ML120690573

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Initial Exam 2012-301 Final RO Written Exam
ML120690573
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 03/06/2012
From:
NRC/RGN-II/DRMA/IRB
To:
Kenneth Shaaf
References
2012-301
Download: ML120690573 (80)


Text

ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission 2012 HNP NRC Site-Specific RO Written Examination Applicant Information Name:

Date: Facility/Unit: Harris Nuclear Plant Region: I [] lllll El lv El ReactorType:W CEE] BWLI GEE]

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 wDl 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

2012 HNP NRC RO

1. Given the following plant conditions:

- The plant has just tripped following 100 days of operation at 100% power Which ONE of the following decribes the actions necessary to maintain a constant value of Shutdown Margin following the trip?

A. Dilute for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, then borate for the next 70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br /> B. Borate for 1 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, then dilute for the next -70 hours C. Dilute for 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />, then borate for the next 55 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> D. Borate for 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />, then dilute for the next 55 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> Monday, February 20, 2012 11:13:28AM 1 Rev. FINAL

2012 HNP NRC RO

2. Given the following plant conditions:

- ISI-3, BIT Outlet Valve, is under clearance for MOV maintenance.

- A Reactor Trip and Safety Injection occurred.

- All RCPs are running.

- RCS pressure is 1370 psig and stable.

- Slflowis 150 GPM.

- Containment pressure is 4.5 psig and slowly rising.

- SG pressures are 1020 psig and stable.

- The QAC reports lSl-4, BIT Outlet Valve, indicates dual position (red/green light lit).

Which ONE of the following completes the statement below upon transition from PATH-I?

RCP5 (1) be tripped AND SGs are (2) for subsequent RCS heat removal.

A. (I) should NOT (2) required B. (1) should NOT (2) NOT required C. (1) should (2) required D. (l)should (2) NOT required Monday, February 20, 2012 11:13:28AM Rev. FINAL

2012 HNP NRC RO

3. Given the following plant conditions:

- The plant is operating at 45% power

- RCP C #1 seal leakoff is 9 gpm and rising Which ONE of the following describes the sequence of actions in accordance with AOP-018, Reactor Coolant Pump Abnormal Conditions?

A. Trip the Reactor, secure RCP C and then implement PATH-i B. Trip the Reactor, implement PATH-i, and then secure RCP C as time permits C. Secure RCP C, shut 1CS-437, RCP C #1 Seal Water Return and then initiate a plant shutdown in accordance with GP-006, Normal Plant Shutdown from Power Operation to Hot Standby D. Initiate a plant shutdown in accordance with GP-006, Normal Plant Shutdown from Power Operation to Hot Standby, secure RCP C and then shut 1CS-437, RCP C

  1. 1 Seal Water Return Monday, February 20, 2012 11:13:28AM 3 Rev. FINAL

2012 HNP NRC RO

4. Given the following plant conditions:

- The plant is in Mode 5

- RHR A and B trains are in service for Shutdown Cooling

- The OAC reports Fl-605B1, RHR Hx B Header Flow AND PDI-5450B, RHR Pump B Duff Pressures are oscillating Which ONE of the following completes the statement below for actions required to be taken in accordance with AOP-020, Loss of RCS Inventory or Residual Heat Removal while Shutdown?

Stop (1) AND shut (2)

A. (1) RHR Pump B ONLY (2) 1RH-39, RCS Loop C to RHR Pump B B. (1) BOTH RHR Pumps (2) 1RH-39, RCS Loop C to RHR Pump B C. (1) RHR Pump B ONLY (2) 1 RH-i, RCS Loop A to RHR Pump A AND I RH-39, RCS Loop C to RHR Pump B D. (1) BOTH RHR Pumps (2) 1 RH-i, RCS Loop A to RHR Pump A AND I RH-39, RCS Loop C to RHR Pump B Monday, February 20, 2012 11:13:28AM 4 Rev. FINAL

2012 HNP NRC RO

5. Given the following plant conditions:

- The plant is operating at 100% power

- CCW Pump A in service and CCW pump B in standby

- A leak occurs in the CCW system causing CCW Surge Tank level to decrease The following CCW surge tank level indications exist as leakage from the system continues:

Ll-670A1 SA LC-676A1 SB Time 0933 39% 41%

0935 37% 38%

1003 3% 14%

1005 0% 3%

In accordance with AOP-014, Loss of Component Cooling Water, what is the EARLIEST time the operating crew is required to place and hold the control switches to STOP for affected CCW pumps?

A. 0933 B. 0935 C. 1003 D. 1005 5 Rev. FINAL Monday, February 20, 2012 11:13:28 AM

2012 HNP NRC RO

6. Given the following plant conditions:

- The plant is operating at 100% power

- The OAC reports to the CRS that PRZ pressure is 2260 psig and slowly rising

- The crew enters AOP-019, Malfunction of RCS Pressure Control

- The OAC identifies that the PRZ group A backup heaters are ON and attempts to secure the heater group from the MCB have failed In accordance with AOP-019, (1) what action should be taken to control PRZ pressure AND (2) what is the expected response of the Master Pressure Controller output after this action is taken?

A. (1) an operator should be dispatched to locally open the malfunctioning heater breaker (2) Master Pressure Controller output increases B. (1) take local control of the PRZ heaters at the Auxiliary Control Panel (ACP) and secure the A backup heaters from the ACP (2) Master Pressure Controller output increases C. (1) an operator should be dispatched to locally open the malfunctioning heater breaker (2) Master Pressure Controller output decreases D. (1) take local control of the PRZ heaters at the Auxiliary Control Panel (ACP) and secure the A backup heaters from the ACP (2) Master Pressure Controller output decreases Monday, February 20, 2012 11:13:28AM 6 Rev. FINAL

2012 HNP NRC RO

7. Given the foflowing plant conditions:

- The plant was operating at 100% power

- A Steam Generator Tube Rupture occurred on the SG A

- Offsite power was lost

- The crew implemented PATH-i and transitioned to PATH-2 then transitioned to EPP-017, Post-SGTR Cooldown Using Backfill

- A RCS cooldown on natural circ is now required In accordance with EPP-01 7, which ONE of the following is the preferred order of dumping steam from the intact SGs to accomplish the cooldown?

1) SG PORV controlled at MOB
2) Locally operate SG PORVs
3) Condenser steam dump
4) TDAFW pump A. 1,2,3 B. 3,1,2 C. 1,2,4 D. 3,2,4 Monday, February 20, 2012 11:13:28AM 7 Rev. FINAL

2012 HNP NRC RO

8. Given the following plant conditions:

- FRP-H.1, Response to a Loss of Secondary Heat Sink, is being implemented

- RCS bleed and feed has been initiated

- Subsequently, Auxiliary Feedwater capability is restored

- All SGs are completely dry and depressurized Under these conditions, which ONE of the following describes the strategy used to re-establish Feedwater?

A. Feed ONLY one (1) SG to ensure RCS cooldown rates are established within Technical Specification limits B. Feed ONLY one (1) SG to minimize excessive thermal stresses to SG components C. Feed ALL SGs to establish subcooled conditions in the RCS as soon as possible D. Feed ALL SGs to allow termination of RCS bleed and feed as soon as possible Monday, February 20, 2012 11:13:28AM 8 Rev. FINAL

2012 HNP NRC RO

9. Given the following plant conditions:

- The plant was operating at 100%

- A loss of off-site power has occurred

- EDGA failsto start

- EDG B output breaker closes, but trips open

- EPP-001, Loss Of AC Power To 1A-SA And 1 B-SB Buses, is being implemented

- All other systems are operating as expected Which ONE of the following completes the statement below?

In accordapce with EPP-001, the RCS cooldown during natural circulation is limited to a MAXIMUM rate of (1) AND the cooldown is required to (2)

A. (1)20°F/Hr (2) minimize RCP seal leakage B. (1)50°F/Hr (2) minimize RCP seal leakage C. (1)20°F/Hr (2) control Pressurizer level D. (1)50°F/Hr (2) control Pressurizer level Monday, February 20, 2012 11:13:28AM 9 Rev. FINAL

2012 HNP NRC RO

10. Given the following plant conditions:

- The plant is operating at 100% power

- A Loss of Offsite Power occurs Which ONE of the following combinations identify the annunciators that are expected for this condition?

1) ALB-006 1-2, Charging Pumps A Trouble
2) ALB-005 8-4, CCW Pumps B Trip or Close CKT Trouble
3) ALB-004 4-5, RHR Pump A Low Duff Press
4) ALB-01 7 7-5, Aux Feedwater Pump Turbine Steam Low Press A. 1,4 B. 1,2 C. 2,3 D. 3,4 Monday, February 20, 2012 11:13:28 AM 10 Rev. FINAL

2012 HNP NRC RO

11. Given the following plant conditions:

- The plant is operating at 100% power

- PRZ Level Control is selected to position 459/460

- Instrument Bus S-li is lost

- The crew is implementing AOP-024, Loss of Uninterruptible Power Supply Which ONE of the following completes the statements below?

Letdown flow will be isolated because (1) went SHUT.

The OAC should control Charging in manual with FK-1 22.1, Charging Flow to (2) with letdown isolated.

A. (1) ICS-1, Letdown Isolation LCV-460 (2) minimize the PRZ level increase V B. (1) 1CS-1, Letdown Isolation LCV-460 (2) prevent gas binding of the CSIP C. (1) 1CS-2, Letdown isolation LCV-459 (2) minimize the PRZ level increase D. (1) ICS-2, Letdown isolation LCV-459 (2) prevent gas binding of the CSIP Monday, February 20, 2012 11:13:28AM 11 Rev. FINAL

2012 HNP NRC RO

12. Given the following plant conditions:

- The plant is in Mode 3

- MDAFW Pumps A and B are in service feeding all 3 SGs

- EDG B is under clearance for maintenance Subsequently:

- All power from 125 VDC Emergency Bus DP-1 B-SB is lost

- One minute later a Startup Transformer 1 B lockout occurs Which ONE of the following completes the statement below?

MDAFW Pump B breaker indication on the MCB is (1) AND the pump motor breaker is (2)  ?

A. (1) available (2) closed B. (1) not available (2) closed C. (1)available (2) open D. (1) not available (2) open Monday, February 20, 2012 11:13:28AM 12 Rev. FINAL

2012 HNP NRC RO

13. Given the following plant conditions:

- The plant is operating at 100% power The following MCB indications exist:

Time 1135 1138 1140 ESW Header A Pl-9101A SA, A Disch Press 88 psig 86 psig 94 psig Fl-9101A1 SA, A Hdr Flow 14550 gpm 11820 gpm 13390 gpm ESW Header B Pl-9101B SB, B Disch Press 89 psig 85 psig 81 psig Fl-9101B1 SB, BHdrFlow 15725gpm 18550gpm l3600gpm NSW Header P1-9302.1, Disch Hdr Press 82 psig 80 psig 112 psig Fl-9304, WPB SW Flow 9800 gpm 8250 gpm 11800 gpm FI-9276, Cnmt Coil Units SW Return 1840 gpm 1560 gpm 2900 gpm AOP-022, Loss of Service Water has been entered and both ESW pumps have been started.

Which ONE of the following completes the statements below?

The Service Water line rupture is located in the (1) ESW Header. In accordance with AOP-022 to isolate the ESW Header leak, the operator will be directed to place and hold (2) control switch(es) to STOP.

A. (1)A (2) the ESW Pump A B. (1)A (2) both ESW Pump A and B C. (1)B (2) the ESW Pump B D. (1)B (2) both ESW Pump A and B Monday, February 20, 2012 11:13:28AM 13 Rev. FINAL

2012 HNP NRC RO

14. Given the following plant conditions:

- The plant is operating at 100% power

- IA header pressure lowers as indicated below:

Time IA Header Pressure 0750 115 psig 0755 95 psig 0800 85 psig 0805 70 psig 0810 60 psig 0815 45psig Which ONE of the following completes the statements below?

At (1) an auto shut signal to the Main Feed Reg valves is generated. The reason these valves have a back up air supply in the form of air accumulators is to (2)

A. (1) 0800 (2) provide motive force to shut the valves B. (1) 0800 (2) provide the ability to maintain the valves open for a short period of time following loss of air C. (1) 0810 (2) provide motive force to shut the valves D. (1) 0810 (2) provide the ability to maintain the valves open for a short period of time following loss of air Monday, February 20, 2012 11:13:28AM 14 Rev. FINAL

2012 HNP NRC RO

15. Given the following plant conditions:

- The plant is operating at 100% power

- Annunciator ALB-22-5-3, Generator Voltage Balance Relay Operated ALARMS

- The voltage regulator remains in AUTO

- MW and MVAR indications are erratic Which ONE of the following actions should be taken for these conditions?

A. Null the Voltage Regulator Output Voltage with the Generator Base Adjuster. If the Base Adjuster does not work, Trip the Reactor and enter PATH-i B. Adjust the Generator Output Voltage to 22KV with the Generator Voltage Adjuster switch. If the Voltage Adjuster does not work, Trip the Reactor and enter PATH-i C. Place the Generator Voltage Regulator switch to OFF and use the Generator Voltage Adjuster switch to restore Main Generator voltage D. Operate the Generator Base Adjuster switch to null the Regulator Output Balance

  • Voltage as close to zero as possible then place the Generator Voltage Regulator in manual by positioning the control switch to TEST Monday, February 20, 2012 11:13:28AM 15 Rev. FINAL

2012 HNP NRC RO

16. Given the following plant conditions:

- A Reactor Trip and Safety Injection have occurred from 100% power

- The crew has transitioned to EPP-013, LOCA Outside Containment

- I RH-I and 1 RH-2, RCS Loop A to RHR Pump A-SA, BOTH indicate partially OPEN Which ONE of the following identifies (1) the action required to ALLOW shutting 1 RH-I and I RH-2 from the MCB AND (2) the parameter used in EPP-0I 3 to determine if this action has isolated the break?

A. (I) turn ON the control power switch on the MCB (2) PRZ level increasing B. (I) turn ON the control power switch on the MCB (2) RCS pressure increasing C. (1) CLOSE the breakers for IRH-I and 1RH-2 locally (2) PRZ level increasing D. (I) CLOSE the breakers for IRH-1 and 1RH-2 locally (2) RCS pressure increasing Monday, February 20, 2012 11:13:28AM 16 Rev. FINAL

2012 HNP NRC RO

17. Given the following plant conditions:

- The plant was operating at 100% power

- MDAFW pump A is under clearance

- A manual Reactor Trip was initiated due to a loss of both MFPs

- The TDAFW pump tripped after starting

- MDAFW flow control valves are full open

- SG NR levels are 50% and lowering

- Containment pressure is 3.5 psig Which ONE of the following would be the FIRST set of conditions that would require entry into FRP-H. 1, Response to Loss of Secondary Heat Sink?

All SG NR levels are (1) AND total AFW flow is (2)

A. (1)39%

(2) 220 KPPH B. (1)39%

(2) 200 KPPH C. (1)24%

(2) 220 KPPH D. (1)24%

(2) 200 KPPH Monday, February 20, 2012 11:13:28AM 17 Rev. FINAL

2012 HNP NRC RO

18. Which ONE of the following describes (1) the reason AND (2) the requirements for depressurizing the RCS in accordance with EPP-012, Loss of Emergency Coolant Recirculation?

A. (1) To minimize RCS break flow (2) Depressurize the RCS to achieve RCS subcooling between 10°F and 20°F

[40°F and 50°F]

B. (1) To increase CSIP injection flow rate (2) Depressurize the RCS to achieve RCS subcooling between 10°F and 20°F

[40°F and 50°F]

  • C. (1) To minimize RCS break flow (2) Depressurize the RCS to maintain RCS subcooling just above 60°F [90°F]

D. (1) To increase CSIP injection flow rate (2) Depressurize the RCS to maintain RCS subcooling just above 60°F [90°F]

Monday, February 20, 2012 11:13:28AM 18 Rev. FINAL

2012 HNP NRC RO

19. Given the following plant conditions:

Time = 1200

- Reactor Power is 89% and stable

- Tavg Tref deviation is 0°F and stable

- PRZ level is 55% and stable

- Control Bank D DRPI indicates 198 steps Time =1202

- Reactor Power is approximately 90% and rising (no load change is in progress)

- Tavg Tref deviation is approximately +2°F and rising PRZ level 56% and rising

- PRZ spray valves have throttled open

- Control Bank D DRPI indicates 204 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 in accordance with AOP-001, Malfunction of Rod Control and Indication System?

A. (1) Selected first stage pressure channel high failure (2) Check that less than 2 control rods are dropped B. (1) Selected first stage pressure channel high failure (2) Place the Rod Bank Selector Switch to MAN C. (1) Continuous spurious control bank withdrawal (2) Check that less than 2 control rods are dropped D. (1) Continuous spurious control bank withdrawal (2) Place the Rod Bank Selector Switch to MAN Monday, February 20, 2012 11:13:28AM 19 Rev. FINAL

2012 HNP NRC RO

20. Given the following plant conditions:

- An irradiated Fuel Assembly was being withdrawn from the core when it was determined that the assembly was damaged

- Containment Area Radiation is rising but monitors are NOT in alarm status

- AOP-013, Fuel Handling Accident, has been entered Which ONE of the following describes the FIRST action required in accordance with AOP-01 3?

A. Evacuate Containment B. Initiate Containment Closure C. Perform radiological surveys of Containment D. Place the affected fuel assembly in an unobstructed opening in the Reactor Vessel Monday, February 20, 2012 11:13:28AM 20 Rev. FINAL

2OI2HNPNRCRO

21. Given the following plant conditions:

- The plant is operating at 100% power

- At 0800 a crack occurs on one SG B tube, resulting in a 83 gpd tube leak

- The crew enters AOP-016, Excessive Primary Plant Leakage Which ONE of the following completes statement below?

In accordance with AOP-016, Reactor power is required to be reduced to 50% within (1) hour(s) AND the impact of reducing power is that the RCS to SG leak rate is (2)

A. (1)one (2) lower B. (1)one (2) higher C. (1)three (2) lower D. (1)three (2) higher Monday, February 20, 2012 11:13:28AM 21 Rev. FINAL

2012 HNP NRC RO

22. Given the following plant conditions:

- The plant is operating at 45% power

- Condenser vacuum is degrading as indicated below:

Time Zone I Pressure Zone 2 Pressure 0900 4.4 Hg absolute 4.8 Hg absolute 0905 4.8 Hg absolute 5.3 Hg absolute 0910 5.4 Hg absolute 5.9 Hg absolute 0915 7.2 Hg absolute 7.8 Hg absolute 0920 7.6 Hg absolute 8.4 Hg absolute What is the EARLIEST time that an automatic Turbine/Reactor Trip will be generated?

A. 0905 B. 0910 C. 0915 D. 0920 Monday, February 20, 2012 11:13:28 AM 22 Rev. FINAL

2012 HNP NRC RO

23. Given the following plant conditions:

- The plant was operating at 100% power

- AOP-004, Remote Shutdown, has been entered due to a fire in the MCB

- Transfer to the Auxiliary Control Panel (ACP) is complete Using ACP indicators, which ONEof the following identifies that natural circulation is occurring?

1) RCS HL indicators: stable
2) SG pressure indicators: stable
3) RCS HL indicators: at saturation for SG pressure
4) RCS CL indicators: at saturation for SG pressure A. land4ONLY B. 2and3ONLY C. 1,2,and3ONLY D. 1,2,and4ONLY Monday, February 20, 2012 11:13:28AM 23 Rev. FINAL

2012 HNP NRC RO

24. Given the following plant conditions:

- The plant is operating at 100% power

- Chemistry reports RCS activity is increasing, and the latest sample is 1.4 microcuries per gram DOSE EQUIVALENT 1-131

- ALB-026 2-1, Gross Failed Fuel Detector Trouble is received Which ONE of the following identifies (1) the source of radiation detected by the Gross Failed Fuel Detector is AND (2) what action will be directed by AOP-032, High RCS Activity, to reduce RCS activity levels?

A. (1) neutron radiation from delayed neutrons (2) place the cation demineralizer in service B. (1) neutron radiation from delayed neutrons (2) place the second mixed bed demineralizer in service C. (1) gamma radiation from decay of fission products (2) place cation demineralizer in service D. (1) gamma radiation from decay of fission products (2) place the second mixed bed demineralizer in service Monday, February 20, 2012 11:13:28AM 24 Rev. FINAL

2012 HNP NRC RD

25. Given the following plant conditions:

- The plant was operating at 100% power

- The plant has experienced a LOCA

- An automatic Reactor Trip and SI have occurred

- The crew has transitioned from PATH-i to EPP-009, Post LOCA Cooldown and Depressurization.

With the above conditions, which ONE of the following describes how voiding can be identified in the RCS?

A. Rapidly decreasing RCS subcooling B. Decreasing safety injection flow C. Increasing RCS pressure D. Rapidly increasing Pressurizer level Monday, February 20, 2012 11:13:28 AM 25 Rev. FINAL

2012 HNP NRC RO

26. Given the following plant conditions:

- The crew is implementing EOP-FRP-P.l, Response to Imminent Pressurized Thermal Shock

- RCS subcooling does not support SI termination but it does support starting an RCP Which ONE of the following describes why it is desirable to re-start an RCP under these conditions?

A. Promote mixing of the Safety Injection water and RCS B. Supply additional heat input into the RCS C. Establish PRZ Spray control D. Promote heat transfer from the SGs to the RCS Monday, February 20, 2012 11:13:28AM 26 Rev. FINAL

2012 HNP NRC RO

27. Given the following plant conditions:

- The plant was operating at beginning of cycle when a large break LOCA occurred

- LT-7162B, Containment Wide Range Level, has increased to 207 inches and continues to rise

- The crew is implementing FRP-J.2, Response to Containment Flooding Which ONE of the following completes the below statement describing why the Containment sump is sampled at this point?

The crew must determine if...

A. the Containment Spray Additive Tank should be isolated.

B. the water is suitable for transfer to tanks outside Containment.

C. Emergency Service Water to Containment should be isolated.

D. the Containment sump contains enough boron to prevent a post-LOCA reactivity transient which could result in a loss of subcriticality.

Monday, February 20, 2012 11:13:28AM 27 Rev. FINAL

2012 HNP NRC RO

28. Given the following plant conditions:

- The plant is operating at 15% power

- Steam Dumps are being transferred to Tavg control

- ALB-009-5-1, Pressurizer High-Low Press, ALARMS Two minutes later, RCS Pressure is 2150 psig and is decreasing.

- The OAC attempts to shut I RC-1 03, PCV-444D: PRZ Spray Loop B, but it does not respond Which ONE of the following describes the actions required for this condition in accordance with AOP-019, Malfunction of RCS Pressure Control?

A. Trip the Reactor then secure ONLY the RCP B to stop the pressure decrease B. Trip the Reactor then secure BOTH the RCP A and B to stop the pressure decrease C. Stop the RCP B and if RCS pressure continues to decreases to < 2000 psig then Trip the Reactor D. Stop BOTH the RCP A and B and if RCS pressure continues to decreases to

<2000 psig then Trip the Reactor Monday, February 20, 2012 11:13:28AM 28 Rev. FINAL

2012 HNP NRC RO

29. Given the following plant conditions:

- The plant is operating at 100% power

- CSIP A has been out of service for maintenance for the past 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

- At 0800, the CSIP B trips due to a motor fault

- CSIP C is not available Based on the conditions above, in accordance with Technical Specifications, the crew must initiate action to shutdown the plant (1) , with the plant reaching Mode 3 no later than (2)

A. (1)byO900 (2) 1400 B. (1)byO900 (2) 1500 C. (1)immediately (2) 1400 D. (1) immediately (2) 1500 Monday, February 20, 2012 11:13:28AM 29 Rev. FINAL

2012 HNP NRC RO

30. Given the following plant conditions:

- PATH-2 is being implemented

- The RCS has been depressurized, and SI flow is terminated

- After normal miniflow is realigned, PATH-2 directs the crew to transfer CSIP suction to the VCT (Level is 38%)

If the RO takes the RWST to CSIP valves to shut prior to opening the VCT outlets, what will be the impact?

The RWST supply valves will A. shut causing a loss of suction to the running CSIP.

B. not shut since the VCT outlets are closed.

C. shut once the VCT outlets automatically open.

D. not shut since the alternate miniflow isolations are open.

Monday, February 20, 2012 11:13:28AM 30 Rev. FINAL

2012 HNP NRC RO

31. Given the following plant conditions:

- The plant was operating at 100% power Time 0515 LOCA occurs and the operators enter PATH-i 0525 RHR Pump B tripped on overcurrent 0550 Cold Leg Recirc is established in accordance with EPP-01 0, Transfer To Cold Leg Recirculation 0555 CSIP B was secured due to a gear drive failure and resultant oil fire 0600 RHR Pump A tripped on overcurrent In accordance with EPP-012, Loss Of Emergency Coolant Recirculation, which ONE of the following (1) represents the time used to calculate minimum SI flow required AND (2) the reason for calculating this minimum SI Flow?

A. (1)0515 (2) to ensure the existence of an adequate vessel inventory such that core cooling is ensured.

B. (1)0515 (2) to match decay heat in order to further decrease SI pump flow and delay RWST depletion.

C. (1)0550 (2) to ensure the existence of an adequate vessel inventory such that core cooling is ensured.

D. (1)0550 (2) to match decay heat in order to further decrease SI pump flow and delay RWST depletion.

Monday, February 20, 2012 11:13:28AM 31 Rev. FINAL

2012 HNP NRC RD

32. Given the following plant conditions:

- RHR A train is in service for Shutdown Cooling

- The Instrument Air supply line to I RH-30, RHR Heat XCHG A Out Flow Control Valve, becomes severed and is completely detached

- 1 RH-30, has a demand of 50%

Which ONE of the following describes the effect on the RHR system?

A. RHR pump A will reach runout conditions.

B. RHR pump A will operate at shutoff head.

C. RHR Heat Exchanger A outlet temperature rises.

D. RHR Heat Exchanger A outlet temperature lowers.

Monday, February 20, 2012 11:13:29AM 32 Rev. FINAL

2012 HNP NRC RO

33. Given the following plant conditions:

-. EPP-009, Post LOCA Cooldown and Depressurization, is in progress

- RCS temperature is 500°F with a cooldown rate of 75°F per hour in progress

- RCS pressure is 1600 psig and lowering

- Subcooling is 50°F and increasing

- Containment pressure is 4 psig

- One RCP is running

- The crew secures one CSIP and aligns normal charging flow Which ONE of the following describes (1) the reason RCS subcooling LOWERS when the crew stops one CSIP AND (2) the HIGHEST value of RCS subcooling that requires action to realign the CSIP flow through the BIT?

A. (1) RCS temperature rise (2) 39°F B. (1) RCS temperature rise (2)9°F C. (1) RCS pressure reduction (2) 39°F D. (1) RCS pressure reduction (2) 9°F Monday, February 20, 2012 11:13:29AM 33 Rev. FINAL

2012 HNP NRC RO

34. Given the following plant conditions:

- A Large Break LOCA occurred 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago

- EPP-010, Transfer to Cold Leg Recirculation has been completed

- CSIP B has just tripped Which ONE of the following completes the statement below?

After CSIP B trips the flow rate through Fl-940, Alternate Header Flow, will (1) and flow rate through Fl-943, Normal Header Flow, will (2)

A. (1) remain at zero flow (2) decrease to approximately half the previous value B. (1) decrease to approximately half the previous value (2) remain at zero flow C. (1) decrease to zero (2) remain constant D. (1) remain constant (2) decrease to zero Monday, February 20, 2012 11:13:29 AM 34 Rev. FINAL

2012 HNP NRC RO

35. Given the following plant conditions:

- The plant is operating at 100% power

- A Pressurizer PORV has a slow leak

- The respective PORV isOlation valve cannot be closed

- ALB-009-8-1, Pressurizer Relief Tank High-Low Level Press or Temp, is in ALARM PRT Level is 73%

PRT Temperature is 128°F PRT Pressure is 6.3 psig Which ONE of the following parameters (pressure I temperature) (1) is causing the alarm, AND (2) what action is required to be performed in accordance with ALB-009-8-1?

A. (1) Pressure (2) Vent the PRT as necessary to control pressure B. (1) Pressure (2) Drain the PRT as necessary to control pressure while maintaining level within the normal band C. (1) Temperature (2) Recirculate the PRT contents through the RCDT Heat Exchanger to lower temperature D. (1) Temperature (2) Drain PRT to the low end of the normal band and then refill with demin water to lower temperature Monday, February 20, 2012 11:13:29AM 35 Rev. FINAL

2012 HNP NRC RD

36. Given the following plant conditions:

- The plant is operating at 100% power Annunciator ALB 005-6-1, CCW Surge Tank High-Low Level is in ALARM

- CCW Surge Tank Level Ll-670A.1 (Train A) reads 60%

- CCW Surge Tank Level Ll-676A.1 (Train B) reads 35%

- CCW Pump A Discharge Temp Tl-671 reads 95°F

- CCW Header A Pressure P1-649 SA reads 96 psig

- CCW Header B Pressure P1-650 SB reads 48 psig

- CCW Hx A Outlet Header Flow Fl-652.1 reads 11,500 gpm Which ONE of the following actions would automatically occur as a result of these indications?

A. COW Pump B will start B. CCW Holdup Tank Transfer Pump will trip C. 1 DW-1 5, CCW Surge Tank Make Up, will open D. 100-252, CCW Return Isolation from the RCP Thermal Barrier, will shut Monday, February 20, 2012 11:13:29 AM 36 Rev. FINAL

2012 HNP NRC RO

37. Given the following plant conditions:

- The plant was operating at 100% power

- A Large Break LOCA has occurred

- The crew is implementing PATH-i Which ONE of the following completes the statement below?

1 CC-i 47, CCW From RHR Heat Exchanger A-SA will be opened (1) AND 1 CC-99, CCW Heat Exchanger A To Non-Essential Supply and 1CC-i 287 CCW Non-Essential Return To Header A will be shut (2)

A. (1) manually (2) automatically B. (1) automatically (2) manually C. (1) manually (2) manually D. (1) automatically (2) automatically Monday, February 20, 2012 11:13:29 AM 37 Rev. FINAL

2O12HNPNRCRO

38. Given the following plant conditions:

- The plant is in Mode 3 at normal operating pressure

- PZR Pressure Control is in AUTO

- PZR Pressure Channel indications are:

- P1-444: 2050 psig

- P1-445: 2500 psig

- P1-455: 2050 psig

- P1-456: 1950 psig

- P1-457: 2050 psig Assuming NO operator actions, which ONE of the following describes the expected conditions of the PZR PORVs and spray valves?

A. PORV 1 RC-1 14 (PCV-444B) CLOSED -

PORVs I RC-l 16 (PCV-445B) and I RC-1 18 (PCV-445A) OPEN Spray Valves PCV-444C and PCV-444D OPEN -

B. PORV 1 RC-1 14 (PCV-444B) OPEN -

PORVs I RC-1 16 (PCV-445B) and I RC-1 18 (PCV-445A) CLOSED Spray Valves PCV-444C and PCV-444D - OPEN C. PORV 1 RC-I 14 (PCV-444B) - CLOSED PORV I RC-l 16 (PCV-445B) and I RC-1 18 (PCV-445A) OPEN Spray Valves PCV-444C and PCV-444D - CLOSED D. PORV I RC-1 14 (PCV-444B) - OPEN PORVs I RC-1 16 (PCV-445B) and I RC-1 18 (PCV-445A) CLOSED Spray Valves PCV-444C and PCV-444D CLOSED-Monday, February 20, 2012 11:13:29AM 38 Rev. FINAL

2012 HNP NRC RO

39. Given the following plant conditions:

- The plant was operating at 100% power

- Offsite power was lost resulting in a Reactor Trip Which ONE of the following operator actions or plant conditions are required to CLOSE the Reactor Trip breakers?

1) Reset the Main Turbine Trip
2) RCP Bus voltage must be restored to greater than 5l48Volts
3) ALL steam generator levels must be restored to greater than 25%
4) Reset the PR High flux rate trips A. 1,2 B. 1,3 C. 2,4 D. 3,4 Monday, February 20, 2012 11:1 3:29 AM 39 Rev. FINAL

2012 HNP NRC RO

40. Given the following plant conditions:

- The plant is operating at 100% power

- Containment Pressure Channel IV pressure indication was oscillating and has been removed from service in accordance with OWP-ESF, Engineered Safety Feature Actuation.

Which ONE of the following identifies the logic from the remaining channels for HI-i and Hl-3 Containment Pressure actuations AFTER Channel IV is REMOVED from service?

HI-i SI Actuation Hl-3 CNMT Spray Actuation A. 1/2 2/3 B. 1/2 1/3 C. 2/3 2/3 D. 2/3 1/3 Monday, February 20, 2012 11:13:29AM 40 Rev. FINAL

2012HNPNRCRO

41. Given the following plant conditions:

- The plant was operating at 100% power

- A Small Break LOCA has occurred

- Containment pressure is 3.8 psig and increasing

- Containment temperature is 137°F and increasing Which ONE of the following completes the statement below?

Containment Fan Coolers will be running in (1) speed with the post-accident dampers (2)

A. (1)SLOW (2) OPEN B. (1)SLOW (2) SHUT C. (1)HIGH (2) SHUT D. (1) HIGH (2) OPEN Monday, February 20, 2012 11:13:29AM 41 Rev. FINAL

2012 HNP NRC RO

42. Given the following plant conditions:

- The plant was operating at 100% power

- MCC-1A22-SA is under clearance for breaker inspection

- RHR Pump A is under clearance for breaker repairs

- A LOCA has occurred

- Containment pressure is 14 psig

- RWST level is 34% and decreasing

- The crew is implementing PATH-i when power is lost to the 480V AC Emergency Bus iB3-SB

- The CRS has transitioned to EPP-012, Loss of Emergency Coolant Recirculation Given the current plant conditions, (1) spray pump(s) is/are running AND in accordance with step 7 of EPP-0i 2, (2) is the required number of Containment Spray Pumps.

Reference Provided (1) (2)

A. two two B. two one C. one two D. one one Monday, February 20, 2012 11:13:29AM 42 Rev. FINAL

2012 HNP NRC RD

43. Given the following plant conditions:

- The plant was operating at 100% power A Main Steam line break has occurred inside Containment

- SPDS is displaying RED on the INTEGRITY Critical Safety Function (CSF)

Which ONE of the following completes the statement below?

The parameters used by SPDS to determine the INTEGRITY CSF are the (1)

Tcold AND the (2) RCS Pressure.

A. (1) lowest (2) lowest B. (1) highest (2) highest C. (1) lowest (2) highest D. (1) highest (2) lowest Monday, February 20, 2012 11:13:29AM 43 Rev. FINAL

2012 HNP NRC RO

44. Given the following plant conditions:

- The plant is operating at 85% power

- A Loss of Main Feedwater Pump B occurs

- The crew enters AOP-01 0, Feedwater Malfunctions Which ONE of the following describes (1)the plant response AND (2) the action required in accordance with AOP-010?

A. (1) Automatic turbine runback is initiated (2) Isolate Steam Generator Blowdown B. (1) Automatic turbine runback is initiated (2) Trip the Reactor and go to PATH-I C. (1) Automatic turbine runback is NOT initiated (2) Isolate Steam Generator Blowdown D. (1) Automatic turbine runback is NOT initiated (2) Trip the Reactor and go to PATH-I Monday, February 20, 2012 11:13:29AM 44 Rev. FINAL

2012 HNP NRC RO

45. Given the following plant conditions:

- The plant is operating at 100% power

- Annunciator ALB-014-7-4, SG A, B, C Backleakage High Temp, has alarmed and has been verified as valid by local pyrometer readings indicating > 212°F Under these conditions why would establishing AFW flow to the Steam Generators be an undesirable action?

Rapid introduction of Auxiliary feed flow could result in.

A. AFW Pump run out conditions.

B. thermal binding of AFW system valves.

C. accelerated water induced corrosion of AFW piping.

D. water hammer in AFW piping.

Monday, February 20, 2012 11:13:29AM 45 Rev. FINAL

2012 HNP NRC RO

46. Given the following plant conditions:

- The plant is operating at 100% power

- Loss of Instrument Bus I DP-IA-S1 has occurred

- The crew is implementing AOP-024, Loss of Uninterruptible Power Supply

- Recovery actions are in progress in accordance with OP-i 56.02, AC Electrical Distribution

- The crew has de-energized the associated Process Instrumentation Cabinet (PlC) in preparation for energizing Instrument Bus 1 DP-IA-S1

- The crew is evaluating bistable status prior to energizing the bus Which ONE of the following describes the reason for checking bistable status prior to energizing the instrument bus and PlC?

A. A Reactor Trip may occur when the PlC is re-energized if another bistable for the same parameter is already tripped.

B. An ESF actuation may occur when the PlC is re-energized because the energize to actuate bistables may experience a momentary trip.

C. To ensure that each parameter for process or protection goes to its required state when the bus is re-energized.

D. To ensure all bistable lights are out, which indicates the PlC normal and alternate supply breakers are open.

Monday, February 20, 2012 11:13:29 AM 46 Rev. FINAL

2012 HNP NRC RD

47. Given the following plant conditions:

- The plant is operating at 50% power

- Aux Bus 1 D deenergizes and is locked out Which ONE of the following loads will be energized following this event?

(Assume no operator action)

A. Heater Drain Pump 1A B. Containment fan coil Unit AH-37 1A C. Service water booster Pump 1A-SA D. Pressurizer backup heater Group A Monday, February 20, 2012 11:13:29 AM 47 Rev. FINAL

2012 HNP NRC RO

48. Given the following plant conditions:

- The plant is operating at 100% power

- DP-IA-SA is being powered by the 1A-SA Battery Charger with the I B-SA Battery Charger in standby The following occurs:

- 1A-SA Battery Charger trips

- ALB-015-4-4, 125 VDC EMER Bus A Trouble, ALARMS Which ONE of the following (1) would be a cause of the Battery Charger trip AND (2) what is currently powering DP-IA-SA?

A. (1) Low DC voltage (2) 1 A-SA Battery B. (1) Low DC voltage (2) 1 B-SA Battery Charger C. (I) High DC voltage (2) 1A-SA Battery D. (1) High DC voltage (2) 1 B-SA Battery Charger Monday, February 20, 2012 11:13:29 AM 48 Rev. FINAL

2012 HNP NRC RO

49. Given the following plant conditions:

- OST-1823, 1A-SA Emergency Diesel Generator Operability Test 18 Month Interval, is being performed

- EDG A is running carrying Bus 1A-SA in lsochronous mode

- ESW A Pump trips

- The crew enters AOP-022, Loss Of Service Water, and ISW-39, Normal SW Supply to Header A, will not OPEN Which ONE of the following completes the statements below?

In accordance with AOP-022, the EDG A (1) switch must be used to secure the Diesel AND when the control switch is released the Diesel will (2)

A. (1) EMERGENCY STOP (2) Automatically restart due to undervoltage (86UV)

B. (1) EMERGENCY STOP (2) not restart until the EDG trip signals are reset C. (1) START/STOP (2) Automatically restart due to undervoltage (86UV)

D. (1) START/STOP (2) not restart until the EDG trip signals are reset Monday, February 20, 2012 11:13:29AM 49 Rev. FINAL

2012 HNP NRC RD

50. Given the following plant conditions:

- The plant is operating at 100% power Which ONE of the following will DIRECTLY initiate an emergency start of the A Emergency Diesel Generator?

A. BKR 1 05-SA, Emergency Bus A-SA to Aux Bus D Tie, opening B. 86UV undervoltage lockout on Aux Bus D activating C. BKR 101, SUT XFMR A to Aux Bus D, opening concurrent with a generator lockout D. Safeguards Sequencer A starting Monday, February 20, 2012 11:13:29AM 50 Rev. FINAL

2012 HNP NRC RO

51. Given the following plant conditions:

- The plant is operating at 100% power

- Annunciator ALB-010-3-4, WPB Effluent Rad Monitor Trouble has alarmed

- RM-11 indicates REM*1WV3546, WPB Stack 5 PIG Monitor is in HIGH alarm Which ONE of the following valves will automatically shut?

A. 3LHS-296, Treated LHS Tk Disch Isol Valve B. 3WG-229, WG Decay Tanks E & F to Plant Vent Vlv C. 3FD-421, WMT Disch lsol Vlv D. 3SWT.-149, Sample Tk Environmental Disch Isol Vlv Monday, February 20, 2012 11:13:29AM 51 Rev. FINAL

2012 HNP NRC RO

52. Given the following plant conditions:

- The plant is operating at 100% power

- An overcurrent fault causes 1 B35-SB to be deenergized How will the supply and return cross-tie valves between NSW and ESW be configured following an automatic start of the ESW pump B?

A. BOTH 1 SW-40, Normal SW Supply to Header B, AND 1 SW-274, Header B Return to Normal Header, will shut.

B. NEITHER ISW-40, Normal SW Supply to Header B, NOR 1SW-274, Header B Return to Normal Header, will shut.

C. I SW-40, Normal SW Supply to Header B, will shut; 1 SW-274, Header B Return to Normal Header, will NOT shut.

D. I SW-40, Normal SW Supply to Header B, will NOT shut; 1 SW-274, Header B Return to Normal Header, will shut.

Monday, February 20, 2012 11:13:29AM 52 Rev. FINAL

2012 HNP NRC RO

53. Given the following plant conditions:

- The plant is operating at 100% power

- Annunciator ALB-002-8-1, Instrument Air Low Pressure, has alarmed

- Air header pressure is lowering as indicated on the MCB meters Which ONE of the following is an expected plant response for this situation?

A. 1 SA-506, Service Air Header Isolation Valve, automatically shuts at 90 psig B. The RCS letdown system automatically isolates at 85 psig C. The Main Feedwater Reg valves automatically shut at 75 psig D. The Main Feedwater Isolation valves automatically isolate at 60 psig Monday, February 20, 2012 11:13:29AM 53 Rev. FINAL

2012 HNP NRC RO

54. Given the following plant conditions:

- The plant is operating at 100% power

- Compressor B is running in Lead

- Compressor A is the Lag unit

- Compressor C is the Standby unit

- A service air pipe ruptures resulting in lowering Instrument Air header pressure Which ONE of the following statements describes the response of the Instrument Air System following the reduction in header pressure?

A. At 95 psig Compressor A will autostart from its internal pressure switch, run for 15 minutes, and if unloaded, will shutdown.

B. At 96 psig Compressor A receives an autostart signal from the CAS Control Panel Sequencer.

C. At 98 psig the CAS Control Panel Sequencer will shift to the A compressor running as Lead, with B as Lag and the C in Standby.

D. At 101 psig system air header pressure Compressor C will autostart.

Monday, February 20, 2012 11:13:29AM 54 Rev. FINAL

2012 HNP NRC RO

55. Which ONE of the following components forces air within Containment between the Reactor Vessel and the concrete wall which surrounds the Reactor Vessel?

A. Reactor Support Cooling Fans, S-4 A-SA B. Containment Fan CoN Units, AH-2 A-SA C. Primary Shield Cooling Fans, S-2 A-SA D. Containment Fan Coolers, AH-37 IA Monday, February 20, 2012 11:13:29AM 55 Rev. FINAL

2012 HNP NRC RO

56. Given the following plant conditions:

- The plant was operating at 100% power

- A Large Break LOCA occurred one hour ago

- Only one Train of ECCS equipment is available Under these conditions, in accordance with the WOG Mitigating Core Damage Assessment, which ONE of the following is the PRIMARY reason Source Range count rate may indicate HIGHER than expected?

A. The Source Range detectors are not accurate indicators under adverse Containment conditions B. Attenuation of neutrons in the downcomer has been reduced by voiding C. Attenuation of neutrons in the central portions of the core has been reduced by voiding D. RHR suction has swapped to the Containment Recirc Sump which contains a lower boron concentration than the ECCS injection Monday, February 20, 2012 11:13:29AM 56 Rev. FINAL

2012 HNP NRC RO

57. Given the following plant conditions:

- The plant is operating at 100% power

- Breaker 102, Unit Aux Xfmr A To Aux Bus D, is opened to isolate an electrical fault caused by a fire.

Which ONE of the following loads will de-energize AND automatically re-energize?

A. NSW Pump A B. NSW Pump B C CSIPA D. CSIPB Monday, February 20, 2012 11:13:29AM 57 Rev. FINAL

2012 HNP NRC RO

58. Given the following plant conditions:

- The plant is operating at 100% power

- A DRPI Data A and Data B failure occurs on the Shutdown Bank C Control Rod E-2

- RPI General Warning and Rod bottom LEDs are lit for Control Rod E-2 Which ONE of the following ERFIS functions will be affected by this failure?

A. AFD Monitor B. Rod Deviation Monitor C. Rod Insertion Limit Alarm D. QPTR Alarm Monday, February 20, 2012 11:13:29 AM 58 Rev. FINAL

2012 HNP NRC RO

59. Given the following plant conditions:

- The plant is operating at 100% power

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

- PT-456, Pressurizer Pressure Channel II, fails HIGH Which ONE of the following completes the statement below?

Based on the above conditions, the input from these thermocouples (G2, K5) to the Inadequate Core Cooling Monitor (ICCM) will be (1) AND the subcooling margin will be (2)

A. (1) failed low; (2) calculated by an operator.

B. (1)failed high; (2) calculated by an operator.

C. (1)failed low; (2) calculated by ICCM.

D. (1)failed high; (2) calculated by ICCM.

Monday, February 20, 2012 11:13:29AM 59 Rev. FiNAL

2012 HNP NRC RO

60. Given the following plant conditions:

- The plant is operating at 100% power

- ARR Fan S-lA is in operation in Containment

- The following alarm is received:

ALB-028-1-4, CNMT BLDG ARR CHAR FILTER TROUBLE

- ARR Fan S-IA switch indication is OFF and ARR Fan S-I B switch indication is ON Which ONE of the following (1) describes the cause of the condition AND (2) the procedure reference to correct this event?

A. (1) High zP across the filter train (2) FPP-002, Fire Emergency B. (1) High zXP across the filter train (2) AOP-036, Safe Shutdown Following A Fire C. (1) High charcoal filter temperature (2) FPP-002, Fire Emergency D. (1) High charcoal filter temperature (2) AOP-036, Safe Shutdown Following A Fire Monday, February 20, 2012 11:13:29AM 60 Rev. FINAL

2012 HNP NRC RO

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

AH-81B, Containment Pre-entry Purge Makeup Fan, will trip when Containment pressure increases to (1) INWG.

1 CB-6, Vacuum Relief SB CIV, receives an open signal at (2) INWG.

A. (1) -0.25 (2)-1.50 B. (1)-0.25 (2) -2.25 C. (1) -0.225 (2)-1.50 D. (1) -0.225 (2) -2.25 Monday, February 20, 2012 11:13:29AM 61 Rev. FINAL

2012 HNP NRC RO

62. Given the following conditions:

- The plant is operating at 100% power

- The suction pipe from Spent Fuel Pool B to the Spent Fuel Pool Cooling Pump completely severs

- Spent Fuel Pool area radiation monitor RM-IFR-3566A-SA is in HIGH alarm and monitor RM-1 FR-3567B-SB is in ALERT Which ONE of the following completes the statements below?

Level in the Spent Fuel Pool will decrease and stabilize at (1) feet above the fuel assemblies.

This condition will cause (2) train(s) of Fuel Handling Ventilation Emergency Exhaust to automatically start.

A. (1)18 (2) A B. (1)18 (2) both A and B C. (1)23 (2) A D. (1)23 (2) both A and B Monday, February 20, 2012 11:13:29AM 62 Rev. FINAL

2012 HNP NRC RO

63. Given the following plant conditions:

- The plant is operating at 7% power

- Feedwater Reg Bypass Valv&s are controlling SG level in automatic

- AFW pumps are all secured Which of the following completes the statement below?

(Assume NO operator action)

If LT-496, SG C level channel 3, fails low, SG C level will increase to (1) , at which time a (2) will occur.

A. (1)78%

(2) MFWI B. (1)78%

(2) MSLI C. (1)73%

(2) MFWI D. (1)73%

(2) MSLI Monday, February 20, 2012 11:13:29AM 63 Rev. FINAL

2012 HNP NRC RO

64. Given the following plant conditions:

- The plant is operating at 100% power

- Treated L&HS Tank A contains radioactive liquid that is required to be released.

Which ONE of the following completes the statement below?

In accordance with OP-120.10.04,Treated Laundry And Hot Shower Tanks, the Treated L&HS Tank A should be discharged to the (1) AND a new release permit is required if (2) before discharging the remaining contents of the tank.

A. (1) Waste Neutralization Settling basin (2) a valid High alarm on radiation monitor REM-3540 occurs B. (1) Waste Neutralization Settling basin (2) release flow rate on WP Computer point FA809 exceeds 80% of the Max Effluent Flow Rate C. (1) Cooling Tower Blowdown line (2) a valid High alarm on radiation monitor REM-3540 occurs D. (1) Cooling Tower Blowdown line (2) release flow rate on WP Computer point FA809 exceeds 80% of the Max Effluent Flow Rate Monday, February 20, 2012 11:13:29AM 64 Rev. FINAL

2012 HNP NRC RO

65. Given the following plant conditions:

- The plant is operating at 100% power

- Instrument Air header pressure is 70 psig and lowering slowly Which ONE of the following describes (1)the location where 1SA-506, Instrument Air from Service Air Isolation Valve, position is indicated AND (2) the status of the Instrument Air Header Low Pressure alarm?

A. (1)SLB-3 (2) Alarm is NOT lit.

B. (1) AEP-1 (2) Alarm is NOT lit.

C. (1) SLB-3 (2) Alarm is lit.

D. (1) AEP-1 (2) Alarm is lit.

Monday, February 20, 2012 11:13:29AM 65 Rev. FINAL

2012 HNP NRC RO

66. Which ONE of the following would require suspension of Core Alterations?

A. Train A Fuel Handling Building Emergency Exhaust unit is OPERABLE and in operation; Train B has just been declared INOPERABLE B. Source Range audible indication inside Containment becomes unavailable C. Reactor Cavity water level is 23 feet 3 inches above the vessel flange with only one RHR loop operable and in operation D. The Containment equipment hatch can be closed with 8 bolts Monday, February 20, 2012 11:13:29AM 66 Rev. FINAL

2012 HNP NRC RO

67. Given the following plant conditions:

- The plant is operating at 90% power

- VCT level is 38%

- VCT Level Transmitter,LT-1 12 fails high Which ONE of the following completes the statement below?

(Assume NO operator actions)

VCT level on LI-I 15 will (1) AND VCT Auto Makeup will be (2)

A. (1)lower (2) available B. (I) lower (2) unavailable C. (I) remain unchanged (2) available D. (1) remain unchanged (2) unavailable Monday, February 20, 2012 11:13:29AM 67 Rev. FINAL

2012 HNP NRC RO

68. Given the following plant conditions:

- Mode 6, Refueling is in progress Which ONE of the following lists the Key Safety Functions per OMP-003, Outage Shutdown Risk Management?

A. Subcriticality, Core Cooling, Integrity, Inventory, Containment B. Decay Heat Removal, Inventory, Electrical Power, Reactivity Control, Containment C. Residual Heat Removal, Inventory, Cavity Level, Electrical Power, Auxiliary Feed Water D. Decay Heat Removal, Reactivity Control, Integrity, Containment, Residual Heat Removal Monday, February 20, 2012 11:13:29AM 68 Rev. FINAL

2012 HNP NRC RO

69. While in Mode 1, in accordance with Technical Specifications, the action for exceeding a Reactor Coolant System pressure of (I) requires the crew to (2)

A. (1) 2735 psig (2) be in HOT STANDBY with the Reactor Coolant System pressure within its limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. (1) 2485 psig (2) be in HOT STANDBY with the Reactor Coolant System pressure within its limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. (1) 2735 psig (2) reduce the Reactor Coolant System pressure within its limits within 5 minutes D. (1)2485psig (2) reduce the Reactor Coolant System pressure within its limits within 5 minutes Monday, February 20, 2012 11:13:29AM 69 Rev. FINAL

2012 HNP NRC RO

70. Given the following plant conditions:

- A Refueling Outage is in progress

- You have been assigned a task in the RCA and are preparing to sign on to the Operations RWP

- The survey map records the radiation levels as 1050 mRem/hour in the general area Which ONE of the following describes the classification of this area and the MINIMUM approval authority?

Area Classification Individual Apirovinq Enjy A. Very High Radiation Area Lead Radiation Control Technician B. Very High Radiation Area Radiation Control Supervisor C. Locked High Radiation Area Lead Radiation Control Technician D. Locked High Radiation Area Radiation Control Supervisor Monday, February 20, 2012 11:13:29 AM 70 Rev. FINAL

2012 HNP NRC RO

71. Given the following plant conditions:

- The plant is operating at 100% power

- ALB-010-4-5, RAD Monitor System Trouble, has ALARMED

- Both REM-OILT-3502ASA, CNMT RCS Leak Detection Monitor, AND RM-ICR-3561A-SA, CNMT Vent Isolation, are in HIGH ALARM Which ONE of the following sets of actions are required in accordance with annunciator panel procedures and AOP-005, Radiation Monitoring System?

A. Verify Normal Containment Purge isolated; Monitor PRZ level and CNMT conditions B. Verify Normal Containment Purge isolated; Verify equipment alignment in accordance with CM M-004, Post-Trip/Safeguards Actuation Review C. Verify Containment Ventilation Isolation; Monitor PRZ level and CNMT conditions D. Verify Containment Ventilation Isolation; Verify equipment alignment in accordance with OMM-004, Post-Trip/Safeguards Actuation Review Monday, February 20, 2012 11:13:29AM 71 Rev. FINAL

2012 HNP NRC RO

72. Which ONE of the following identifies (1) the 10 CFR 20 annual limit for TEDE AND (2) identifies the Emergency Exposure Limit for life saving activities in accordance with PEP-330, Radiological Consequences?

A. (1)4rem (2)10 rem B. (1)5rem (2)10 rem C. (1)4rem (2) 25 rem D. (1)5rem (2) 25 rem Monday, February 20, 2012 11:13:29AM 72 Rev. FINAL

2012 HNP NRC RO

73. Given the following plant conditions:

- The plant was operating at 100% power

- A loss of Component Cooling Water has occurred

- The Reactor was tripped in accordance with AOP-014, Loss of Component Cooling Water

- The crew has entered PATH-i Under these conditions which ONE of the following describes the continued use of AOP-014?

A. Is NOT allowed during EOP performance B. Is ONLY to be used concurrently with actions of PATH-i, and ONLY where directed by the EOP procedure C. May be used concurrently with EOPs ONLY if referencing the AOP does NOT result in delaying accident mitigation D. Must be continued without interruption following the verification of PATH-i immediate actions Monday, February 20, 2012 11:13:29AM 73 Rev. FINAL

2012 HNP NRC RO

74. Given the following plant conditions:

- The plant is in Mode 6 with Refueling in progress

- A fire occurred inside Containment Per FPP-003, Fire Investigation Report, who is responsible for initiating the Fire Investigation Report and providing it to the Shift Manager?

A. Refueling SRQ B. Control Room Supervisor C. Site incident Commander D. Containment Coordinator Monday, February 20, 2012 11:13:29AM 74 Rev. FINAL

2012 HNP NRC RO

75. Which ONE of the following is (1) the LOWEST classification that REQUIRES accountability to be completed AND (2) the LOWEST classification that REQUIRES activation of the Emergency Response Organization?

A. (1)Alert (2) Alert B. (1)Alert (2) Site Area Emergency C. (1) Site Area Emergency (2) Alert D. (1) Site Area Emergency (2) Site Area Emergency You have completed the test!

Monday, February 20, 2012 11:13:29AM 75 Rev. FINAL

LOSS OF EMERGENCY COOLANT RECIRCULATION INSTRUCTIONS RESPONSE NOT OBTAINED j

7. Determine CNMT Spray Requirements:

D a. Spray pump suction ALIGNED -

D a. GOTOStep8.

TO RWST D b. Determine required number of CNMT spray pumps from Table:

CONTAINMENT SPRAY REQUIREMENTS TOTAL # OF REQUIRED #

RWST CONTAINMENT FAN COOLER OF CNMT LEVEL PRESSURE UNITS RUNNING SPRAY PUMPS GREATER THAN 45 PSIG N/A 2 GREATER THAN 23.4% BETWEEN 0 OR 1 2 10 PSIG AND 45 PSIG 20R3 1 4 0 LESS THAN 10 PSIG N/A 0 GREATER THAN 45 PSIG N/A 2 BETWEEN 3% BETWEEN 0, 1 OR 2 1 AND 23.4% 10 PSIG AN]) 45 PSIG 3OR4 0 LESS THAN 10 PSIG N/A 0 LESS THAN 3% N/A N/A 0 D c. Verify spray pumps REQUIRED NUMBER RUNNING

d. Shut CNMT spray pump discharge valve(s) for the pump(s) stopped in Step 7c:

1J 1CT-50 (A CT Pump) 0 1CT-88 (B CT Pump)

EOP-EPP-012 I Rev. 27 I Page 6 of 63

2012 HNP NRC RO WRITTEN EXAM ANSWER KEY

A

  1. ID Points Type 0 1 2O12NRCRO1 1.00 MCS A 2 2O12NRCRO2 1.00 MCS A 3 2O12NRCRO3 1.00 MCS C 4 2012 NRC R04 1.00 MCS D 5 2O12NRCRO5 1.00 MCS C 6 2012NRCR06 1.00 MCS C 7 2O12NRCRO7 1.00 MCS C 8 2O12NRCRO8 1.00 MCS B 9 2012 NRC R09 1.00 MCS D 10 2O12NRCRO1O 1.00 MCS A 11 2O12NRCRO11 1.00 MCS A 12 2OI2NRCRO12 1.00 MCS B 13 2O12NRCRO13 1.00 MCS C 14 2O12NRCRO14 1.00 MCS C 15 2O12NRCRO15 1.00 MCS D 16 2O12NRCROI6 1.00 MCS D 17 2O12NRCRO17 1.00 MCS B 18 2O12NRCRO18 1.00 MCS A 19 2OI2NRCRO19 1.00 MCS C 20 2O12NRCRO2O 1.00 MCS D 21 2O12NRCRO21 1.00 MCS A 22 2012 NRC RU 22 1.00 MCS B 23 2012 NRC RU 23 1.00 MCS D 24 2012 NRC RU 24 1.00 MCS A 25 2012 NRC RU 25 1.00 MCS D 26 2O12NRC RU 26 1.00 MCS A 27 2012NRCR027 1.00 MCS B 28 2O12NRC RU 28 1.00 MCS C 29 2012NRCR029 1.00 MCS B 30 2O12NRCRO3O 1.00 MCS A 31 2O12NRCRO3I 1.00 MCS B 32 2012NRCR032 1.00 MCS D 33 2012NRCR033 1.00 MCS C 34 2012 NRC RU 34 1.00 MCS D 35 2012NRCR035 1.00 MCS C 36 2012NRCR036 1.00 MCS A 37 2012NRCR037 1.00 MCS C 38 2OI2NRCRU38 1.00 MCS C 39 2012NRCR039 1.00 MCS D 40 2012 NRC RU 40 1.00 MCS A 41 2O12NRCRO41 1.00 MCS A 42 2012NRCR042 1.00 MCS A 43 2O12NRC RU 43 1.00 MCS C 44 2O12NRC RU 44 1.00 MCS A 45 2O12NRC RU 45 1.00 MCS D 46 2012NRCR046 1.00 MCS B 47 2012NRCR047 1.00 MCS C 48 2012 NRC RU 48 1.00 MCS C

An.,

  1. ID Points Type 0 49 2012NRCR049 1.00 MCS B 50 2O12NRCRO5O 1.00 MCS A 51 2O12NRCRO51 1.00 MCS B 52 2012NRCR052 1.00 MCS B 53 2012NRCR053 1.00 MCS A 54 2012NRCR054 1.00 MCS D 55 2012NRCR055 1.00 MCS C 56 2012NRCR056 1.00 MCS B 57 2012NRCR057 1.00 MCS C 58 2012NRCR058 1.00 MCS B 59 2012NRCR059 1.00 MCS C 60 2012NRCR060 1.00 MCS C 61 2O12NRCRO6I 1.00 MCS D 62 2012NRCR062 1.00 MCS A 63 2012NRCR063 1.00 MCS A 64 2012NRCR064 1.00 MCS C 65 2012NRCR065 1.00 MCS C 66 2012NRCR066 1.00 MCS B 67 2012NRCR067 1.00 MCS A 68 2012NRCR068 1.00 MCS B 69 2012NRCR069 1.00 MCS A 70 2O12NRCRO7O 1.00 MCS D 71 2O12NRCRO71 1.00 MCS A 72 2012NRCR072 1.00 MCS D 73 2012NRCR073 1.00 MCS C 74 2012NRCR074 1.00 MCS C 75 2012NRCR075 1.00 MCS C SECTION 1 (75 items) 75.00