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March 05000400/2008301 Final RO Written Examination & Reference
	ML081140047
Person / Time
Site:	Harris
Issue date:	03/21/2008
From:	; NRC/RGN-II
To:	; Progress Energy Carolinas
References
	50-400/08-301
	Download: ML081140047 (65)
	v • d • e

Final Submittal

(Blue Paper)

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FINAL RO

WRITTEN EXAMINATION

AND REFERENCES

I ES-40 Site-Specific RO Written Examination

Cover Sheet

u.s. Nuclear Regulatory Commission

Site-Specific RO Written Examination

Applicant Information

Name:

Date: 3/21/08 Facility/Unit: HARRIS PLANT

Region: I D II IX] III D IV D Reactor Type: WOO CE D BWD GE D

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 paperswill be collected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months afterthe examination begins.

Applicant Certification

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

Applicant's Signature

Results

Examination Value Points

Applicant's Score Points

Applicant's Grade _ _ _ _ Percent

ES-401, Page 30 of 33

Name: Harris 2008 RO Exam Rev FINAL

Form: 0

Version: 0

1.

Initial conditions:

The plant is at 80% Reactor power and ramping UP at 1/2% per minute.

Tave and Tref are matched.

Rod Control is in AUTOMATIC.

Current conditions:

ONE (1) Control Bank D Rod has just dropped and is stuck at 170 steps.

All Other Control Bank D Rods are currently indicating 206 Steps.

Assuming NO operator action is taken, which ONE of the following describes the

DEMAND for rod motion, and the effect on Axial Flux Difference (AFD) for the channel

NEAREST the control rod problem?

ROD MOTION AFD EFFECT

A. Outward Less Negative

B. Outward More Negative

C. Inward Less Negative

D. Inward More Negative

Thursday, March 20, 2008 10:35:06 AM 1

Harris 2008 RO Exam Rev FINAL

2.

Initial Plant Conditions:

The plant is Solid.

Current Plant Conditions:

A controller failure has caused 1CS-38, Letdown Pressure Control valve, to shut.

The crew has just entered AOP-019, Malfunction of RCS Pressure Control.

Which ONE of the following describes the effect of this malfunction on RCS pressure

and the actions required lAW AOP-019 to mitigate this event?

A. RCS Pressure will increase;

Ensure the RCP Seal Water Return valves are open

B. RCS Pressure will increase;

Secure the running CSIP

C. RCS Pressure will decrease;

Ensure the RCP Seal Water Return valves are shut

D. RCS Pressure will decrease;

Increase charging flow to raise RCS pressure

3.

The plant is operating at 100% power when one control rod drops fully into the core

causing Power Range N-41 to read lower than the other power range channels.

Which ONE of the following is the expected QPTR response over the next two to six

hours and why?

A. QPTR will increase due to the buildup of Xenon in the dropped rod's fuel assembly.

B. QPTR will decrease due to the buildup Xenon in the dropped rod's fuel assembly.

C. QPTR will increase due to the change in temperature in the dropped rod's fuel

assembly.

D. QPTR will decrease due to the change in temperature in the dropped rod's fuel

assembly.

Thursday, March 20, 2008 10:35:06 AM 2

Harris 2008 RO Exam Rev FINAL

4.

Given the following:

A plant startup is in progress.

Reactor power is 20%.

"B" RCP trips.

Which ONE of the following describes the effect on the reactor and "B" loop Tave?

A. Reactor remains at power;

Loop "B" Tave lowers due to Thot lowering to the value of Tcold.

B. Reactor remains at power;

Loop "B" Tave rises due to the decreased flow in the "B" loop.

C. Reactor automatically trips;

Loop "B" Tave lowers due to Thot lowering to the value of Tcold.

D. Reactor automatically trips;

Loop "B" Tave rises due to the decreased flow in the "B" loop.

5.

Which ONE of the following evolutions, by itself, will "RAISE Shutdown Margin?

A. Lowering the setpoint of the Letdown Temperature Control Valve, TCV-144, by 10

of.

B. Raising the flow setting of the boric acid flow controller by 2 turns during a blended

makeup to the VCT.

C. Raising the setting of the blended makeup flow totalizer by 100 gallons total during

a blended makeup to the VCT.

D. Lowering the setting of the boric acid batch totalizer by 20 gallons total during a

blended makeup to the VCT.

Thursday, March 20, 2008 10:35:06 AM 3

Harris 2008 RO Exam Rev FINAL

6.

Which ONE of the following sets of parameters and conditions will satisfy the interlocks

to open the Residual Heat Removal Hot Leg Suction valves (1 RH-1, 2, 39, and 40)?

A. RCS temperature is 345 of,

RCS pressure is 365 psig,

RHR discharge to CSIP valves, 1RH-25 and 1RH-63, are shut,

RHR suction from RWST valves, 1RH-322 and 1RH-323, are shut:

B. RCS temperature is 335 of,

RCS pressure 355 psig,

RHR discharge to CSIP valves, 1RH-25 and 1RH-63, are shut,

RHR suction from RWST valves, 1RH-322 and 1RH-323, are shut.

C. RCS temperature is 345 of,

RCS pressure 355 psig,

RHR suction from RWST valves, 1RH-322 and 1R'H-323, are shut.

RHR suction from Containment sump valves 1SI-300, 301, 310, and 311 are shut.

D. RHR temperature is 335 of,

RCS pressure is 365 psig,

RHR discharge to CSIP valves, 1RH-25 and 1RH-63, are shut,

RHR suction from Containment sump valves 181-300, 301, 310, and 311 are shut.

Thursday, March 20, 2008 10:35:06 AM 4

Harris 2008 RO Exam Rev FINAL

7.

Given the following:

The plant is in Mode 4.

RHR Train "A" is in service.

RHR Heat Exchanger Bypass Valve 1RH-20 is in automatic with the output at

400/0 to maintain 3750 GPM.

RHR Heat Exchanger outlet valve 1RH-30 demand position is set at 30%.

The Instrument Air supply line to RHR Heat Exchanger Outlet Valve

1RH-30 becomes severed and is completely detached.

No other air operated valves are impacted by the failure.

Which ONE of the following describes the RHR system parameter changes from the

initial steady state condition to final steady state condition?

RHR HX Outlet Temp Total RHR flow

A. Higher Lower

B. Higher Higher

c. Lower Higher

D. Lower Lower

Thursday, March 20, 2008 10:35:07 AM 5

Harris 2008 RO Exam Rev FINAL

8.

Given the following:

A reactor trip and safety injection have occurred.

RCS pressure is 1000 psig and lowering.

"A" CSIP fails to operate.

All other equipment operates as designed.

Which ONE of the following describes the expected MCB Charging Flow indication

(FI-122.1), and the Safety Injection flow indication (FI-943)?

A. MCB Charging flow 0 gpm;

Safety Injection flow is approximately 600 gpm

B~ MCB Charging flow 0 gpm;

Safety Injection flow is approximately 450 gpm

C. MCB Charging flow approximately 150 gpm;

Safety Injection flow is approximately 150 gpm

D. MCB Charging flow approximately 150 gpm;

Safety Injection flow is approximately 450 gpm

Thursday, March 20, 2008 10:35:07 AM 6

Harris 2008 RO Exam Rev FINAL

9.

Given the following:

"A" Train equipment is in service.

A Reactor Trip occurs.

All equipment is operating as designed.

The crew is performing actions of Path-1.

Conditions are as follows:

CH III CH IV

PZR press. 1865 psig 1865 psig 1845psig NA

CNMT press. 2.9 psig 3.1 psig 3.1 psig 2.9 psig

Which ONE of the following describes the status of the Charging Safety Injection

Pumps?

A. Both CSIPs are running due to SI signal on low PZR pressure.

B. Both CSIPs are running due to SI signal on high Containment pressure.

C. Only "A" CSIP is running, but "B" CSIP will be started automatically if the additional

required PZR pressure transmitter reaches the SI actuation setpoint.

D. Only "A" CSIP is running, but "B" CSIP will be started automatically if if the

additional required CNMT pressure transmitter reaches the SI actuation setpoint.

Thursday, March 20, 2008 10:35:07 AM 7

Harris 2008 RO Exam Rev FINAL

10.

Initial Conditions:

With the plant operating at 1000/0 power and all equipment in its normal

lineup, the RO takes the Reactor Trip switch to the TRIP position.

Current plant conditions are:

Reactor Trip Breaker "A" Red indication exists.

Reactor Trip Breaker "B" Green indication exists.

Reactor Power is 40/0 and lowering.

Rod bottom lights are lit with the exception of FOUR Control Bank D rods.

Their positions are as follows:

H-8 - 16 steps

K-2 - 220 steps

M-12 - 8 steps

M-8 - 20 steps

Which ONE of the following describes the condition of the reactor, and the action that

will be required?

A. The reactor is tripped;

Perform normal RCS boration for the stuck rods as directed by EPP-004

referencing OP-107, Charging and Volume Control System.

B. The reactor is tripped;

Initiate emergency boration for the stuck rods as directed by EPP-004 referencing

AOP-002, Emergency Boration.

C. The reactor is not tripped;

Manually insert control rods in accordance with FRP-S.1 until all rods are on

bottom.

D. The reactor is not tripped;

Initiate emergency boration for the stuck rods in accordance with FRP-S.1 until

adequate Shutdown Margin is verified.

Thursday, March 20,2008 10:35:07 AM 8

Harris 2008 RO Exam Rev FINAL

11.

Given the following:

The plant is at 100% power.

A PressurizerPORV has a slow leak through the seat or disk.

The respective PORV isolation valve cannot be closed.

ALB-009-8-1, PRESSURIZER RELIEF TANK HIGH-LOW LEVEL PRESS OR

TEMP, is actuated.

PRT Level is 73%.

PRT Temperature is 128 of.

PRT Pressure is 6.3 Psig.

Which ONE of the following parameters is causing the alarm, and which ONE of the

following is the action required to be performed from OP-100, Reactor Coolant System,

Section 8, Infrequent Operations?

A. Pressure;

Vent the PRTas necessary to control pressure.

B. Pressure;

Drain the PRT as necessary to control pressure while maintaining level within the

normal band.

C. Temperature;

Recirculate the PRT contents through the RCDT Heat Exchanger to lower

temperature.

D. Temperature;

Drain PRT to the low end of the normal band and then refill with demineralized

water to lower temperature.

Thursday, March 20, 2008 10:35:07 AM 9

Harris 2008 RO Exam Rev FINAL

12.

Given the following:

The plant is at 1Ooo~ power.

The temperature input to Letdown Heat Exchanger CCW flow control valve

TCV-144, 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 CCW flow to Letdown Heat Exchanger;

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

B. High CCW flow to Letdown Heat Exchanger;

Isolate letdown and place Excess Letdown in service.

C. High temperature letdown diversion to VCT;

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

D. High temperature letdown diversion to VCT;

Isolate letdown and place Excess Letdown in service.

13.

Given the following:

A reactor trip has occurred from 100 % power.

Pressurizer pressure is 2050 psig and lowering.

Pressurizer level is rising rapidly.

Containment pressure is 1 psig and slowly rising.

Assuming NO operator action, which ONE of the following could have caused the

event in progress?

A. Master Pressure Controller PT-444 output failed LOW

B. Both Pressurizer Spray Valves failed OPEN

C. Master Pressure Controller PT-444 output failed HIGH

D. Small break LOCA on an RCS Hot Leg

Thursday, March 20, 2008 10:35:07 AM 10

Harris 2008 RO Exam Rev FINAL

14.

Given the following:

A reactor trip has occurred.

Safety Injection is actuated.

All actions required in Path-1 have been taken.

All RCPs are running.

RCS pressure is 1450 psig and stable.

SI flow is 150 GPM.

Containment pressure. is 4.5 psig and slowly rising.

SG pressures are 1050psig and stable.

Which ONE of the following describes the plant condition upon transition from Path-1?

A. RCPs should NOT be tripped.

SGs are required for subsequent RCS heat removal.

B. RCPs should NOT be tripped.

SGs are NOT required for subsequent RCS heat removal.

C. RCPs should be tripped.

SGs are required for subsequent ReS heat removal.

D. RCPs should be tripped.

SGs are NOT required for subsequent RCSheat removal.

Thursday, March 20, 2008 10:35:07 AM 11

Harris 2008 RO Exam Rev FINAL

15.

Initial Plant Conditions:

The plant was at 100% power.

Current plant conditions are:

A Loss of Off-site Power occurs.

Bus 1A-SA is locked out.

All other equipment has operated as designed.

Diesel loading sequence is complete.

RCS pressure is 2180 psig.

Assuming NO operator action has been taken, which ONE of the following describes

the status of the PZR Heaters?

A. ALL PZR Backup Heaters are DE-ENERGIZED.

B. Group B is the only PZR heater group ENERGIZED.

C. Group C is the only PZR heater group ENERGIZED.

D. Groups Band C are the only PZR heater groups ENERGIZED.

Thursday, March 20, 2008 10:35:07 AM 12

Harris 2008 RO Exam Rev FINAL

16.

Which ONE of the following describes the characteristics of a design basis Large Break

LOCA twenty (20) minutes into the event?

A. RCS temperature is at saturation temperature for intact SG pressure;

RCS pressure is stable below normal 81 accumulator pressure, but above RHR

pump shutoff head.

B. RCS temperature is at saturation temperature for intact 8G pressure;

RCS pressure is stable below RHR Pump shutoff head.

C. RCS temperature is below saturation temperature for intact 8G pressure;

RCS pressure is stable below normal 81 accumulator pressure, but above RHR

pump shutoff head.

D. RCS temperature is below saturation temperature for intact 8G pressure;

RCS pressure is stable below RHR Pump shutoff head.

17.

Given the following:

The unit is at 100% power.

Unit electrical alignment is normal.

Aux Bus 1 0 'deenerqizes and is locked out.

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

A. "A" NSW Pump

B. "B" NSW Pump

C. "A" CSIP

D. "B" CSIP

Thursday, March 20,*2008 10:35:07 AM 13

Harris 2008 RO Exam Rev FINAL

18.

Given the following:

The plant is operating at 30% reactor power, steady state.

I&C technicians are preparing to perform a calibration on Power Range Channel

N-41.

One I&C technician mistakenly pulls the control power fuses on N-42.

Realizing his mistake, he reinserts the fuses for N-42 and then pulls the control

power fuses for the correct channel, N-41.

Which ONE of the following describes the status of the reactor after the N-41 fuses

were pulled and which bistable(s) in N-42 would be tripped?

A. The reactor is tripped;

PR Positive Rate Trip and PR Negative Rate Trip.

B. The reactor is tripped;

PR Postive Rate Trip ONLY.

C. The reactor is NOT tripped;

PRPositive Rate Trip and PR Negative Rate Trip.

D. The reactor is NOT tripped;

PR Positive Rate Trip ONLY

19.

Given the following:

Pressurizer Pressure Protection Channel PT-455 has failed off-scale HIGH.

NO Operator action has been taken.

Which ONE of the following identifies the MINIMUM additional channels required to

meet the ESF and RPS actuation logic to initiate a reactor trip and safety injection on

Pressurizer Pressure?

A. Reactor Trip - 1; Safety Injection - 1

B. Reactor Trip - 1; Safety Injection - 2

C. Reactor Trip - 2; Safety Injection - 1

D. Reactor Trip - 2; Safety Injection - 2

Thursday, March 20, 2008*10:35:08 AM 14

Harris 2008 RO Exam Rev FINAL

20.

Given the following:

A LOCA has occurred.

RCSpressure is 200 psig.

"A" Containment Spray Pump is Out of Service.

Containment pressure is 12 psig and slowly increasing.

Train "B" Phase A has failed to actuate.

Normal Containment Purge was in service at the time of the LOCA.

The Containment Ventilation Isolation Signal (CVIS) fails to actuate.

All other ECCS equipment is running as required.

Assuming no action by the crew, which ONE of the following describes the effect on

the plant?

A. Containment Normal Purge Makeup fans will trip and their associated dampers

SHUT.

B. Offsite dose consequences will exceed the guidelines of 10CFR100.

C. Normal Containment Purge Makeup valves (1CP-6 and 9) will remain OPEN.

D. Only half of the Containment penetrations required for containment isolation will be

isolated.

21.

Given the following:

The plant is at 200/0 power.

Rod Control is in AUTO.

The operating crew is preparing to stop RCP 1C due to rising vibration.

Assuming that reactor power is maintained at 200/0, which ONE of the following

describes the expected indications on Loop 1 and Loop 3 flowrates when RCP 1C is

stopped?

Loop 1 Flowrate Loop 3 Flowrate

A. increase to 110 0/0 decreases to 0 0/0 and stabilizes

B. increase to 110 0/0 decreases to 00/0 then increases to 10 0/0

C. increase to 120% decreases to 0 0/0 and stabilizes

D. increase to 120% decreases to 00/0 then increases to 100/0

Thursday, March 20,2008 10:35:08 AM

Harris 2008 RO Exam Rev FINAL

22.

Given the following:

The plant is at 60% power during a plant startup.

Steam Dumps are in the Tave mode of control.

First Stage Pressure Transmitter PT-446 fails high.

Assuming the reactor remains at power, which ONE of the following describes the

effect on the steam dump system?

A. Steam Dumps will receive an arming signal.

B. Steam Dumps will receive a modulation (open) signal.

C. Steam Dumps will NOT arm if required.

D. Steam Dumps will NOT modulate if required.

23.

Given the following:

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 circuitfailures, the input from these thermocouples to the Inadequate

Core Cooling Monitor (ICCM) will be and the subcoolng margin

calculated by ICCM will be _

A. failed low;

higher

B. failed low;

unaffected

C. failed high;

lower

D. failed high;

unaffected

Thursday, March 20,2008 10:35:08 AM 16

Harris 2008 RO Exam Rev FINAL

24.

Initial Conditions:

Containment Cooling is in the Normal Cooling Mode of operation with Train "A"

in service.

Containment temperature has been slowly rising.

Current Conditions:

The crew has placed the Containment Cooling system in Maximum Cooling

Mode per OP-169, Containment Cooling System.

Containment temperature is now lowering.

Which ONE of the following identifies the MINIMUM temperature at which a Technical

Specification action statement must be entered and the expected alignment for the

Containment Cooling System?

A. 118 OF

BOTH fans in AH-3 and AH-4 in high speed AND ONE (1) fan in AH-1 and AH-2 in

high speed.

B.118°F

BOTH fans in AH-3 and AH-4 in high speed AND BOTH fans in AH-1 and AH-2 in

high speed.

C. 120 OF

BOTH fans in AH-3 and AH-4 in high speed AND ONE (1) fan in AH-1 and AH-2 in

high speed.

D. 120 of

BOTH fans in AH-3 and AH-4 in high speed AND BOTH fans in AH-1 and AH-2 in

high speed.

Thursday, March 20,2008 10:35:08 AM 17

Harris 2008 RO Exam Rev FINAL

25.

Given the following:

The plant is at 100 % power.

VCT Level Channel LT-112 fails high.

Assuming NO operator action, which ONE of the following describes the function(s)

lost due to this failure?

A. ONLY Divert to RHT will be disabled

B. ONLY Auto Swapover from RWST will be disabled.

C. Auto Swapover from RWST AND Auto Makeup will be disabled.

D. Divert to RHT AND Auto Makeup will be disabled.

Thursday, March 20, 2008 10:35:08 AM 18

Harris 2008 RO Exam Rev FIN*AL

26.

Initial conditions:

The plant is at 1000/0 power.

Train "B" Containment Fan Cooling is in service.

Current conditions:

A Safety Injection signal has occurred.

All equipment is operating as designed.

Which ONE of the following describes the operation of Containment Cooling?

One fan in each Fan Cooler Unit is operating in...

A. LOW speed;

Normal Service Water aligned.

B. HIGH speed;

Normal Service Water aligned

C. LOW speed;

Emergency Service Water aligned

D. HIGH speed;

Emergency Service Water aligned

Thursday, March 20,2008 10:35:08 AM 19

Harris 2008 ROExam Rev FINAL

27.

Initial conditions:

"A" Boric Acid pump is under clearance for motor replacement.

Current conditions:

1B-SB Emergency Safety Bus locks out due to an 86UV failure.

The crew is performing an Emergency Boration in accordance with AOP-002,

Emergency Boration, due to a secondary load rejection.

The RO performs the required valve alignment to provide a boration source.

Which ONE of the following describes the action and/or verification required to ensure

that the required boration flow is achieved?

A. Verify a minimum of 30 GPM on FI-11 0, Emergency Boration flow.

B. Verify a minimum of 30 GPM on FI-113, Boric Acid flow.

C. Adjust FCV-122 as necessary to achieve a minimum of 30 GPM on FI-122.1,

Charging Header flow.

D. Adjust FCV-122 as necessary to achieve a minimum of 90 GPM on FI-122.1,

Charging Header flow.

Thursday, March 20, 2008 10:35:08 AM 20

Harris 2008RO Exam Rev FINAL

28.

Given the following:

The plant is in Mode 5.

An RCS leak and loss of RHR occurs..

The crew is performing actions of AOP-020, Loss of RCS Inventory or Residual

Heat Removal While Shutdown.

The crew is aligning to provide RCS Makeup using CSIP flow in accordance with

section 3.6, Establishing SI Following a Major RCS Leak.

Which ONE of the following describes the required actions to provide RCS makeup in

this condition?

A. Start ONE (1) CSIP;

Initiate flow though the BIT

B. Start ONE (1) CSIP;

Initiate flow though the normal charging line

C. Start TWO (2) CSIPs;

Initiate flow though the BIT

D. Start TWO (2) CSIPs;

Initiate flow though the normal charging line

Thursday, March 20,2008 10:35:08 AM 21

Harris 2008 RO Exam Rev FINAL

29.

Initial Conditions:

Surveillance testing is in progress on Containment Spray Train "A".

"A" Containment Spray Pump is running.

1CT-24-SA and 1CT-25-SB; Containment Spray Eductor Test Valves, are open

for testing.

1CT-50-SA, Containment Spray Pump 1A-SA Discharge Valve, is closed.

Current conditions:

A LOCA occurs.

RCS pressure is 600psig.

Containment Pressure is 10.5 psig.

Which ONE of the following correctly lists the position of the Containment Spray

Eductor Test Valves and the 1A-SA Discharqe Valve for the current plant conditions?

1CT-24-SA and 1CT-25-SB 1CT-50-SA

A. OPEN OPEN

B. CLOSED OPEN

C. OPEN CLOSED

D. CLOSED CLOSED

Thursday, March 20, 2008 10:35:08 AM 22

Harris 2008 RO Exam Rev FINAL

30.

Given the following:

The plant is in Mode 1.

12:00 Containment Spray Pump 1A-SA declared INOPERABLE due to a failed

surveillance.

12:27 Containment Spray Pump 1B-SB also declared INOPERABLE due to the

results of a common cause failure analysis.

14:21 Containment Spray Pump 1A-SA returned to OPERABLE status.

14:40 Containment Spray Pump 1B-SB returned to OPERABLE status.

Which ONE of the following describes the Technical Specification requirements for

operation of the plant?

Actions to initiate a plant shutdown must commence no later than ...

A. 12:27;

The. shutdown may be terminated no earlier than 14:21.

B. 12:27;.

The shutdown may be terminated no earlier than 14:40.

C. 13:27;

The shutdown maybe terminated no earlier than 14:21.

D. 13:27;.

The shutdown maybe terminated no earlier than 14:40.

Thursday, March 20, 200810:35:09 AM 23

Harris 2008 RO Exam Rev FINAL

31.

Given the following:

The plant is operating at 100% power.

A failure of the PT-444 input to PK-444A, Pressurizer Pressure Master

Controller, caused actual pressurizer pressure to decrease to 2190 psig.

PK-444A has been placed in MANUAL.

Which ONE of the following describes the action required to return pressure to 2235

psig?

A. Decrease the controller output.

B. Increase the controller output.

C. Lower the pressuresetpoint adjustment.

D. Raise the pressure setpoint adjustment.

Thursday, March 20, 2008 10:35:09 AM 24

Harris 2008 RO Exam Rev FINAL

32.

Given the following:

The unit is in Mode 6.

Refueling activities are in progress.

A fuel assembly has been ruptured during removal from the core.

Radiation levels are rising steadily and are currently as follows:

REM-01 LT-3502A-SA, Cnmt RCS Leak Detection Monitor, is in HIGH

ALARM

REM-01 LT-3502B-SB, Cnmt Pre-Entry Purge Monitor, is in HIGH

ALARM

Which ONE of the following describes the system isolation signal(s), if any, that have

been automatically initiated, and action required in accordance with AOP-013, Fuel

Handling Accident?

A. ONLY a Containrnent Pre-Entry Purge isolation signal has been initiated.

Perform an evacuation from Containment.

B. BOTH Normal Containment Purge AND Containment Pre-Entry Purge isolation

signals have been initiated.

Perform an evacuation from Containment.

C. ONLY a Containment Pre-Entry Purge isolation signal has been initiated.

Dispatch Radiation Protection to determine if Containment Evacuation is required.

D. BOTH Normal Containment Purge AND Containment Pre-Entry Purge isolation

signals have been initiated.

Dispatch- Radiation Protection to determine if Containment Evacuation is required ..

Thursday, March 20,2008 10:35:09 AM 25

Harris 2008 RO Exam Rev FINAL

33.

Given the following:

The plant is at 100% power.

A transient on SGlevel required a reactor trip, butthe reactor did not trip.

The crew is performing FRP-S.1, Response To Nuclear Power Generation /

ATWS.

The crew notes that the Pressurizer pressure is 2350 psig.

Control rods are inserting in AUTO.

All Pressurizer PORV valve position indicating green lights are on and red

lights are off.

Which ONE ofthe following actions are required in relation to the PZR PORVs?

A. Verify ONLY ONE Pressurizer PORV and Block valve OPEN;

reduce pressure to less than 2135 psig.

B. Verify ALL Pressurizer PORVsandBlock valves OPEN;

reduce pressure to less than 2135 psig.

C. Verify ONLY ONE PressurizerPORVand Block valve OPEN;

reduce pressure to less than 2235 psig.

D. Verify ALL Pressurizer PORVs and Block valves OPEN;

reduce"pressure to less than 2235 psig.

Thursday, March 20,2008 10:35:09 AM 26

Harris 2008 RO Exam Rev FINAL

34.

Given the following:

The plant is at 40% power.

Intermediate Range Channel N-35 loses compensating voltage.

I&C is called to investigate.

Prior to any action by f&C, a reactor trip occurs.

Which ONE of the following describes the expected Source Range response in this

condition and why?

A. Source Range Instruments will automatically energize prematurely; they must be

manually de-energized until approximately 5 minutes post-trip to prevent damage to

the detectors.

B. Source Range Instruments will automatically energize prematurely; they must be

manually de-energized until approximately 15 minutes post-trip to prevent damage

to the detectors.

C. Source Range Instruments will not automatically energize when required; they must

be manually energized approximately 5 minutes post-trip to prevent a loss of

reactor power indication.

D. Source Range Instruments will not automatically energize when required; they must

be manually energized approximately 15 minutes post-trip to prevent a loss of

reactor power indication.

Thursday, March 20,2008 10:35:09 AM 27

Harris 2008 RO Exam Rev FINAL

35.

Initial plant conditions:

The plant is in Mode 6 with Refueling in progress.

Current plant conditions are:

Fuel movement has stopped due to a problem with the Manipulator.

The Main Control Room has been informed that initial troubleshooting is in

progress onthe Manipulator.

The troubleshooting team desires to operate TS~5, the TROLLEY INTERLOCK

BYPASS switch to permit forward and reverse motion of the trolley without the

gripper tube at its top limit.

Which ON.Eof the following describes the permission and concurrence, if any, required

for this action?

A. The SRO-FuelHandling must approve. No concurrence is required.

B. The SRO-Fuel Handling must approve with the concurrence of the SSO.

C. The SSOmust approve with concurrence of the Manager - Mechanical

Maintenance.

D. The SSO must approve. No concurrence' is required.

Thursday, March 20; 2008 10:35:09 AM 28

Harris 2008 RO Exam Rev FINAL

36.

Given the following:

Refueling is in progress.

A spent fuel assembly is being moved in the Fuel Handling Building (FHB) when

- it's damaged by contacting a wall of the pool.

Spent Fuel Pool area radiation monitor RM-1FR-3566A-SAis in HIGH alarm.

Spent Fuel Pool area radiation monitor RM-1FR-3567B-SB is in ALERT.

Which ONE of the following describes the effect on the plant?

A. ONLY "A" train of Fuel Handling Building Ventilation Emergency Exhaust has

received an automatic start signal.

B. BOTH "A" and "B" trains of Fuel Handling Building Ventilation Emergency Exhaust

have received .automatic start signals.

c. NEITHER train of Fuel Handling Building Ventilation Emergency Exhaust has

received an automatic start signal, and manual start is NOT required.

D. NEITHER train of Fuel Handling Building Ventilation Emergency Exhaust has

received an automatic start signal, but manual start is required by AOP-013, Fuel

Handling Accident.

Thursday, March 20, 2008 10:35:09 AM 29

Harris 2008 RO Exam *Rev FINAL

37.

Given the following:

A Steam Generator Tube Rupture has occurred.

Off-Site power has been lost.

Both DG's are operating as required.

Pressurizer level indicates 10 % and lowering slowly.

All plant equipment has responded as expected for the plant conditions.

Which ONE of the following describes a plant concern during the performance of

Path-2 for these conditions?

A. Voiding in the inactive regions of the RCSduring the rapid RCS cooldown to target

temperature.

B. Loss of ReS subcooling during depressurization using main or auxiliary spray.

C. Voiding in the inactive regions of the RCS during depressurization using a PZR

PORV.

D. Loss of RCS subcooling due to the time required to cooldown to target temperature

with condenser steam dumps unavailable.

Thursday, March 20, 2008 10:35:09 AM 30

Harris 2008 RO Exam Rev FINAL

38.

Given the following:

A reactor trip has occurred from 100% power.

All systems functioned as designed.

Which ONE of the following describes the position of valves associated with the Main

Turbine?

A. Throttle Valves - CLOSED

Intercept Valves - CLOSED

Reheat Stop Valves -OPEN

B. Governor Valves - OPEN

Intercept Valves - OPEN

Reheat Stop Valves - CLOSED

C. Throttle Valves - CLOSED

Intercept Valves - CLOSED

Reheat Stop Valves - CLOSED

D. Governor Valves - OPEN

Intercept Valves - CLOSED

Reheat Stop Valves - CLOSED

Thursday, March 20, 2008 10:35:09 AM 31

Harris 2008 RO Exam Rev FINAL

39.

Given the following:

A Steam Line break has occurred on "C" SG.

The crew has performed actions contained in EPP-014, Faulted SG isolation.

SG "C" pressure is 50 psig.

SG "C" WR level is off-scale low.

SG "A" and "B" NR levels are being controlled at 25%.

SG "A" and "B" pressures are approximately 900 psig and stable.

Which ONE of the following describes the action required lAW EPP-014, and the

. reason for this action?

A. Isolate AFW flow to SG"C";

Minimize RCS cooldown and the mass and energy release from the steam line

break

B. Isolate AFW flow to SG "C" ;

Failure of components in "C SG may occur due to thermal shock

C. Initiate AFW flowtoSG "C at the MINIMUM verifiable rate;

Feeding the "C" SG is required for cooldown, but high AFW flow rates may cause

an excessiveRCS cooldown requiring an undesired transition out of EPP-014

D. Initiate AFW flow to SG "C" at the MINIMUM verifiable rate;

Feeding the "C" SG is required forcooldown, .but high AFW flow rates may cause

failure ofSG"C" components due to thermal shock

Thursday, March 20,2008 10:35:09 AM 32

Harris 2008 RO Exam Rev FINAL

40.

Initial Plant Conditions:

The plant is at 100% power.

Current Plant Conditions:

A spurious turbine trip occurs.

The C-8interlock fails to operate.

All other plant equipments responds as expected.

Which *ONE of the following describes the response of the Steam Dump Control

System (SDCS) and the overall effect on the RCS temperature?

A. SDCS will control temperature using the Turbine Trip Controller;

RCS temperaturewillbecontrolled at normal no-load temperature.

B. SDCS will control temperature using the Load Rejection Controller;

RCS temperature will be controlled at normal no-load temperature.

C. SDCS will control temperature using the Turbine Trip Controller;

RCS temperature will be controlled at approximately 3 degrees above normal

no-load temperature.

D. SDCS will control temperature using the Load Rejection Controller;

Res temperature will be controlled at approximately 3 degrees above normal

no-load temperature.

Thursday, March 20,2008 10:35:10 AM 33

Harris 2008 RO Exam Rev FINAL

41.

Given the following:

The Reactor is critical atthePOAH.

The crew is preparing to perform a turbine startup lAW GP-005, Power

Operation.

Which ONE ofthe following describes the expected rod height for Control Bank "0"

rods lAW GP-005 and the basis for this band?

A. Between 95 and 115 steps;

Helps ensure IR trip and rod stop bistable setpoints are not reached before they

can be blocked

B. Between 130 and 150 steps;

Helps ensure IR trip and rod stop bistable setpoints are not reached before they

can be blocked

C. Greater than 95 steps;

Minimum height required to remain above Rod Insertion Limit

o. Greater than 130 steps;

Mi-nimum height required to remain above Rod Insertion Limit

Thursday, March 20, 200810:35:10 AM 34

Harris 2008 RO Exam Rev FINAL

42.

Initial Conditions:

The plant is at 1000/0 power.

Testing isin progress on the AFW system.

The "A" MDAFW pump is running with the MDAFW FCVs 200~ open.

Current Conditions:

A trip of bothMFWpumps occurs.

The lowest SG levels during the transient were:

SG"A"=18%

SG"B" = 24°~

SG "C" =28%

Assuming NO operator actions have occured, which ONE of the following describes the

current status of the MDAFW Flow Control Valves (FCVs) and TDAFW pump for this

event?

MDAFW FCVs TDAFW Pump

A. 200~ Open Running

B. 200~ Open Secured

C. Full Open Running

D. Full Open Secured

Thursday, March 20,2008 10:35:10 AM 35

Harris 2008 ROExam Rev FINAL

43.

Given the following:

The plant is at 1000/0 power.

An Extreme HI-HI ,level is received in Feedwater Heater 1A.

Which ONE of the following describes the impact on the unit and the action, if any, that

is required in accordance with OP-136, Feedwater Heaters?

A. ONLY Feedwater Heaters 1A and 2A are bypassed;

Reduce Turbine Load to less than 70 0/0.

B. ONLY Feedwater Heater 1A and 2A are bypassed;

Ensure reactor power less than 1000/0, NO additional power restrictions are required

c. FeedwaterHeaters1A, 2A, 1B, and 28 are bypassed;

Reduce Turbine Load to less than 700/0.

D. FeedwaterHeaters 1A, 2A, 1B, and 28 are bypassed;

Ensure reactor power less than 100 0/0, NO additional power restrictions are required

Thursday, March 20, 2008 10:35:10 AM 36

Harris 2008 RO Exam Rev FINAL

44.

Given the following:

The plant was operating at 98% power when a loss of off-site power occurred.

Twenty minutes later, the following plant conditions exist:

RCS pressure is 2235 psig and stable.

RCS Loop THOT is 596°F in all 3 loops and lowering.

RCS Loop TCOLD is 552°F in all 3 loops and lowering.

Core exit TCsindicate approximately 600°F and lowering slowly.

Steam Generator pressures are approximately 1048 psig and stable.

Which ONE of the' following describes the current plant conditions?

(Steam Tables are provided.)

A. Natural Circulation does not exist.

Heat removal must be established by opening the condenser steam dumps.

B. Natural Circulation exists.

Heat removal is being maintained by condenser steam dumps.

C. Natural Circulation does not exist.

Heat removal must be established by opening the SG PORVs.

D. Natural Circulation exists.

Heat removal is being maintained by SG PORVs.

Thursday, March 20, 2008 10:35:10 AM 37

Harris 2008 RO Exam Rev FINAL

The plant is in Mode 3.

A loss of DC Bus DP-1B-SBhas occurred.

The crew is performing actions of AOP-025, Loss of One Emergency AC Bus

(6.9 kV) or ONE Emergency DC Bus (125V)

Which ONE of the following describes the reason for ensuring that letdown orifice

valves are shut in accordance with AOP-025?

A. Preventwater hammer or flashing in the letdown line.

B. Prevent RCS leakage in excess of Technical Specification limits.

C. Minimize reduction in PZR level with loss of charging flow.

D. Prevent damage to the Regenerative Heat Exchanger.

46.

For the Steam Generator Water Level Control System (SGWLCS), which ONE of the

following describes this system's normal operation and program level input?

A. SGWLCS is a level dominant system that ultimately adjusts Feed Reg valve

position by level error.

Program level isvariab.lebased on input from Turbine First Stage pressure.

B. SGWLCS is a level dominant system that ultimately adjusts Feed Reg valve

position by level error.

Program level is constant at 57°A, NR.

C. SGWLCSis a flow dominant system that ultimately adjusts Feed Reg valve position

by mismatch in steam flow VS. feed flow.

Program level is variable based on inputfrom Turbine First Stage pressure.

D. SGWLCS is a flow dominant system that ultimately adjusts Feed Reg valve position

by mismatch in steam flowvs. feed flow.

Program level is constantat57%NR.

Thursday, March 20,200810:35:10 AM 38

Harris 2008 RO Exam Rev FINAL

47.

Given the following:

The plant is at 100% power.

The following alarm has just been received:

ALB-04-2-2,REFUELING WATER STORAGE LOW LEVEL

All other MCR alarms are clear

The crew enters AOP-008, Accidental Release of Liquid Waste

Which ONE of the following describes the setpoint for the alarm received, and the

action required in accordance with AOP-008?

A. 9'4.3%;

Immediately begin refilling the RWSTto above the alarm setpoint

B. 94.3%;'

Stop all additions to the RWST

C. 23.40/0;

Ensure RHR and Containment Spray Pumps are de-energized

D. 23.40/0.

Ensure CSIP suctions are isolated from the RWST

48.

Which ONEol the following instruments failures will cause actual feedwater flow to the

affected SG to INITIALLY lower? (Assume selected)

A. SGlevel fails low

B. Feedwater flow fails low

C. Steam pressure fails high

D. Steam flow fails low

Thursday, March 20, 2008 10:35: 10 AM 39

Harris 2008 RO Exam Rev FINAL

49.

Given the following:

A Gaseous Waste release of Gas Decay Tank C is in progress.

An ALERT alarm is received on REM-3546, WPB Stack 5 PIG monitor.

Activity leveLisstable just above the ALERT setpoint.

Which ONE of the following describes the action required in accordance with

OP-120.07?

A. The release MUST be stopped; release may continue under the same release

permitafter REM-3546 is determined to be operable and curie content of the

release is determined to be within limits.

B. The release MUST be stopped; a new release permit must be generated prior to

resuming the decay tank release.

C. The release may continue; if activity level approaches or exceeds the HIGH alarm

setpoint, stop the release; release may continue underthe same release permit

after REM-3546 is determined to be operable and curie content of the release is

determined to be within limits.

D. The release may continue; if activity level approaches or exceeds the HIGH alarm

setpoint, stop the release; a new release permit must be generated prior to

resuming the decay tank release.

Thursday, March 20, 2008 10:35:10 AM 40

Harris 2008 ROExam Rev FINAL

50.

Given the following:

The plant is operating at 50%* power.

The Turbine Driven AFW pump was taken OOS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ago for bearing

replacement.

Both Motor Driven AFW pump motors have been determined to be

INOPERABLE due to a common cause failure analysis.

Which ONE of the following actions is required?

A. Immediately initiate action to restore one AFW train to operable status; power

operation is currently allowed with all three AFW Pumps Inoperable.

B. Restore at least 2 AFW Pumps to service within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , or be in Hot Standby within

the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

C. Restore at least 1 AFW Pump to service within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , or be in Hot Standby within

the foHowing6 hours.

D. Immediatelyenterthe action of TS 3.0.3 and be in at least HOT STANDBY within 7

hours from the time it was determined that no AFW pumps were operable.

Thursday, March 20, 2008 10:35:11 AM 41

Harris 2008 RO Exam Rev FINAL

51.

Given the following:

The plant is in mode 3

RCS heatup is in progress

As AFWfiow to the steam generators is increased, what will happen to the initial heat

transfer rate between RCS and the steam generators and why?

The heat transfer rate will...

A. increase;

because the-cooler AFW water will increase the delta T between the RCS and the

steam generators.

B. decrease;

because the cooler AFW water will decrease the delta T between-the RCS and the

steam generators.

C. increase;

because increasing SG level causes SG pressure and saturation temperature to

increase.

D. decrease;

because increasing SGlevel causes SG pressure and saturation temperature to

decrease.

Thursday, March 20,2008 10:35:11 AM 42

Harris 2008 RO Exam Rev FINAL

52.

Given the following:

The plant is at 100 oiOpower.

Recovery from a Loss of Instrument Bus 1DP-1A-S1 is in progress.

The crew has de-energized the associated Process Instrumentation Cabinet

(PIC) in preparation for energizing Instrument Bus 1DP-1A-S1.

The crew is evaluating bistable status prior to energizing the bus.

Which ONE of the following describes the reason for checking bistable status?

A. When the Instrument bus is energized with the PIC deenergized, a reactor trip may

occur due to 'de-enerqize to actuate' bistables becoming actuated. Checking other

bistables ensures' a Reactor Trip will not occur.

B. When the PIC is energized after the Instrument Bus is energized,'energizeto

actuate' bistables may experience a momentary inadvertent trip. Checking other

bistables ensures an ESF actuation will not occur.

C. Bistables are checked to ensure that each parameter for Process or Protection

goes to its required state when the Instrument Bus and PIC are energized.

D. Bistables are checked to ensure that all lights areout,verifying that the PIC normal

and alternate supply breakers are open prior to reenergizing the Instrument Bus.

Thursday, March 20, 2008 10:35: 11 AM 43

Harris 2008 RO Exam Rev FINAL

53.

Initial Plant Conditions:

Yesterday, a loss of ESW Header "A" occurred due to a failure shaft shear of the

"A"ESW Pump.

The crew completed AOP-022, Attachment 1, Equipment Alignment Due to Loss

of anESW Header.

The crew implemented OWP-SW, Operations Work Procedure Service Water,

due to the extended loss of the "A" ESWheader.

Current Plant Conditions:

A loss of off-site power occurs coincident with a safety injection

actuation.

Which ONE of the following describes the alignment of ESW loads for the current plant

condition?

A. "A" EDG will NOT automatically start because implementation of OWP-SW places

the diesel in MAINTENANCE MODE.

B. "A" EDG will automatically start, but must be manually tripped because it will have

no ESWflow.

C. "All EDG will NOT automatically start because implementation of OWP-SW will

have barred the diesel.

D. "A" EDG will automatically start, but operators must realign NSW to the ESW

header.

Thursday, March 20, 2008 10:35: 11 AM 44

Harris 2008 RO Exam Rev FINAL

54.

Given the following:

The plant is in Mode 3.

AFW Pump 1A-SA is operating to provide secondary inventory.

DC Bus DP-1A-SA becomes de-energized.

Which ONE of the following describes the effect on the operating AFW pump?

A. MCRcontrol switch indication is extinguished.

Pump remains running.

MCRbreaker control is lost

B. MCR control switch indication is extinguished.

Pump remains running.

MCR breaker control is available

C. MCR control switch indication is available.

Pump trips.

MCR breaker control is lost

D. MCRcontrol switch indication is available.

Pump trips.

MCRbreaker control is available

55.

Which ONE of the following describes the MAXIMUM continuous rating of the

Emergency Diesel Generators?

A. 6500 KW at a power factor of 0.8 leading

B. 6500 KW at a power factor ofO'B lagging

C. 7150 KWata power factor of 0.8 leading

D. 7150 KWat a power factor of 0.8 lagging

Thursday, March 20,2008 10:35:11 AM 45

Harris 2008 RO Exam Rev FINAL

56.

Given the following:

The unit is in Mode 4.

Maintenance reports that the inner door on the Containment Emergency Airlock

will not seal properly after leaving Containment.

The crew has declared the inner door INOPERABLE and closed the outer door.

Which ONE of the foHowing describes the status of CONTAINMENT INTEGRITY, per

Technical Specification Definitions, and the required Technical Specification action?

A. Containment Integrity IS met;

Immediately verify the outer door closed

B. Containment Integrity IS NOT met;

Immediately verify the outer door closed

C. Containment Integrity IS met;

Verify the outer door closed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

D. Containment Integrity IS NOT met;

Verify the outer door closed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

57.

Which ONE of the following would be used to change the alarm setpoints from the

Main Control Room of a safety related radiation monitor?

A. RM-11

B. RM-23

C. RM-23P

D. RM-80

Thursday, March 20,2008 10:35:11 AM 46

Harris 2008 RO Exam Rev FINAL

58.

Given the following:

The crew entered FRP-C.1, Response to Inadequate Core Cooling, with the

followinq conditions present:

Loss of Offsite has occurred

Core Exit temperature is 737 degrees F

RCS pressure is 1650 psig

RVLIS is 36%

Which ONE of the following describes the condition of the RCS and the actions

required in response to this condition?

A. Saturated, heat transfer is degraded;

Establish an RCSVent path to lower pressure and temperature

B. Saturated, heat transfer isin jeopardy;

Reinitiate High Pressure Safety Injection to restore core cooling

C. Superheated, heat transfer is degraded;

Establish an RCS Vent path to lower pressure and temperature

D. Superheated, heat transfer is in jeopardy;

Reinitiate High Pressure Safety Injection to restore core cooling

Thursday, March 20,2008 10:35:11 AM 47

Harris 2008 RO Exam Rev FINAL

59.

Given the following:

The plant is operating at 55% power.

The following annunciator is received in the Control Room:

APP-ALB-002-7-2, SERV WTR PUMPS DISCHARGE LOW PRESS

The RO notes that Cooling Tower Basin Level is decreasing rapidly.

Service Water header pressure is 45 psig and lowering.

One minute "later, Service Water header pressure is 25 psig and continues to

lower.

CTMU cannot maintain Cooling Tower Basin level.

The crew enters AOP-022, Loss of Service Water and completes the immediate

actions.

APP-ALB-002-7-2 is still in and the Cooling Tower Basin Level continues to

decrease rapidly.

RAB Operator reports that a large volume of water is gushing from overhead

piping in the vicinity of 1SW-276, Headers A & B Return To Normal SW Header

valve. The area is inaccessible.

All automatic plant systems have functioned as designed.

Which ONE of the following describes the location of the leak, and the action required?

A. Unisolable leak located in the Normal Service Water System;

Trip the reactor and go to PATH-1.

B. Unisolable leak located in the Emergency Service Water System;

Trip the reactor and go toPATH-1.

C. Isolable leak located in the Normal Service Water System;

Ensure NSW is properly aligned to equipment listed in AOP-022, Attachment 1.

D. Isolable leak located in the Emergency Service Water System;

Ensure ESW is properly aligned to equipment listed in AOP-022, Attachment 1.

Thursday, March 20, 2008 10:35:11 AM 48

Harris 2008 RO Exam Rev FINAL

60.

Which ONE of the following describes the operation of Service Air Header Isolation

Valve, 1SA-506?

A. Closes automatically when Instrument Air header pressure decreases below 75

psig;

Automatically reopens when pressure increases above 79 psig.

B. Closes automatically when Instrument Air header pressure decreases below 75

psig;

Must bemanually reopened when pressure increases above 79 psig.

C. Closes automatically when Instrument Air header pressure decreases below 90

psig;

Automatically reopens when pressure increases above 94 psig.

D. Closes automatically when Instrument Air header pressure decreases below 90

psig;

Must be manually reopened when pressure increases above 94 psig.

Thursday, March 20, 200810:35: 12 AM 49

Harris 2008 RO Exam Rev FINAL

61.

Given the following:

The plant is at 100% power.

An inadvertent Containment Spray actuation has occurred on Train "A".

Train "A" Containment Spray has been secured.

Containment pressure indicates (-)2.4 inches H20.

Which ONE of the following describes how Containment pressure will be restored to

within limits?

A. Containment Vacuum Relief system will operate to restore containment pressure to

-1.5 inches H20. No other actions are required.

B. Containment Vacuum Relief system will operate to restore containment pressure to

-1.5 inches H20. Containment purge operation is then required to restore to -1.0

inches H20.

C. Containment Vacuum Relief system will operate to restore containment pressure to

-1.0 inches H20. No other actions are required.

D. Containment Vacuum Relief system will operate to restore containment pressure to

-1.0 inches H20. Containment purge operation is then required to restore to -0.5

inches H20.

Thursday, March 20,200810:35:12 AM 50

Harris 2008 RO Exam Rev FINAL

62.

The plant is at 100% pm'o'ef:' f .

'3JZI 10K

r-I'

I 1'\.<2-:- ? I A~T.

e,

'

W~ ~A- f co '0 '? 0 ~

t\l'..\-\-.... ~o Q.~lP~ ev+ a~ s~r(-e~

The operating crew has entered EPP-013, LOCA Outside Containment due to MCB

indications.

Which ONE of the following describes the leak location that would be isolated first in

accordance with EPP-013, LOCA Outside Containment, and the method for

confirmation of leak isolation?

A. Excess Letdown Heat Exchanger;

PZR level rising.

B. Excess Letdown Heat Exchanger;

RCS pressure rising.

C. RHR Heat Exchanger;

PZR level rising.

D. RHR Heat Exchanger;

RCS pressure rising

Thursday, March 20, 200810:35:12 AM 51

Harris 2008 RO Exam Rev FINAL

63.

Given the following:

The reactor was tripped on simultaneous loss of the Main Feedwater Pumps.

All AFW was subsequently lost.

RCS Bleed and Feed is in progress in accordance with FRP-H.1, RESPONSE

TO LOSS OF SECONDARY HEAT SINK.

Core Exit Thermocouples have stabilized at an average of 595 of.

Main Feedwater Pump "A" has been started.

Containment pressure is 1.0 psig and stable.

Which ONE of the following describes the method and rate of establishing feedwater

flow?

A. Feed one Steam Generator at the MINIMUM controllable rate until a SG WIDE

range level is >15% using the respective Feedwater Control Bypass Valve.

B. Feed one Steam Generator at the MAXIMUM rate until a SGNARROW range level

is >250/0 using the respective Feedwater Control Bypass Valve.

C. Feed all Steam Generators at the MINIMUM controllable rate until a SG WIDE

range level is >.150/0 using the Feedwater Control Valves.

D. Feed all Steam Generators at the MAXIMUM rate until aSG NARROW range level

is >250/0 using the Feedwater Control Valves.

64.

Given the foUowing:

A reactor trip and loss of off-site power have occurred.

The crew is performing a cooldown using EPP-007,NaturaICirculation With

Steam Void in Vessel (Without RVLIS).

Off-Site power has been restored.

Preparations are being madeto start an RCP.

Which ONE of the following describes the minimum PZRlevel required for RCP restart

in accordance with EPP-007, and the reason for the level?

A. 25%to ensure minimum inventory for adequate pressure control.

B. 65% to' ensure minimum inventory for adequate pressure control.

C. 250/0 to ensure adequate volume for collapsing the void

D. 650/0 to ensure adequate volume for collapsing the void

Thursday, March 20, 2008 10:35: 12 AM 52

Harris 2008 ROExam Rev FINAL

A. TominimizeRCS leakage;

Depressurize the RCS to achieve RCS subcooling between 10°F and 20°F [40°F

and 50°F];

. B. To ensure SI Accumulator injection;

Depressurize the RCSto achieve RCS subcooling between 10°F and 20°F [40°F

and 50°F];

C. To minimizeRCS leakage;

Depressurize the RCSto maintain RCS subcooling just above lOaF [100°F];

D. To ensureSI Accumulator injection;

Depressurize theRCS to maintain RCS subcooling just above 70°F [100°F];

Thursday, March 20,2008 10:35:12 AM 53

Harris 2008 RO Exam Rev FINAL

66.

Given the following:

You are assigned as the RO on day shift.

You have been called for Fitness for Duty screening.

You must leave the Control Room for approximately 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

TheSSO has given permission and directed no additional actions are required

beyond those stated in OMM-002, Shift Turnover Package.

lAW OMM-002, which ONE of the following is the MINIMUM required for the shift

relief?

Note:

(Attachment 14, Documentation of Short Term Assumption of Duties)

(Attachment 5, Control Operator Shift Turnover Checklist)

A. Oral turnover to the remaining Board Operator. Both watchstanders Initial

Attachment 14. No log entry required.

B. Oral turnover to the remaining Board Operator. Both watchstanders Initial

Attachment 14 and document relief for greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in the Control Operator

log.

C. Perform a turnover using Attachment 5. Both watchstanders Initial Attachment 5.

No log entry required.

D. Perform a turnover using Attachment 5. Enterthe information in the Control

Operators log, and sign the log over.

Thursday, March 20,2008 10:35:12 AM 54

Harris 2008 RO Exam Rev FINAL

67.

Given the following:

A power increase is in progress in accordance with GP-005, Power Operation.

Average Power Range Nls indicate 400/0 power.

Main Turbine load indicates 35% power.

Average Loop DeltaT indicates 420/0 power.

Which ONE of the following describes the actions required in accordance with

GP-005?

A. Power must be reduced less than 30% by all indications and a calorimetric

performed to determine actual power.

B. Power increase should be stopped and a calorimetric must be performed to

determine actual power.

C. Power increase should be stopped and the PRNls adjusted to match turbine power.

D. Power increase may continue using turbine power and no further action is required

unless turbine power and averagePRNls deviate by 50/0 or greater.

68.

Which ONE of the following activities is considered ACCEPTABLE preconditioning of

equipment related. to performance of a surveillance on that equipment?

A. Lubrication of a valve stem prior to each scheduled testing of the valve.

B. Periodic or occasionalventing of pumps prior to testing, not associated with the

surveillance being performed.

C. Adjusting the bolt torque on a valve collar prior to stroke time testing of the valve.

D. Operation of a pump shortly before a test, if a situation could be avoided to operate

the pump while maintaining plant and personnel safety.

Thursday, March 20, 2008 10:35:12 AM 55

Harris 2008RO Exam Rev FINAL

69.

Given the following:

The unit is in Mode 6.

Refueling operations are in progress.

The 30th fuelassembly is being loaded into the core.

Current Boron Concentration is 2450 ppm.

According to GP-009, Refueling Cavity Fill, Refueling, and Drain of the Refueling

Cavity, Modes 5-6-5, which ONE of the following would require fuel loading operations

to be stopped immediately?

A. Communications is lost between Containment and the Control Room.

B. Water in the Spent Fuel Pool in not clear enough to view the Fuel top Nozzles

without supplemental lighting.

C. Boron concentration drops by 10 ppm as determined by two successive samples of

Reactor Coolant.

D. An unanticipated rise in count rate by a factor of two occurs on 1 of 2 operable

Source Range channels during any single loading step.

Thursday, March 20, 2008 10:35:12 AM 56

Harris 2008RO Exam Rev FINAL

70.

Given the following conditions at a work site:

Airborne activity - 5>DAC

Radiation level- 40 mrem/hr.

Radiation level with shielding - 20 mrem/hr.

Time to conduct task WITH respirator - 40 minutes.

Time to conduct task WITHOUT respirator- 30 minutes.

Assumptions:

The airborne dose with a respirator will be zero.

A dose rate of 40 mrem/hr will be received while placing the shieldinq. Assume

no benefit from shielding during placement.

All tasks will performed by one worker.

Shielding can be placed in 15 minutes with or without a respirator.

The shielding will not ~e removed.

Which ONE of the following would result in thelowest whole body dose?

A. Conduct task WITHOUT respirator or shielding.

B. Conduct task WITH respirator and WITHOUT shielding.

C. Place shielding while wearing respirator and conduct task' WITH respirator.

D. Place shielding while wearing respirator and conduct task WITHOUT respirator.

Thursday, March 20, 2008 10:35:12 AM 57

Harris 2008RO Exam Rev FINAL

71.

Per DOS-NGGC-0004, Administrative Dose Limits, which ONE of the following

describes the annual Progress Energy dose limit and the MINIMUM authorization

required for an individual to exceed that limit?

A. 2000 mrem;

Superintendent - Radiation Protection

B. 2000mrem;

Site Vice President

C. 4000 mrem;

Superintendent - Radiation Protection

D. 4000mrem;

Site Vice President

Thursday, March 20, 200810:35:12 AM 58

Harris 2008 RO Exam Rev FINAL

72.

Initial Conditions:

The unit is at1 00% power.

Current Conditions:

The following alarm is received:

ALB-001-7-1, ACCUMULATOR TANK A HI-LO PRESSURE

The RO reports the following indications:

Cold Leg Accumulator "A" pressure is 650psig and slowly increasing

Cold Leg Accumulator "A" level is 75 % and slowly' increasing

Which one of the following is the action required lAW the appropriate Annunciator

Plant Procedure and the OPERABILITY of the "A" Cold Leg Accumulator (CLA)?

A. Drain "A" CLA to lower pressure;

CLA "A" is INOPERABLE

B. Verify Nitrogen to the accumulators is isolated and vent excess accumulator

pressure;

CLA "A" is INOPERABLE

C. Drain "A" CLA to lower pressure;

CLA "A" is OPERABLE

D. Verify Nitrogen to the accumulators isisolated*andvent excess accumulator

pressure;

CLA "A'! is OPERABLE

Thursday, March 20,2008 10:35:13AM 59

Harris 2008 RO Exam Rev FINAL

73.

Given the following:

At 1302, a steam generator tube leak is identified.

At 1318,a plant shutdown is commenced due to exceeding TS leakage limits.

At 1319, an Unusual Event is declared by the Site Emergency Coordinator.

(SEC)

At 1321 , a reactor trip occurs.

At 1327, the crew identifiesSG "A" as the ruptured SG.

At 1330, an ALERT is declared by the SEC.

Which ONE of the following describes the latest time that the initial notification to

State/County officials AND the NRC is due?

State/County NRC

A. 1334 1334

B. 1334 1419

C. 1345 1419

D. 1345 1430

Thursday, March 20,2008 10:35:13 AM 60

Harris 2008 RO Exam Rev FINAL

74.

Given the following:

One Shutdown Bank-A, Group 2 Rod has dropped into the core.

The crew is recovering the dropped rod.

ALB-13-7-1, ROD CONT SYSTEM URGENT FAILURE is received.

Which ONE of the following describes the reason for the alarm and the plant

response?

A. Withdrawing the rod while the remaining Group 2 Lift Coils are deenergized.

Rod withdrawal is blocked until the alarm is reset.

B. Initiation of an "out" signal to SO Bank "A" Rods, and its Group 1 rods do not move.

Rod withdrawal is blocked until the alarm is reset.

C. Withdrawing the rod while the remaining Group 2 Lift Coils are deenergized.

Rod withdrawal is unaffected and recovery may continue.

O. Initiation of an "out" signal to SO Bank "A" Rods and its Group 1 rods do not move.

Rod withdrawal is unaffected and recovery may continue.

Thursday, March 20, 200810:35:13 AM 61

Harris 2008 RO Exam Rev FINAL

75.

Given the following:

The Unit has experiencedaSBLOCA.

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

All RCPs are running.

RCS pressure is 1690 psig.

AnRCS cooldown has been initiated by.dumping steam to the atmosphere.

Which ONE of the following describes the required RC.P configuration 'lAW with

EPP-QOg, and the basis for this configuration?

A. All RCPs shouldbe stopped;

minimize ReS inventory loss when' the break uncovers

B. One RCPshould be stopped;

produces effective heat transfer,provides boron mixing for RHR operations, and

provides RCS pressure control

C. All RCPs should be left running;

ensures symmetricheattransfer to the S/Gs, aids in RCS pressure control, and

prevents steam voiding in the Reactor vessel head

D. Two RCPs should be stopped;

minimizes RC.Sheat input and still produces effective heat transfer and RCS

pressure control

You have completed the test!

Thursday, March 20, 2008 10:35:13 AM 62

Harris 2008*301 RO Initial License Examination References

1. Steam Tables

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