decreasing.

- Tavg is 545° F and slowly decreasing.

- RCS pressure is 2020 psig and slowly decreasing.

Which ONE of the following actions should be the first priority of the crew lAW with EPP-004 to address the conditions?

A. Establish Emergency Boration B. Close MSIVs and bypass valves C. Throttle Auxiliary Feedwater Flow D. Initiate Safety Injection and Return to PATH-I 46

?01 I HNP SRO NRC Written Exam

47. Given the following plant conditions:

- The plant is operating at 100% power

- The AMDAFW pump is under clearance

- A loss of B-SB 125V DC power occurs Which ONE of the following identifies:

1.) The response of the TDAFW Pump after the pump start signal occurs 2.) The method of controlling TDAFW speed with the Trip and Throttle Valve (T&TV) lAW OP-i 37, Auxiliary Feedwater System?

A. (1) start and trip on overspeed (2) throttle using controls at the local control panel B. (I) start and trip on overspeed (2) throttle using the manual handwheel C. (1) start and idle at 1000 rpm (2) throttle using controls at the local control panel D. (I) start and idle at 1000 rpm (2) throttle using the manual handwheel 47

2011 HNP SRO NRC Written Exam

48. Given the following:

- The unit is operating at 100% power

- A Fire in Aux Bus IE1 occurs, resulting in the loss of Aux Bus E Which ONE of the following describes the battery charger(s) that temporarily lose power and will automatically be re-energized?

A. IA-SAandlB-SA B. 1A-SBand lB-SB C. 1A-SAor1B-SA D. 1A-SBorIB-SB 48

2011 HNP SRO NRC Written Exam

49. Given the following plant conditions:

- A loss of AC power has occurred

- 125 VDC battery IA-SA is currently loaded at rated load DC load shedding has been performed to reduce the battery load to half of rated load.

How long will the battery be available to supply the remaining loads?

A. More than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> B. More than 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> but less than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> C. More than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> but less than 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> D. upto4hours 49

2011 HNP SRO NRC Written Exam

50. Which ONE of the following describes the normal power source for a safety-related 125-V DC bus?

480-V MCC through a...

A. battery charger to the DC bus.

B. battery charger, through the DC battery, and then to the DC bus.

C. 7.5-KVA inverter, through the DC battery, and then to the DC bus.

D. 7.5-KVA inverter to the DC bus.

50

2011 HNP SRO NRC Written Exam

51. During performance of AOP-004, Remote Shutdown, which ONE of the following describes the responsibility of the BOP operator?

A. Locally operate and control CSIPs for RCS Makeup B. Monitor and control plant conditions from the Auxiliary Control Panel.(ACP)

C. Operate plant equipment at the Auxiliary Transfer Panel (ATP) and Switchgear Rooms D. Locally trip RCP breakers and start and control EDGs locally to provide safety-related power 51

2011 HNP SRO NRC Written Exam

52. Given the following plant conditions:

- An elevated reading of 10 mR/hour was observed on RM-3601, the Letdown HX Valve Gallery Radiation Monitor.

- Health Physics identified a hot spot in the letdown piping 20 feet from the RM-3601 detector.

- Operations flushed the hot spot and relocated it to 5 feet from the RM-3601 detector.

Based on current conditions, which ONE of the following identifies the expected radiation reading on RM-3601?

(Assume the hot spot in the pipe is a point source)

A. 20 mR/hr B. 40 mR/hr C. 80 mR/hr D. 160 mR/hr 52

2011 HNP SRO NRC Written Exam

53. Given the following plant conditions:

A NSW pump is running in normal alignment with B NSW pump secured Which ONE of the following identifies the Service Water valve alignment two minutes after B Emergency Service Water (ESW) pump is taken to START?

- ISW-40, NSW SUPPLY to B ESW header will be (1)

- 1SW-276, ESW TO NSW COMMON RETURN will be (2)

• (1) * (2) -

A. shut

• shut B. open open C. shut open D. open shut 53

2011 HNP SRO NRC Written Exam

54. Given the following plant conditions:

- The plant startup is in progress with the Reactor critical at 10-8 amps

- P 1-9751 .1 MCB Instrument Air Header Pressure instrument is broken and a work request has been generated

- Annunciator ALB-002-8-1, Instrument Air Low Pressure has just gone into alarm

- At 0800, the crew implemented AOP-01 7, Loss of Instrument Air

- The BOP runs group display AOP-017 on ERFIS

- ERFIS Instrument Air pressure point P1A9751 trends the following:

Time PIA9751 0815 88.5 psig 0830 74.6 psig 0850 57.4 psig 0910 33.8 psig Which ONE of the following identifies the FIRST time the crew will be required to manually Trip the Reactor lAW AOP-017?

A. 0815 B. 0830 C. 0850 D. 0910 54

2011 HNP SRO NRC Written Exam

55. Given the following plant conditions:

- A LOCA has occurred

- RCS pressure is 600 psig and stable

- Containment pressure is 11 .5 psig and lowering

- SI has NOT been reset

- The OAC has placed the reset switches for Containment Isolation Phase A and Phase B to RESET Which ONE of the following describes the status of Containment Isolation Phase A and Phase B signals?

PhaseA Phase B A. will NOT reset will reset B. will NOT reset will NOT reset C. will reset will reset D. will reset will NOT reset 55

2011 HNP SRO NRC Written Exam

56. The plant is in Mode 4.

The RCS has the following leak rates:

- Primary to secondary SG A 0.08 gpm

- Primary to secondarySGB 0.11 gpm

- Primary to secondary SG C 0.07 gpm

- Leakage by the PZR Safeties to PRT 5.40 gpm

- Total leakage from RCS 5.82 gpm Which ONE of the following RCS Tech Spec leakage limits is being exceeded?

A. Primary to Secondary Leakage B. Unidentified Leakage C. Pressure Boundary Leakage D. Identified Leakage 56

2011 HNP SRO NRC Written Exam

57. Given the following plant conditions:

- A Reactor startup is in progress lAW GP-004, Reactor Startup

- The OAC is currently withdrawing Control Bank C rods Which ONE of the following is the indicated rod height on the Control Bank C Step Counters at which Control Bank D rods are expected to begin withdrawing and what is the expected rod speed?

Control Bank C Step Counter Indication Control Bank D Rod Sjeed A. 100 Steps 48 SPM B. 100 Steps 64SPM C. 128 Steps 48SPM D. 128 Steps 64SPM 57

2011 HNP SRO NRC Written Exam

58. Given the following plant conditions:

- The crew is performing EPP-004, Reactor Trip Response

- Natural circulation verification is in progress.

- Core Exit Thermocouples G2 and K5 have failed due to open circuits.

With these open circuit failures, the input from these thermocouples to the Inadequate Core Cooling Monitor (ICCM) will be (1) and the subcooling margin calculated by 10CM will be (2)

A. (1) failed low (2) unaffected B. (1) failed low (2) higher C. (1) failed high (2) unaffected D. (1) failed high (2) lower 58

2011 HNP SRO NRC Written Exam

59. Which ONE is the power supply for S-IA and S-I B, Containment Airborne Radioactivity Removal (ARR) Fans?

S-lA S-lB A. MCC1A2I-SA MCC 1B21-SB B. 480V Bus IAI 480V Bus 1BI C. 48OVBus1D2 480V Bus 1E2 D. MCC1DII MCC 1EII 59

2011 HNP SRO NRC Written Exam

60. Given the following:

- The unit is in Mode 6.

- Refueling activities are in progress.

- A fuel assembly has been slightly damaged during removal from the core.

- Radiation levels are rising steadily and are currently as follows:

- REM-OILT-3502A-SA, Cnmt RCS Leak Detection Monitor, is in HIGH ALARM Which ONE of the following describes the system isolation signal(s), if any, that have been automatically initiated as a result of this alarm?

A. ONLY Normal Containment Purge.

B. ONLY Containment Pre-Entry Purge.

C. BOTH Normal Containment Purge AND Containment Pre-Entry Purge.

D. NEITHER Normal Containment Purge NOR Containment Pre-Entry Purge.

60

2011 HNP SRO NRC Written Exam

61. Which ONE of the following completes the statement below?

During refueling operations the fuel assemblies are removed from the core using the Manipulator crane (1) hoist that is equipped with a primary overload cutout limit switch that is set at a maximum of (2) pounds.

A. (1) main (2) 2700 B. (1) main (2) 3000 C. (1) auxiliary (2) 2700 D. (1) auxiliary (2) 3000 61

2011 HNP SRO NRC Written Exam

62. Given the following plant conditions:

- A Waste Gas release is in progress when the associated radiation monitor exceeds its high alarm setpoint.

Which ONE of the following describes: (1) how the release will be automatically terminated AND (2) in which stack this radiation will be detected.

A. (1) 3WG-230, Gas Decay Tanks to Plant Vent Isolation Valve, CLOSES (2) Stack 5 B. (1) 3WG-229, Waste Gas Decay Tanks E & F to Plant Vent, CLOSES (2) Stack 5 C. (1) 3WG-230, Gas Decay Tanks to Plant Vent Isolation Valve, CLOSES (2) Stack 5A D. (1) 3WG-229, Waste Gas Decay Tanks E & F to Plant Vent, CLOSES (2) Stack 5A 62

2011 HNP SRO NRC Written Exam

63. Given the following plant conditions:

- The plant is operating at 100% power

- Irradiated Fuel movement is being performed in the Spent Fuel Pool in preparation for Refueling

- Fuel Handling Building area radiation monitor RM1*FR3564ASA, fails HIGH and is declared inoperable Which ONE of the following completes the statements below?

Fuel Handling Building Emergency Exhaust Unit E-12 (1)

Fuel movement (2)

A. (1) Receives an auto start signal (2) may continue with no additional actions required.

B. (1) Receives an auto start signal (2) must be immediately suspended C. (1) Does NOT receive an auto start signal (2) may continue with no additional actions required D. (1) Does NOT receive an auto start signal (2) must be immediately suspended 63

2011 HNP SRO NRC Written Exam

64. Given the following plant conditions:

- The plant was operating at 54%

- C CWP under clearance

- B CWP tripped and Condenser vacuum has began degrading

- A manual Reactor/Turbine trip was initiated per AOP-012, Partial Loss of Condenser Vacuum

- The operating crew is stabilizing the plant Which ONE of the following identifies both the value of Condenser vacuum the Reactor/Turbine should have been manually tripped at per AOP-012 AND the expected response of Condenser vacuum after the Turbine trip?

Manual Trip on Vacuum Condenser Vacuum A. 7.5 inches Hg Degrading B. 7.5 inches Hg Improving C. 5.0 inches Hg Degrading D. 5.0 inches Hg Improving 64

2011 HNP SRO NRC Written Exam

65. Given the following conditions:

You are in the Admin Building PABX Room

- The fire suppression system has actuated Which ONE of the following describes (1) the fire extinguishing agent used in the Admin Building PABX Room AND (2) the hazard level to personnel in the room from the extinguishing agent? -

A. (1) C02 (2) life threatening B. (1) CO2 (2) NOT life threatening C. (1) Halon (2) NOT life threatening D. (1) Halon (2) life threatening 65

2011 HNP SRO NRC Written Exam

66. Given the following plant conditions:

- The plant is in Mode 6

- An Emergency call has just been received from the Fuel Handling Building (FHB) that there was a loud banging noise coming from the lower levels in the FHB

- Fuel Handlers are waiting for an assembly to be placed in the upender on the Reactor side prior to transferring the assembly to the A Fuel Pool

- Cavity and Spent Fuel Pool levels are observed to be decreasing lAW AOP-031, Loss of Refueling Cavity Integrity, which ONE of the following coordinated activities will be directed by the operators in the control room?

Once all fuel assemblies are safely stored...

A. Direct the Fuel Handling crew to move the Fuel Transfer Cart to the Fuel Handling Building side Dispatch an operator to shut 1 PP-427, Fuel Transfer Tube Gate Valve B. Direct the Fuel Handling crew to move the Fuel Transfer Cart to the Fuel Handling Building side Direct Maintenance to install and inflate Fuel Pool gates to the Unit 1&4 Transfer Canal C. Direct the Fuel Handling crew to maintain the Fuel Transfer Cart on the Reactor side Dispatch an operator to shut I PP-427, Fuel Transfer Tube Gate Valve D. Direct the Fuel Handling crew to maintain the Fuel Transfer Cart on the Reactor side Direct Maintenance to install and inflate Fuel Pool gates to the Unit 1 &4 Transfer Canal 66

2011 HNP SRO NRC Written Exam

67. Per SAF-NGGC-21 75, Electrical Safety and Arc Flash Protection, which ONE of the following describes:

1) What is the minimum voltage that requires a safety person?

2) What a designated electrical safety person is allowed to do while critical work is in progress?

A. (1) When working on or near exposed energized parts >150 Volts.

(2) Verify that a correct component is being manipulated.

B. (1) When working on or near exposed energized parts >150 Volts.

(2) Hold open doors or covers for others to perform work.

C. (1) When working on or near exposed energized parts >300 Volts.

(2) Verify that a correct component is being manipulated.

D. (1) When working on or near exposed energized parts >300 Volts.

(2) Hold open doors or covers for others to perform work.

67

2011 HNP SRO NRC Written Exam

68. Given the following plant conditions:

- The plant is operating at 100% power

- Troubleshooting is in progress on the 1A-SA ESCW Chiller lAW AP-929, Troubleshooting Guide

- Leads must be lifted in the Control Circuit to support the troubleshooting

- The lead lift does not pose a risk of personnel injury or equipment damage Which of the following identify acceptable methods for documenting the lead lift lAW AP-929?

1. Clearance Order (OPS-NGGC-1 301, Equipment Clearance)

2. Verification Sign-Off Sheet (OPS-NGGC-1 303, Independent Verification)

3. Component Manipulation Sign-Off Sheet (OPS-NGGC-1 308, Plant Status Control)

4. Add to the Work Order Instructions at the time of lift (ADM-NGGC-0104, Work Management Process)

A. land2 B. 2and3 C. 3and4 D. land4 68

2011 HNP SRO NRC Written Exam

69. Given the following plant conditions:

- The Reactor is shutdown for a scheduled refueling outage

- An RCS cooldown is in progress lAW GP-007, Normal Plant Cooldown The following information is a plot of the cooldown:

TIME RCS Tcold 0830 51 6°F 0845 505°F 0900 489°F 0915 478°F 0930 465°F 0945 425°F 1000 386°F 1015 382°F 1030 364°F 1045 349°F 1100 336°F 1115 320°F 1130 309°F 1145 297°F At which time was the Tech Spec RCS Cooldown rate limit FIRST exceeded?

A. 0930 B. 1000 C. 1030 D. 1145 69

2011 HNP SRO NRC Written Exam

70. Which ONE of the following identifies (1) the annual administrative limit for TEDE at HNP AND (2) the Emergency Exposure Limit for protecting valuable property lAW PEP-330, Radiological Consequences?

A. (1)5reni (2) 25 rem B. (1)2ren, (2) 25 rem C. (1)5rem (2) 10 rem D. (1)2rem (2) 10 rem 70

2011 HNP SRO NRC Written Exam

71. Given the following plant conditions:

- The plant is operating at 100% power

- ALB-10-4-5, RAD MONITOR SYSTEM TROUBLE has alarmed

- Both REM-Ol LT-3502ASA, CNMT RCS Leak Detection Monitor, AND RM-1CR-3561A-SA, CNMT Vent Isolation Monitor, are in High Alarm Which ONE of the following identifies actions required lAW annunciator panel procedures AND AOP-005, Radiation Monitoring System?

A. Verify Containment Ventilation Isolation Monitor PZR level and CNMT conditions B. Verify Containment Ventilation Isolation Verify proper equipment alignment using OMM-004, Post-Trip/Safeguards Actuation Review C. Verify Containment Purge isolated Monitor PZR level and CNMT conditions D. Verify Containment Purge isolated Verify proper equipment alignment using OMM-004, Post-Trip/Safeguards Actuation Review 71

2011 HNPSRO NRC Written Exam

72. The crew is implementing PATH-2 due to a SGTR. The ruptured SG PORV controller setpoint has been adjusted to 88% (1145 psig).

This controller setpoint is designed to serve which of the following purposes?

A. Minimize RCS to SG AP and minimize challenges to the Code Safety valves.

B. Minimize atmospheric releases and minimize challenges to the Code Safety valves.

C. Minimize RCS to SG AP and maintains ruptured SIG PORV available for cooldown.

D. Minimize atmospheric releases and maintains ruptured SIG PORV available for cooldown.

72

2011 HNP SRO NRC Written Exam

73. Given the following plant conditions:

- A LOCA has occurred

- Both CSIPs are tripped

- A RED Path CSF is confirmed on Core Cooling

- A RED Path CSF is confirmed on Heat Sink

- The operating crew is performing FRP-C.1, Response To Inadequate Core Cooling

- The RWST LO-LO LEVEL alarm just annunciated Which ONE of the following identifies when the crew must transition to EPP-010, TRANSFER TO COLD LEG RECIRCULATION?

A. After receiving ALB-0412-5, REFUELING WATER STORAGE TANK EMPTY alarm B. When directed by FRP-C.1 to return to the procedure and step in effect C. As soon as cold leg recirculation capability is confirmed D. Prior to completing any other actions in FRP-C.1 73

2011 HNP SRO NRC Written Exam

74. Given the following plant conditions:

- The plant is operating at 100% power

- A loss of offsite power occurs

- Both EDGs fail to start

- The crew entered EPP-001, Loss of AC Power To IA-SA and I B-SB Which ONE of the following statements provides the reason for this caution in EPP-001?

CAIJ11ON Critical Safety Function Status Trees should be monitored for information only.

Function Restoration Procadures shoutd NOT be implemented unless directed by this procedure.

A. During a loss of AC power the CSF status tree inputs are unreliable.

B. The steps of EOP-EPP-001 are a higher priority than any of the steps in the FRPs.

C. The FRPs were designed under the assumption that at least one safety bus was energized.

D. FRPs assume that a design basis accident has occurred and a loss of all AC power is not a design basis accident.

74

2011 HNP SRO NRC Written Exam

75. Given the following plant conditions:

- The plant is operating at 55% power

- Both Condensate and Feedwater Trains are in service

- Both Heater Drain Pumps are in service A transient occurs and the following annunciators are received:

- ALB-1 3-7-3, TWO RODS AT BOTTOM V V

- ALB-14-4-1 B, SG A STM> FW FLOW MISMATCH

- ALB-16-1-4, FW PUMP A/B 0/C TRIP GND OR BKR FAIL TO CLOSE (due to a trip of the A MFW pump)

- ALB-19-2-2A, HTR DRN PUMP A 0/C TRIP-GND Which ONE of the following identifies the annunciator that requires an entry into the EOP network?

A. TWO RODS AT BOTTOM B. SG A STM> FW FLOW MISMATCH C. FW PUMP A/B 0/C TRIP GND OR BKR FAIL TO CLOSE D. HTR DRN PUMP A 0/C TRIP-GND 75

Harris 2011-301 List of References RO Exam:

Steam Tables SRO Exam:

Steam Tables Curve F-17-1, Revision 0. (Rod Insertion Limit Curve)

AOP-001 Revision 35, page 45, attachment 4

ANSWER KEY REPORT for 2011 HNP RO NRC Written Exam Test Form: 0 Answers

1. ID  : Points Type O I 2O11NRCRO1 1.00 MCS A 2 2O11NRCRO2 1.00 MCS D 3 2O1INRCRO3 1.00 MCS A 4 2O1INRCRO4 1.00 MCS D 5 2011 NRC RO 5 1.00 MCS A 6 2O11NRCRO6 1.00 MCS D 7 2O11NRCRO7 1.00 MCS A 8 2011 NRCRO8 1.00 MCS B 9 2011 NRCRO9 1.00 MCS A 10 2O11NRCRO1O 1.00 MCS A 11 2011 NRC ROll 1.00 MCS C 12 2O1INRCRO12 1.00 MCS D 13 2O1INRCRO13 1.00 MCS A 14 2O11NRCRO14 1.00 MCS C 15 2O1INRCRO15 1.00 MCS B 16 2O11NRCRO16 1.00 MCS B 17 2O11NRCRO17 1.00 MCS B 18 2O11NRCRO18 1.00 MCS B 19 2O1INRCRO19 1.00 MCS D 20 2O11NRCRO2O 1.00 MCS B 21 2O11NRCRO21 1.00 MCS C 22 2O11NRCRO22 1.00 MCS D 23 2OI1NRCRO23 1.00 MCS D 24 2011 NRCRO 24 1.00 MCS B 25 2011 NRCRO 25 1.00 MCS C 26 2011 NRC RO 26 1.00 MCS A 27 2011 NRC RO 27 1.00 MCS C 28 2O1INRCRO28 1.00 MCS D 29 2O11NRCRO29 1.00 MCS A 30 2O11NRCRO3O 1.00 MCS D 31 2O11NRCRO31 1.00 MCS D 32 2O11NRCRO32 1.00 MCS B 33 2OI1NRCRO33 1.00 MCS C 34 2OIINRCRO34 1.00 MCS C 35 2O11NRCRO35 1.00 MCS B 36 2011 NRCRO 36 1.00 MCS A 37 2O11NRCRO37 1.00 MCS C 38 2OI1NRCRO38 1.00 MCS A 39 2O11NRCRO39 1.00 MCS D 40 2O11NRCRO4O 1.00 MCS A 41 2O11NRCRO41 1.00 MCS D 42 2O11NRCRO42 1.00 MCS D 43 2011 NRCRO 43 1.00 MCS D 44 2O11NRCRO44 1.00 MCS A 45 2011 NRCRO 45 1.00 MCS D 46 2011 NRCRO 46 1.00 MCS C 47 2OI1NRCRO47 1.00 MCS B Tuesday, Juy 19, 2011 5:01:53 PM 1

ANSWER KEY REPORT for 2O1 I HNP RO NR Written exam Test Form: 0 A

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1. ID Points Type 0 48 2011 NRCRO 48 1.00 MCS D 49 2011 NRC RO 49 1.00 MCS A 50 2011 NRCRO 50 1.00 MCS A 51 2011NRCRO51 1.00 MCS D 52 2O1INRCRO52 1.00 MCS D 53 2011 NRCRO 53 1.00 MCS C 54 2011 NRCRO 54 1.00 MCS D 55 2011 NRCRO 55 1.00 MCS C 56 2011 NRC RO 56 1.00 MCS A 57 2O11NRCRO57 1.00 MCS C 58 2O11NRCROS8 1.00 MCS A 59 2011 NRCRO 59 1.00 MCS D 60 2O11NRCRO6O 1.00 MCS A.

61 2011 NRCRO 61 1.00 MCS A 62 2011NRCR062 1.00 MCS B 63 2011 NRC RO 63 1.00 MCS A 64 2011 NRCRO 64 1.00 MCS D 65 2OI1NRCRO65 1.00 MCS C 66 2011 NRC RO 66 1.00 MCS A 67 2011 NRC RO 67 1.00 MCS C 68 2O11NRCRO68 1.00 MCS B 69 2011 NRC RO 69 1.00 MCS B 70 2011 NRCRO 70 1.00 MCS D 71 2O11NRCRO71 1.00 MCS C 72 2011 NRC RO 72 1.00 MCS B 73 2011 NRC RO 73 1.00 MCS D 74 2011 NRC RO 74 1.00 MCS C 75 2011 NRCRO 75 1.00 MCS A SECTION 1 (75 items) 75.00 Tuesday, July 19, 2011 5:01:53 PM 2