Text

2009-03-Final Written Exam - Site-Specific RO and SRO Written Examinations
	ML091030679
Person / Time
Site:	Fort Calhoun
Issue date:	03/27/2009
From:	; NRC Region 4
To:	;
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l ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission l Site-Specific RO Written Examination Applicant Information Name:

Date: 03/27/2009 Facility/Unit: Fort Calhoun l Region: I II III IV X Reactor Type: W CE X BW GE l

Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet l on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 __________ Points Applicants Score __________ Points Applicants Grade __________ Percent ES-401, Page 30 of 33

2009 FORT CALHOUN RO EXAM (1)

A reactor trip has just occurred and the Standard Post Trip Actions are being performed in accordance with EOP-00, STANDARD POST TRIP ACTIONS.

Which of the following parameters requires you to take contingency actions?

A. All trippable control element assemblies are fully inserted except for B-15. All non-trippable control element assemblies are fully withdrawn.

B. Instrument air pressure is 85 psig and stable.

C. Both steam generator wide range levels are 85% and stable.

D. Pressurizer pressure is 2060 psia and increasing.

page 1

2009 FORT CALHOUN RO EXAM (2)

Given the following plant conditions:

A loss of load event resulted in a high pressure reactor trip Both of the Power-Operated Relief Valves (PORVs) opened One of the PORVs failed to close when pressurizer pressure lowered below it's setpoint Power was not available to the open PORV's block valve during performance of Standard Post Trip Actions EOP-03, LOSS OF COOLANT ACCIDENT, was entered Power has now been restored to the open PORV's block valve The PORV block valve associated with the open PORV should NOT be closed if:

A. Pressurizer level is at 100%.

B. Pressurizer pressure is 2010 psia.

C. Reactor vessel level is 83%.

D. RCS subcooling is 0°F.

page 2

2009 FORT CALHOUN RO EXAM (3)

Given the following plant conditions:

The plant is in hot shutdown Charging and letdown were isolated in response to RCS leakage Isolation of charging and letdown terminated the RCS leakage Pressurizer heaters have just lost power due to the low level cutout All Reactor Coolant Pumps are operating as designed How much time do the operators have to reestablish charging flow to the RCS before the pressurizer empties assuming RCS cold leg temperature stays steady at 532°F?

A. 3.5 - 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months B. 5.0 - 6.0 hours0 days 0 hours 0 weeks 0 months C. 6.5 - 7.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months D. 8.0 - 9.0 hours0 days 0 hours 0 weeks 0 months page 3

2009 FORT CALHOUN RO EXAM (4)

The following plant conditions exist during a RCS heatup:

T-cold is 410°F.

T-hot is 411°F.

Core Exit Thermocouples are reading between 410°F and 415°F.

Pressurizer pressure indicates 955 psia.

No operations are in effect that could cause a RCS dilution.

Which one of the following Reactor Coolant Pump operating conditions is NOT allowed by the requirements of T.S. 2.1.1?

A. RC-3A and RC-3C are operable, but not operating. RC-3B and RC-3D are not operable. RC-3A has been shutdown for 35 minutes.

B. RC-3A is operating. RC-3C is operable, but not operating. RC-3B and RC-3D are not operable. RC-3C has been shutdown for 75 minutes.

C. RC-3B and RC-3D are operable, but not operating. RC-3A and RC-3C are not operable. RC-3D has been shutdown for 35 minutes.

D. RC-3C is operating. RC-3D is operable, but not operating. RC-3A and RC-3B are not operable. RC-3D has been shutdown for 75 minutes.

page 4

2009 FORT CALHOUN RO EXAM (5)

Given the following plant conditions:

RCS temperature is 105°F Pressurizer pressure is 15 psia Shutdown Cooling was in operation per OI-SC-1, SHUTDOWN COOLING INITIATION LPSI pump, SI-1A, was running The pressurizer manway is removed Offsite power has just been lost The Emergency Diesel Generators operate as designed What action (if any) should you perform after the Emergency Diesel Generators start and their output breakers close?

A. Manually restart the LPSI pumps.

B. Un-isolate the LPSI system from the RCS and restart the LPSI pumps.

C. No action is necessary; the Emergency Diesel Generators will pick up the LPSI pumps as dead bus loads.

D. No action is necessary; the sequencers will restart LPSI pumps within one minute of the breaker closing.

page 5

2009 FORT CALHOUN RO EXAM (6)

The following plant conditions exist:

The plant was operating at 65% power with all systems are aligned for normal operation The "CC WATER SURGE TANK AC-2 HI OR LO LEVEL" alarm was received The Auxiliary Building Operator reported that he heard a loud rumbling noise from the operating CCW pump, AC-3A You observe fluctuating current and discharge pressure for AC-3A The CCW surge tank level is 8 inches and lowering The reactor was manually tripped two minutes after the AUXILIARY COOLANT FROM CRDM FLOW LO alarm was received What action should be performed in addition to Standard Post Trip Actions in accordance with AOP-11?

A. Trip one RCP in each loop within 3 minutes. Trip the remaining RCPs if high bearing temperature alarms are received.

B. Trip one RCP in each loop within 5 minutes. Trip the remaining RCPs if high bearing temperature alarms are received.

C. Shutdown all RCP's within 3 minutes.

D. Shutdown all RCP's within 5 minutes.

page 6

2009 FORT CALHOUN RO EXAM (7)

Given the following sequence of events:

The plant was operating at full power Pressurizer level channel "Y" was selected as the controlling channel LT-101Y failed Letdown flow increased Pressurizer level lowered to 31%

Pressurizer pressure lowered to 1920 psia All pressurizer heaters turned off.

The Operator then took manual control of charging and letdown and restored level to 60%

The operator then selected channel "X" as the controlling channel Pressurizer pressure control remained in automatic Current plant conditions are:

Pressurizer pressure and level are both stable with level at 60% and pressure at 1950 psia Pressurizer steam temperature indicates 632°F Pressurizer liquid temperature indicates 620°F How will pressurizer pressure respond?

A. Pressurizer pressure will steadily increase to 2100 psia.

B. Pressurizer pressure will remain at approximately1950 psia until the Level Control Bistables, LC-101-1 and LC-101-2, located behind CB-1/2/3 are reset.

C. Pressurizer pressure will remain at approximately1950 psia until Channel "X" is selected on PZR Heater Cutout Channel Select Switch, HC-101-1.

D. Pressurizer pressure will remain at approximately1950 psia until the water in the pressurizer reaches saturation temperature.

page 7

2009 FORT CALHOUN RO EXAM (8)

The plant experiences an ATWS event where both the reactor and turbine failed to trip.

What action does EOP-00 direct you to perform to limit reactor power?

A. Trip all Reactor Coolant Pumps.

B. Transfer charging pump suction to the SIRWT.

C. Insert the non-trippable CEAs.

D. Close the MSIVs.

page 8

2009 FORT CALHOUN RO EXAM (9)

Given the following plant conditions:

The plant is operating at 20% power A high radiation alarm has been received on RM-054B Counts are rising RM-057 but below the alarm setpoint Charging flow is 40 gpm Letdown flow is 30 gpm Pressurizer pressure is 2080 psia and steady Pressurizer level is 48% and steady The are no containment radiation alarms Containment pressure is steady Containment sump level is steady Which one of the following actions will occur automatically with these plant conditions?

A. Blowdown flow from Steam Generator, RC-2B will be isolated. Blowdown flow will continue from RC-2A.

B. Blowdown flow from both Steam Generators will be isolated.

C. RCV-978, 6th Stage Extraction Isolation Valve, will close.

D. A Ventilation Isolation Actuation Signal (VIAS) will be generated page 9

2009 FORT CALHOUN RO EXAM (10)

Given the following plant conditions:

A tube has ruptured in Steam Generator, RC-2A The steam line from Steam Generator, RC-2B, has ruptured in room 81 EOP-00, STANDARD POST TRIP ACTIONS, has been completed EOP-20, FUNCTIONAL RECOVERY PROCEDURE, has been entered In mitigating this event, which steam generator(s), if any, should be isolated?

A. Neither Steam Generator should be isolated.

B. Only RC-2A should be isolated.

C. Only RC-2B should be isolated.

D. Both steam generators should be isolated.

page 10

2009 FORT CALHOUN RO EXAM (11)

A break on the feedwater line to Steam Generator, RC-2B, inside containment has occurred.

The following plant conditions exist:

SGIS has actuated Heat removal has been established using Steam Generator, RC-2A.

AFW Pump, FW-6, is feeding Steam Generator RC-2A and is the only available AFW pump.

Steam Generator, RC-2B, has dried out.

No Reactor Coolant Pumps are running.

In accordance with EOP-05, UNCONTROLLED HEAT EXTRACTION, which one of the following actions should be taken and for what reason?

A. AFW flow should be established to RC-2B to help promote natural circulation flow in both RCS loops.

B. AFW flow should be established to RC-2B to increase decay heat removal.

C. AFW flow should NOT be established to RC-2B because it would result in a positive reactivity addition.

D. AFW flow should NOT be established to RC-2B because FW-6 does not have the capacity to feed both S/Gs simultaneously.

page 11

2009 FORT CALHOUN RO EXAM (12)

The following plant conditions exist:

A loss of 161 KV to the plant resulted in fast transfer of vital buses 1A3 and 1A4 to 345 KV This was followed by a loss of load that resulted in a reactor trip Both D/Gs failed to start due to a common mode failure resulting in a station blackout Breakers 1A11, 1A13, 1A22 and 1A24 are open The generator field breaker is closed The Kirk key for disconnect, DS-T1, has been inserted and turned he isolated phase bus duct cooling units are off All Main Steam Stop Valves are closed Both DC buses are energized Which one of the following actions must be taken to allow disconnect, DS-T1, to be opened from CB-20 prior to restoring 345 KV power to buses 1A3 and 1A4?

A. Breakers 1A13 and 1A24 must be closed.

B. The generator field breaker must be opened.

C. The Kirk key Interlock must be disengaged.

D. An isolated phase bus duct cooling unit must be started.

page 12

2009 FORT CALHOUN RO EXAM (13)

The plant tripped from 100% power following a loss of all offsite power. The following conditions exist:

RCS pressure is 2000 psia.

Pressurizer level is 40%.

Steam Generator Pressures are 900 psia.

Steam Generator Wide Range levels are 40%.

Hot leg temperatures are 575F.

Cold leg temperatures are 532F.

Which of the following actions would be most effective in enhancing natural circulation?

A. Raise RCS pressure.

B. Raise Pressurizer level.

C. Raise Steam Generator pressures.

D. Raise Steam Generator levels.

page 13

2009 FORT CALHOUN RO EXAM (14)

Given the following plant conditions:

The plant was operating at full power Power was lost to Instrument bus AI-40A AOP-16, LOSS OF INSTRUMENT BUS POWER, was entered AOP-16,Section II, "Loss of Instrument Bus AI-40A", Step 14 states "Consider closing BOTH of the PORV (Power-Operated Relief Valves) Block Valves" What is the purpose of this step?

A. An additional vital instrument bus failure will result in opening ONE of the PORVs.

B. An additional vital instrument bus failure will result in opening BOTH of the PORVs.

C. An additional vital instrument bus failure will result in the inability to close ONE of the PORV Block Valves.

D. An additional vital instrument bus failure will result in the inability to close BOTH of the PORV Block Valves.

page 14

2009 FORT CALHOUN RO EXAM (15)

The following plant indications were noted following a reactor trip.

Bus Power Failure DC Distribution Panel 1 Light is off.

Bus Power Failure DC Distribution Panel 2 Light is on.

The DC BUS#1 LOW VOLT annunciator is in alarm The 43/FW Switch is in the OFF position.

All NORMAL/OVERRIDE switches on AI-66A are in NORMAL.

FW-6 can NOT be started from CB-10,11.

In accordance with AOP-16, LOSS OF INSTRUMENT BUS POWER, which one of the following actions is required to be able to start FW-6?

A. Place the 43/FW Switch in the AUTO position.

B. Start FW-6 from AI-66A after placing the NORMAL/OVERRIDE switches on AI-66A to OVERRIDE.

C. Use the 1A1-1A3 Emergency MTS button, PB2-1A1-1A3 PBS, to switch to the emergency DC source.

D. Start FW-6 from the Alternate Shutdown Panel, AI-179.

page 15

2009 FORT CALHOUN RO EXAM (16)

One of the two 20 inch underground Raw Water headers from the intake structure to the auxiliary building completely ruptured.

How does isolating the ruptured header affect the ability to provide cooling to the RW/CCW heat exchangers?

A. Raw Water can be supplied to all of the RW/CCW heat exchangers but only two of the Raw Water Pumps can be used.

B. Raw Water can only be supplied to two of the RW/CCW heat exchangers and only two of the Raw Water Pumps can be used.

C. Raw Water can be supplied to all of the RW/CCW heat exchangers but only three of the Raw Water Pumps can be used.

D. Raw Water can only be supplied to three of the RW/CCW heat exchangers and only three of the Raw Water Pumps can be used.

page 16

2009 FORT CALHOUN RO EXAM (17)

The reactor has been manually tripped following a sudden loss of instrument air pressure.

According to AOP-17, Loss of Instrument Air, which of the following actions should be taken to prevent RCS cooldown?

A. Close FCV-1101 and FCV-1102 using DCS.

B. Maximize S/G blowdown flow.

C. Initiate a Steam Generator Isolation Signal (SGIS).

D. Manually trip all Main Feedwater Pumps.

page 17

2009 FORT CALHOUN RO EXAM (18)

Given the following plant conditions:

The plant is operating at 10% reactor power A loss of stator water cooling occurred Attempts to restore stator water cooling have been unsuccessful Stator cooling water outlet temperature has risen to 83°C What action is required by AOP-27, GENERATOR MALFUNCTIONS?

A. Manually trip the reactor.

B. Manually trip the turbine.

C. Manually trip the main generator output breakers.

D. Manually open the main generator field breaker.

page 18

2009 FORT CALHOUN RO EXAM (19)

Given the following plant conditions:

A reactor startup is being performed using OP-2A, PLANT STARTUP The brake on one of regulating group 2 CEAs fails to release The CEAs are being withdrawn in the manual sequential mode.

When will a SCEAPIS (DCS) rod block signal be generated?

A. When any CEA in group 2 is withdrawn 8 inches above the stuck CEA.

B. When any CEA in group 2 is withdrawn 4 inches above the stuck CEA.

C. When any CEA in group 1 reaches the upper rod stop.

D. When any CEA in group 3 begins to withdraw.

page 19

2009 FORT CALHOUN RO EXAM (20)

Given the following plant conditions:

A power increase is in progress per OP-4, LOAD CHANGE AND NORMMAL POWER OPERATION The reactor is at 80% power Group 4 CEAs are at 52 inches All other CEAs are fully withdrawn.

Using the attached PDIL curve, determine what action must be taken as a result of these conditions?

A. Immediately commence emergency boration.

B. Withdraw group 4 CEAs to above the short term insertion limit.

C. Withdraw group 4 CEAs until proper group overlap is achieved.

D. Place the plant in hot shutdown within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

page 20

2009 FORT CALHOUN RO EXAM (21)

Given the following:

The AI-149 FIRE DETECTION ALARM OR TROUBLE alarm was received The Control Room Fire Detection Computer, PC-66, indicates that multiple detectors in the Cable Spread Room are in alarm The EONT was dispatched and reports that Halon is being discharged into the Cable Spread Room In accordance with AOP-06, FIRE EMERGENCY, what action should be taken by the Control Room Operators?

A. Trip the reactor, open clutch power supply breakers, close the PORV block valves and evacuate the Control Room.

B. Trip the reactor, close the PORV block valves, start both Fire pumps, FP-1A and FP-1B, and evacuate the Control Room.

C. Trip the reactor, open clutch power supply breakers, close the PORV block valves and place the Control Room HVAC in Recirculation Mode.

D. Close the PORV block valves, start both Fire pumps, FP-1A and FP-1B, and place the Control Room HVAC in Recirculation Mode.

page 21

2009 FORT CALHOUN RO EXAM (22)

The following power indications are observed 10 minutes after a reactor trip:

All four WR NI Channels are indicating 3 x 10-3% Power and lowering.

All four WR NI Channels are indicating a startup rate of -0.1 DPM and steady.

All four Power Range NI Channels are indicating 0% power and steady.

All four Delta-T Power Channels are indicating 2% power and lowering.

A miscalibration of which of the following could cause these indications?

Assume trip from full power.

A. Wide Range NI power indication channels.

B. Wide Range NI startup rate channels.

C. Power Range NI channels.

D. Delta-T Power Channels.

page 22

2009 FORT CALHOUN RO EXAM (23)

Radioactive liquid that leaks inside containment will collect in the containment sump.

The containment sump pumps will normally pump this radioactive water to the:

A. Reactor Coolant Drain Tank.

B. Waste Holdup Tanks.

C. Waste Monitor Tanks.

D. Spent Regenerant Tanks.

page 23

2009 FORT CALHOUN RO EXAM (24)

The radioactive gases released following a waste gas decay tank rupture will consist mostly of isotopes of:

A. Xenon and Krypton.

B. Iodine and Cesium.

C. Tritium and Carbon.

D. Argon and Neon.

page 24

2009 FORT CALHOUN RO EXAM (25)

Given the following sequence of events:

Condenser vacuum was lost The turbine and reactor tripped Immediately following the trip, a small LOCA occurred inside containment PPLS and CPHS have actuated All HPSI pumps failed to start RCS pressure is steady at 1000 psia Reactor Vessel Level is at 43%

Which of the following valves can be used by the Balance of Plant Operator to immediately begin a RCS cooldown in accordance with EOP-03?

A. Steam Dump Valves, TCV-909-1,2,3,4.

B. Steam Bypass Valve, PCV-910.

C. Atmospheric Dump Valve, HCV-1040.

D. Air Assisted Main Steam Safety Valves, MS-291, MS-292.

page 25

2009 FORT CALHOUN RO EXAM (26)

FC-214, REACTOR COOLANT DAILY

SUMMARY

REPORT, contains the following information:

Fuel Reliability Indicator (FRI): 1.1 x 10-4 uCi/gm Dose Equivalent Iodine: 0.8 uCi/gm Xe-133 Activity: 2.8 uCi/gm RCS Total Activity: 5.5 uCi/gm E-bar: 0.68 Mev Which one of the following actions is required?

A. AOP-09, HIGH RADIOACTIVITY, must be entered due to the Fuel Reliability Indicator.

B. AOP-09, HIGH RADIOACTIVITY, must be entered due to the Xe-133 Activity C. AOP-21, REACTOR COOLANT SYSTEM HIGH ACTIVITY, must be entered due to Dose Equivalent Iodine.

D. AOP-21, REACTOR COOLANT SYSTEM HIGH ACTIVITY, must be entered due to the RCS Total Activity.

page 26

2009 FORT CALHOUN RO EXAM (27)

The "REACTOR VESSEL FLANGE LEAK" alarm was received due to leakage past the Reactor Vessel Flange inner O-Ring. Actions were taken to reset the alarm condition.

What one of the following parameters would cause an alarm if leakage occurs past the outer O-Ring?

A. Increasing pressure.

B. Increasing temperature.

C. Decreasing pressure.

D. Decreasing temperature.

page 27

2009 FORT CALHOUN RO EXAM (28)

Given the following:

You have been directed to shutdown Reactor Coolant Pump, RC-3A in accordance with OI-RC-9 You notice the Control Switch for Oil Lift Pump, RC-3A-1, is in the "AFTER START" position and that the Oil Lift Pump is not operating Which one of the following actions, if any, is required to ensure proper lubrication of the RCP bearings?

A. Do not trip RCP, RC-3A unless its' Oil Lift Pump is running.

B. If the Oil Lift Pump does not start automatically after tripping RC-3A, then momentarily place the Oil Lift Pump Control Switch in the "STOP" position then back to the "START" position to reset it.

C. If the Oil Lift Pump does not start automatically after tripping RC-3A, then hold the Oil Lift Pump Control switch in the "START" position until the "ZERO SPEED" light comes on.

D. No action is required. The Oil Lift Pump is only needed when starting a Reactor Coolant Pump.

page 28

2009 FORT CALHOUN RO EXAM (29)

Given the following plant conditions:

Leakage through Power Operated Relief Valve (PORV), PCV-102-1, has been discovered The leaking PORV has been isolated by closing its block valve, HCV-151 HCV-151 also leaks through VCT makeup is in its normal alignment Assuming no operator action is taken, how will the VCT level control system first respond?

A. FCV-269, FCV-269X and FCV-269Y will open automatically to supply water to the VCT at the neutral blend boron concentration.

B. FCV-269, FCV-269X and FCV-269Y will open automatically to supply water to the charging pump suction at the neutral blend boron concentration.

C. LCV-218-3 will open and LCV-218-2 will close automatically to supply water to the VCT at the SIRWT boron concentration.

D. LCV-218-3 will open and LCV-218-2 will close automatically to supply water to the charging pump suction at the SIRWT boron concentration.

page 29

2009 FORT CALHOUN RO EXAM (30)

A plant shutdown and cooldown are being performed. One hour after placing shutdown cooling in service, the following plant indications are observed:

Pressurizer pressure and level are lowering.

Containment sump level is steady.

CCW surge tank level and pressure are increasing.

Steam Generator levels are steady.

Steam Generator pressures are lowering slowly.

RM-053 is in alarm.

All other process radiation monitors are reading normal.

Which one of the following could cause these indications?

A. A raw water/CCW heat exchanger tube leak B. A regenerative heat exchanger tube leak.

C. A shutdown cooling heat exchanger tube leak.

D. A steam generator tube leak.

page 30

2009 FORT CALHOUN RO EXAM (31)

Given the following:

EOP/AOP Attachment 7, "SDC WITH RAS" has been entered following a Loss of Coolant Accident A RCS cooldown is being conducted using shutdown cooling The RCS cold leg temperatures are currently 170°F.

What is the maximum allowable cooldown rate under these conditions?

A. 25°F/hr.

B. 50°F/hr.

C. 100°F/hr.

D. 200°F/hr.

page 31

2009 FORT CALHOUN RO EXAM (32)

The plant is operating at full power. HPSI pump, SI-2A, has been tagged out of service due to a breaker problem. Normal actions have been taken.

How does this affect the operability of the HPSI train associated with SI-2A per Technical Specifications?

A. The HPSI train is considered operable if SI-2B is operable.

B. The HPSI train is considered operable if SI-2C is operable.

C. One train of HPSI is inoperable, SI-2A must be made operable within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

D. One train of HPSI is inoperable, SI-2A must be made operable within 7 days.

page 32

2009 FORT CALHOUN RO EXAM (33)

How is a steam bubble formed in the pressurizer following a refueling outage per OP-2A, PLANT STARTUP?

A. With the pressurizer level at approximately 50%, pressurizer heaters are used to heat the water to saturation. Non-condensable gases are allowed to dissolve in the water.

B. With the pressurizer level at approximately 90%, pressurizer heaters are used to heat the water to saturation. Non-condensable gases are allowed to dissolve in the water.

C. With the pressurizer level at approximately 50%, pressurizer heaters are used to heat the water to saturation. Non-condensable gases are vented to the PQT or VCT using OI-CH-3, CHEMICAL AND VOLUME CONTROL SYSTEM NORMAL OPERATION OF VOLUME CONTROL TANK, Attachment 5 or 6.

D. With the pressurizer level at approximately 90%, pressurizer heaters are used to heat the water to saturation. Non-condensable gases are vented to the PQT or VCT using OI-CH-3, CHEMICAL AND VOLUME CONTROL SYSTEM NORMAL OPERATION OF VOLUME CONTROL TANK, Attachment 5 or 6.

page 33

2009 FORT CALHOUN RO EXAM (34)

Given the following plant conditions:

The plant is operating at 100% power.

Pressurizer Safety Valve, RC-142, has seat leakage.

Quench Tank temperature and level are rising.

Quench Tank pressure is 8 psig and increasing slowly.

Which one of the following automatic actions will occur assuming no operator actions are taken?

A. Quench Tank relief valve, RC-125, will open resulting in increasing containment pressure.

B. Quench Tank relief valve, RC-125, will open and relieve to the waste gas system.

C. Quench Tank vent valve, HCV-155, will open and vent to the containment vent header and the RCDT outlet containment isolation valve will close.

D. Quench Tank vent valve, HCV-155, will open and the Quench Tank rupture disk will rupture resulting in increasing containment pressure.

page 34

2009 FORT CALHOUN RO EXAM (35)

Given the following:

The CCW system is being started up in accordance with OI-CC-1 All pre-requisites have been met All CCW pumps are off.

What action will you direct the EONA to take before starting the first CCW pump, AC-3A?

A. Ensure CCW Surge tank pressure is greater than 60 psig.

B. Vent AC-3A using its casing vent valve.

C. Fully open the discharge valve for AC-3A.

D. Fully close the discharge valves for AC-3B and AC-3C.

page 35

2009 FORT CALHOUN RO EXAM (36)

Given the following:

plant transient resulted in valid SIAS and CIAS actuations COMPONENT COOLING WATER SYSTEM LOW PRESSURE alarm came in 40 seconds ago CCW Header Pressure, PI-499, indicates 118 psig HCV-438A/B/C/D are closed in automatic CCW Surge Tank Pressure indicates 41 psig All CCW Pumps are running Which one of the following conditions could cause these indications?

A. PI-499, CCW header pressure, has failed low.

B. CCW Pressure Switches, PCS-412 and PCS-413, have failed low.

C. PIC-2802, CCW Surge Tank Pressure indication, has failed low.

D. HCV-438A/B/C/D have inadvertently closed resulting in low CCW pressure to the RCPs.

page 36

2009 FORT CALHOUN RO EXAM (37)

Given the following plant conditions:

A Reactor Coolant System cooldown is in progress for a refueling outage S

hutdown cooling is in operation per OI-SC-1 R

CS temperature is 120°F R

CS pressure is 235 psia R

eactor Coolant Pumps, RC-3A and RC-3B, are operating.

P ressure is being controlled manually using Main pressurizer spray and heaters.

What actions should be taken before shutting down Reactor Coolant Pumps, RC-3A and RC-3B, in accordance with OI-RC-9?

A. RCS pressure should be lowered to less than 215 psia.

B. RCS temperature should be lowered to less than 110°F.

C. The RCS should be borated to the refueling boron concentration.

D. RCS pressure control using Auxiliary spray should be established.

page 37

2009 FORT CALHOUN RO EXAM (38)

Given the following plant conditions:

B us Power Failure DC Distribution Panel 1 Light is off D

C BUS#1 LOW VOLT annunciator is in alarm D

C Bus #1 voltage indicates 0 volts P

ower has been lost to the "A" DSS 86-Relay How will operation of the Diverse Scram System (DSS) be affected?

A. The DSS will initiate a reactor trip.

B. The DSS will go to a "1 of 3" trip logic.

C. The "A" DSS 86-Relay will not be capable of generating a reactor trip.

D. The DSS will not be capable of generating a reactor trip.

page 38

2009 FORT CALHOUN RO EXAM (39)

Given the following:

T he power supply to RPS Clutch Power Supply Breaker, CB-AB, will be transferred from Instrument Bus "B" to Instrument Bus "A".

nverter "A" is supplying power to Instrument Bus "A" and Swing Inverter, EE-8U, is supplying power to Instrument Bus "B".

Which one of the following actions will be taken before placing the Clutch Power Supply Transfer Switch, RPS/TS-AB, in the Instrument Bus A (#1) position in accordance with OI-EE-4?

A. Cross-tie Instrument Bus "A" to Instrument Bus "C".

B. Bypass Inverter "A".

C. Transfer Instrument Bus "B" supply to Inverter "B".

D. Bypass Swing Inverter 8-U.

page 39

2009 FORT CALHOUN RO EXAM (40)

Given the following:

The plant was operating at 50% power when a LOCA occured The reactor tripped automatically PPLS, CPHS, SIAS, CIAS, VIAS and SGIS all actuated The sequencers begin starting safeguards motors During the starting sequence bus 1A3 voltage and transformer T1A3 voltage decreased below the OPLS setpoint How will the OPLS relays respond and what action, if any, should be taken by the Operators to ensure safeguards equipment actuates?

A. OPLS will not actuate. Operators should trip both 86A/OPLS and 86B/OPLS.

B. 86A/OPLS will actuate. Operators should trip 86B/OPLS.

C. 86B/OPLS will actuate. Operators should trip 86A/OPLS.

D. 86A/OPLS and 86B/OPLS will both actuate. No operator action is required.

page 40

2009 FORT CALHOUN RO EXAM (41)

From where do the CEDM Cooling Fans, VA-2A and VA-2B, take suction?

A. Directly from the containment coolers.

B. From the seismic skirt area.

C. Directly from the containment atmosphere.

D. From the nuclear detector well cooling system.

page 41

2009 FORT CALHOUN RO EXAM (42)

Given the following:

E CCS actuation has occurred due to a PPLS E

OP-03, LOSS OF COOLANT ACCIDENT, has been entered S

tep 33 has been reached S

tep 33 says, "Verify that the Containment Sump level rises as the SIRWT level lowers."

S IRWT level is 95 inches and lowering C

ontainment sump level is low and not rising What action should be taken per EOP-03?

A. Minimize ECCS flow to the minimum required to remove decay heat.

B. Initiate containment spray to ensure adequate containment sump level.

C. Begin blended makeup to the SIRWT to increase SIRWT inventory.

D. Trip the LPSI pumps to reduce SIRWT depletion rate.

page 42

2009 FORT CALHOUN RO EXAM (43)

In order to maintain steam generator pressure below 1100 psia following a loss of load from 100% power, Technical Specifications require that _________ be operable in modes 1 and 2.

A. All 10 Main Steam Safety Valves.

B. 9 of 10 Main Steam Safety Valves.

C. 4 of 5 Main Steam Safety Valves on each Steam Generator.

D. 3 of 5 Main Steam Safety Valves on each Steam Generator.

page 43

2009 FORT CALHOUN RO EXAM (44)

Given the following plant conditions:

T he plant is operating at full power A

ll Feedwater Reg valves and Bypass valves are in AUTO on DCS T

he Bypass valves are closed B

oth DCS level controllers are in AUTO on DCS N

arrow range level in both Steam Generators is at 63%

How should the Feedwater Reg valves and Bypass valves respond to a reactor trip?

A. The Feedwater Reg valves will ramp closed. The Feedwater Bypass valves will initially open to 40-45% and control narrow range water level at 63%

B. The Feedwater Reg valves will ramp closed. The Feedwater Bypass valves will initially open to 40-45% and control narrow range water level at 35%

C. The Feedwater Reg valves will initially ramp down to 8% and control narrow range water level at 63%. The Feedwater Bypass valves will remain closed.

D. The Feedwater Reg valves will initially ramp down to 8% and control narrow range water level at 35%. The Feedwater Bypass valves will remain closed.

page 44

2009 FORT CALHOUN RO EXAM (45)

To prevent a loss of RCS heat removal following a total loss of feedwater, either AFW flow must be initiated or once-through-cooling must be established when:

A. Wide Range level in either S/G falls below 32%.

B. Wide Range levels in both S/G's fall below 32%.

C. An uncontrolled rise in RCS T-cold of 6°F.

D. An uncontrolled rise in RCS pressure of 50 psi.

page 45

2009 FORT CALHOUN RO EXAM (46)

Given the following plant conditions:

T he plant was operating at full power A

n electrical grid disturbance results in degraded grid voltage A

OP-31, 161 KV GRID MALFUNCTIONS, was entered T

he voltage on all 4160 V buses is less than the minimum required per AOP-31 T

he voltage on all 480 volt buses is less than the minimum required per AOP-31 T

he reactor was tripped and EOP-00, STANDARED POST TRIP ACTIONS, was entered What actions are directed by AOP-31 after tripping the reactor and entering EOP-00?

A. Trip all pumps fed by 4160 V buses and manually initiate a 480 volt load shed.

B. Trip all pumps fed by 4160 V buses, parallel Diesel Generators to buses 1A4 and 1A3 and open their respective feeder breakers.

C. Deenergize buses 1A4 and 1A3 by opening their respective feeder breakers and allowing the Diesel Generators to power the buses, manually initiate the sequencers to start required loads.

D. Deenergize buses 1A4 and 1A3 by opening their respective feeder breakers and allowing the Diesel Generators to power the buses, manually start required loads.

page 46

2009 FORT CALHOUN RO EXAM (47)

Given the following:

The plant was operating at full power The DC BUS #1 GROUND annunciator came into alarm The EONT has been dispatched to 125 VDC Bus 1 EE-8F You have been directed to check the DC Bus at AI-41A for indications of a ground in accordance with ARP-CB-20/A15.

Which one of the following is an indicator of a severe ground on 125V DC Bus #1 at AI-41A?

A. Both white lights will be brightly lit and one Ground Fault Voltmeter will indicate low voltage.

B. One white light will be brightly lit and one Ground Fault Voltmeter will indicate low voltage.

C. Both white lights will be brightly lit and both Ground Fault Voltmeters will indicate low voltage.

D. One white light will be brightly lit and both Ground Fault Voltmeters will indicate low voltage.

page 47

2009 FORT CALHOUN RO EXAM (48)

The timer on battery charger #1, EE-8C, is being used to place an equalizing charge on battery #1.

What voltage would be expected to be indicated on DC bus #1 during this operation and when the timer times out?

A. 133-137 volts dropping to 123-127 volts.

B. 138-142 volts dropping to 123-127 volts.

C. 133-137 volts dropping to 128-132 volts.

D. 138-142 volts dropping to 128-132 volts.

page 48

2009 FORT CALHOUN RO EXAM (49)

Given the following plant conditions:

A large break LOCA occurred in containment O

ffsite power was lost at the same time B

oth Diesel Generators started D

G-1's speed only increased to 700 rpm due to a problem with its governor How would the ECCS pumps normally powered by DG-1 be affected?

A. The output breaker from DG-1 would not close and there would be no power to the pumps.

B. The output breaker from DG-1 would close, but the sequencers would not close the individual pump breakers.

C. The output breaker from DG-1 would close and the sequencers would close the individual pump breakers, but the DG-1 output breaker would soon open due to an overcurrent condition.

D. The output breaker from DG-1 would close and the sequencers would close the individual pump breakers, but the pumps would run at reduced speed and flow.

page 49

2009 FORT CALHOUN RO EXAM (50)

Given the following plant conditions:

T he plant is operating at 90% power 10 months into the operating cycle Ion Exchanger, CH-8B, has just been placed into service L etdown temperature transmitter, TE-2897, has just been recalibrated A tmospheric dump valve, HCV-1040, was just unisolated N ew fluid has just been added to the EHC system P ower range NI power is rising slowly on all channels D elta T power is rising slowly on all channels A ll hot and cold leg temperatures are rising slowly What action should be taken based on these indications?

A. Bypass the ion exchangers using OI-CH-2.

B. Manually increase CCW flow through the letdown heat exchanger using OI-CH-2.

C. Isolate the atmospheric dump valve using OI-MS-1A.

D. Check the EHC fluid for air bubbles using OI-ST-12.

page 50

2009 FORT CALHOUN RO EXAM (51)

Given the following plant conditions:

T here is high activity in the RCS A

steam generator tube leak exists in RC-2B R

M-064 has been placed in service with the selector switch placed in the "auto" position The indicated radiation level on RM-064 will:

A. Read background radiation only.

B. Peg high and stay that way.

C. Alternate between high and low readings.

D. Slowly continue to rise.

page 51

2009 FORT CALHOUN RO EXAM (52)

Given the following conditions:

A steam line has ruptured inside containment T

he CCW surge tank has ruptured.

A ll other Engineered Safeguards Features are operating as designed R

iver level is 990 feet C

ontainment pressure is 40 psia C

ontainment temperature is 190°F Should Raw Water backup cooling be supplied to the Containment Coolers in accordance with AOP-11, LOSS OF COMPONENT COOLING WATER and why?

A. Yes, because both Containment temperature and pressure are high.

B. No, because they are not needed with Containment Spray operating.

C. No, because Containment temperature is too high.

D. No, because river level is too low.

page 52

2009 FORT CALHOUN RO EXAM (53)

Given the following plant conditions:

T he plant was operating at 100% power R

aw Water pumps, AC-10A and AC-10B were running A

Loss of Coolant Accident occurred coincident with a loss of offsite power D

iesel Generator, DG-2, failed to start Which Raw Water pumps will be running after sequencer operation?

A. AC-10A and AC-10B.

B. AC-10A and AC-10C.

C. AC-10B and AC-10D.

D. AC-10C and AC-10D.

page 53

2009 FORT CALHOUN RO EXAM (54)

Given the following plant conditions:

T he plant is operating at full power T

he PLANT AIR PRESS LO annunciator alarmed S

oon after, the INSTRUMENT AIR PRESS LO annunciator alarmed O

n CB-10,11, PI-1750, Instrument Air Pressure, is cycling between 80 and 85 psig Which one of the following failures could cause these indications?

A. A leak in an instrument air line inside containment.

B. A stuck open relief valve on an air receiver.

C. A clogged or flooded air dryer.

D. A leak in the turbine building service air header.

page 54

2009 FORT CALHOUN RO EXAM (55)

A mechanical interlock is provided on the Personnel Air Lock (PAL) doors to ensure that:

A. The Inner PAL door cannot be opened with a high differential pressure across it.

B. The Inner PAL door cannot be opened unless the outer PAL door is closed.

C. The Outer PAL door cannot be opened from the outside with a Containment Isolation Actuation Signal (CIAS) present.

D. The Outer PAL door cannot be opened from the outside with a Containment Radiation High Signal (CRHS) present.

page 55

2009 FORT CALHOUN RO EXAM (56)

Given the following plant conditions:

A steam line break has occurred in Room 81 P

PLS and SGIS have actuated T

he affected steam generator has blown dry P

ressurizer level is 60% and rising P

ressurizer pressure is at 1650 psia and rising In accordance with EOP-AOP Attachment 23, RESTORATION OF LETDOWN, what action should be taken to allow the letdown isolation valves, HCV-204 and TCV-202 to be opened?

A. Reset Engineered Safeguards relays.

B. Block PPLS, reset PPLS and CIAS lockout relays.

C. Place CIAS override switches for HCV-204 and TCV-202 in override.

D. Place Defeat switch for HCV-204 in the defeat position.

page 56

2009 FORT CALHOUN RO EXAM (57)

How could inoperability of the Containment Purge Exhaust Fans affect a refueling outage?

A. Containment entry could be delayed due to higher airborne activity.

B. Containment entry could be delayed due to higher temperatures in containment.

C. Fuel movement could be delayed because Tech Specs require operability of the purge fans.

D. Plant restart could be delayed because Tech Specs require operability of the purge fans.

page 57

2009 FORT CALHOUN RO EXAM (58)

Given the following plant conditions:

T he plant is in a refueling outage S

hutdown Cooling is in service T

he Refueling Cavity is flooded T

he core has been offloaded to the Spent Fuel Pool S

pent Fuel Pool Cooling pump, AC-5A, has just tripped and cannot be restarted S

pent Fuel Pool Cooling pump, AC-5B, will not start How will alternate spent fuel pool cooling be established per AOP-36, LOSS OF SPENT FUEL POOL COOLING?

A. The Fuel Transfer Canal Drain pumps, AC-13A and AC-13B, will be aligned to circulate water through the Spent Fuel Pool.

B. The Fuel Transfer Canal Drain pumps, AC-13A and AC-13B, will be aligned to circulate water between the Refueling Cavity and Spent Fuel Pool, back through the Fuel Transfer Tube.

C. The Low Pressure Safety Injection Pumps, SI-1A and SI-1B, will be aligned to circulate water through the Spent Fuel Pool.

D. The Low Pressure Safety Injection Pumps, SI-1A and SI-1B, will be aligned to circulate water between the Refueling Cavity and Spent Fuel Pool, back through the Fuel Transfer Tube.

page 58

2009 FORT CALHOUN RO EXAM (59)

How will the Steam Dump and Bypass valves respond to an uncomplicated reactor trip from full power if the output from pressure controller PIC-910 fails low?

(Assume all systems are in automatic.)

A. The Steam Dump Valves, TCV-909s, will open fully and then reclose. The Bypass Valve, PCV-910, will open fully and remain open.

B. The Steam Dump Valves, TCV-909s, will open fully and then modulate to control RCS average temperature between 530°F and 535°F. The Bypass Valve, PCV-910, will remain fully closed.

C. The Steam Dump Valves, TCV-909s, and the Bypass Valve, PCV-910, will open fully and then modulate to control RCS average temperature between 530°F and 535°F.

D. The Steam Dump Valves, TCV-909s, and the Bypass Valve, PCV-910, will open fully and then modulate to control RCS average temperature between 535°F and 540°F.

page 59

2009 FORT CALHOUN RO EXAM (60)

Given the following:

C ondenser Evacuation pumps, FW-8A and FW-8C, are operating F

W-8B is the standby pump T

he "43/FW" switch is in the "OFF" position.

What will happen if FW-8A trips due to high seal water temperature?

A. FW-8B will start immediately. Condenser vacuum will be maintained steady.

B. FW-8B will start automatically if condenser vacuum drops to 24.5 inches of mercury.

FW-8B will continue to run after automatically starting.

C. FW-8B will start automatically if condenser vacuum drops to 24.5 inches of mercury.

FW-8B will then cycle on and off to maintain condenser vacuum between 24.5 and 25.5 inches of vacuum.

D. FW-8B will not start automatically unless the "43/FW" switch is placed in the "AUTO" position.

page 60

2009 FORT CALHOUN RO EXAM (61)

Given the following plant conditions:

T he plant is operating at 40% power C

ondensate pump, FW-2A is out of service C

ondensate pump, FW-2B, is operating F

W-2B is selected on SIAS/CSAS selector switch, 43-SIAS/FW2 What action, if any, should be taken in accordance with OI-FW-1 and for what reason?

A. The selected pump should be changed to FW-2C to ensure that FW-2C will start automatically if FW-2B trips following a SIAS or CSAS actuation.

B. The selected pump should be changed to FW-2C to ensure that FW-2B will continue to run following a SIAS or CSAS actuation.

C. FW-2B should remain as the selected pump to ensure that FW-2B will trip following a SIAS or CSAS actuation.

D. FW-2B should remain as the selected pump to ensure that FW-2B will continue to run following a SIAS or CSAS actuation.

page 61

2009 FORT CALHOUN RO EXAM (62)

Given the following:

The plant is operating at full power REACTOR REGULATING SYSTEM LOOP 1 TREF/TAVG GROSS DEV annunciator is in alarm REACTOR REGULATING SYSTEM LOOP 2 TREF/TAVG GROSS DEV annunciator is in alarm The T-ref (black) pens on both of the TAVG/TREF Recorders (TR-111/TR-121) indicate 532°F Which one of the following would produce these indications?

A. One of the Power Range Control Channels output failed low.

B. Both of the Power Range Control Channels output failed low.

C. The Main Generator output transmitter failed low.

D. The Turbine first stage pressure transmitter failed low.

page 62

2009 FORT CALHOUN RO EXAM (63)

Given the following plant conditions:

W aste Gas Compressor, WD-28A, is lined up and discharging to Gas Decay Tank, WD-29B T

he Control Switch for WD-28A is in the "HAND" Position.

T he Control Switch for Waste Gas Decay Tank, WD-29B's, Inlet Pressure Control valve, PCV-514B, is in the "HAND" position.

If vent header pressure is sufficient, which one of the following will act first to prevent overpressurizing WD-29B?

A. WD-28A will trip on high discharge pressure.

B. PCV-514B will close on high tank pressure.

C. WD-29B's rupture disk will break relieving to the room.

D. WD-29B's relief valve will open relieving to the Auxiliary Building Exhaust Duct.

page 63

2009 FORT CALHOUN RO EXAM (64)

The Distributed Control System (DCS) core mimic monitor provides color graphic displays for each CEDM. Green squares are used to indicate that the CEDM is fully inserted. The DCS input that results in the green square display comes from the:

A. Synchro-transmitters.

B. ERF computer.

C. Magnet actuated reed switches.

D. Cam actuated limit switches.

page 64

2009 FORT CALHOUN RO EXAM (65)

Which of the following describes the response of the Switchgear Room HVAC to Fire Protection System detector alarms in the East Switchgear Room?

A. After a detector has actuated in either zone 7 or 8, the ventilation dampers for only the East Switchgear Room shut.

B. After a detector has actuated in both zones 7 and 8, the ventilation dampers for only the East Switchgear Room shut.

C. After a detector has actuated in either zone 7 or 8, the ventilation dampers for both Switchgear Rooms shut.

D. After detectors have actuated in both zones 7 and 8, the ventilation dampers in both Switchgear Rooms shut.

page 65

2009 FORT CALHOUN RO EXAM (66)

For what procedures are you allowed to use the Indexes on the Document Control Web page to verify that the most current revision of a procedure is being used per SO-G-7, OPERATING MANUAL?

A. For all plant procedures.

B. Only for procedures designated as "Information Use."

C. Only for procedures designated as "Information Use" or "Reference Use."

D. Cannot be used to verify current revision for any procedures.

page 66

2009 FORT CALHOUN RO EXAM (67)

Spent fuel is being moved in the Spent Fuel Pool using Spent Fuel Handling Machine, FH-12. Which one of the following plant HVAC configurations is required in accordance with OP-12, FUELING OPERATIONS?

A. One Auxiliary Building Supply and two Auxiliary Exhaust Fans must be running.

B. All Auxiliary Building Exhaust Fans must be running.

C. Spent Fuel Pool Area Filter, VA-66, must be in the Filtered Mode position and Control Room Ventilation must be operating in the Filtered Air Makeup Mode.

D. Spent Fuel Pool Area Filter, VA-66, must be in the Filtered Mode position and Control Room Ventilation must be operating in the Recirculation Mode.

page 67

2009 FORT CALHOUN RO EXAM (68)

Given the following:

A surveillance test is being performed that measures the closure time of a containment isolation valve.

A suggestion is made that the test be conducted first for "just in time training" prior to the actual surveillance test being conducted.

Is this allowed in accordance with SO-G-23, SURVEILLANCE TEST PROGRAM and why?

A. Yes, SO-G-23 requires pre-cycling of the valves to ensure operability prior to measuring stroke time.

B. Yes, this is a good practice although it is not required by SO-G-23.

C. No, this is not a good practice because it involves excessive valve cycling.

D. No, this is not allowed because SO-G-23 requires the test be conducted from the "as found" condition.

page 68

2009 FORT CALHOUN RO EXAM (69)

During the conduct of a surveilance test, the control switch for a pump that is required to be operable by Technical Specifications is placed in the "PULL-TO-LOCK" position.

No other changes have been made to the system.

How does this affect the Operability and Availability of the pump?

A. The pump is "Operable" and "Available."

B. The pump is NOT "Operable" but is "Available."

C. The pump is "Operable" but is NOT "Available."

D. The pump is NOT "Operable" and NOT "Available."

page 69

2009 FORT CALHOUN RO EXAM (70)

The plant is operating at full power. An instrument bus has been placed in an abnormal alignment to allow for maintenance activites.

Which one of the following alignments requires logging into a Limiting Condition for Operation?

A. Instrument Bus "A" is being supplied by swing inverter, EE-8T.

B. Instrument Bus "A" is being supplied by its bypass transformer.

C. Instrument Bus "1" is being supplied by its bypass transformer.

D. Instrument Bus "1" is being supplied by its testing transformer.

page 70

2009 FORT CALHOUN RO EXAM (71)

When are Control Room Log entries required for containment entry and exit per Standing Order O-22, "CONTAINMENT ACCESS AND EGRESS?

A. When one PAL door is inoperable.

B. When containment integrity is required.

C. When entering without Radiation Protection coverage.

D. When the containment security card readers are not operational.

page 71

2009 FORT CALHOUN RO EXAM (72)

How will placing the keyswitch on a Control Room process radiation monitor ratemeter in the "KEYPAD" position affect operation of the radiation monitor?

A. Annunciation and equipment actuations will be blocked.

B. Annunciation will still work but equipment actuations will be blocked.

C. Annunciation and equipment actuations will still work but output to the radiation monitor recorder will be blocked.

D. Annunciation and equipment actuations will still work but output to the ERF computer will be blocked.

page 72

2009 FORT CALHOUN RO EXAM (73)

EOP-04, STEAM GENERATOR TUBE RUPTURE, directs aligning blowdown sample flow to the Spent Regenerant Tank to:

A. Limit the release of radioactive liquid to the river.

B. Limit contamination of the water in the Condenser Hotwell.

C. Minimize radiation levels in Room 81.

D. Minimize radiation levels in the secondary sampling room.

page 73

2009 FORT CALHOUN RO EXAM (74)

In the Control Room, plant instruments that have been qualified to survive in an accident environment (EEQ) can be identified by:

A. Orange tape.

B. Orange dots.

C. Yellow labels.

D. Red and white striped label borders.

page 74

2009 FORT CALHOUN RO EXAM (75)

Given the following plant conditions:

A reactor startup is in progress W

ide Nange NI power indicates 5 x 10-5% power A

sustained positive startup rate of 1.5 DPM is indicated on all channels.

A ll Zero Power Mode Bypass Switches are in the "BYPASS" position A

ll Reactor Coolant Pumps are operating If Reactor Coolant Pump, RC-3D, were to trip from these conditions, when and why would an automatic reactor trip occur and EOP-00 be entered?

Assume no operator actions.

A. The reactor would trip immediately due to low RCS flow.

B. The reactor would trip on low RCS flow when power exceeds 1 x 10-4% power.

C. The reactor would trip immediately due to high startup rate.

D. The reactor would trip on high startup rate when power exceeds 1 x 10-4% power.

page 75

RO EXAM HANDOUTS

TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Reactor Coolant System 2.1.1 Operable Components Applicability Applies to the operable status of the reactor coolant system components.

Objective To specify certain conditions of the reactor coolant system components.

Specifications Limiting conditions for operation are as follows:

(1) Reactor Critical All four (4) reactor coolant pumps shall be in operation.

Exceptions The limitations of this specification may be suspended during the performance of physics tests provided the power level is < 10-1% of rated power and the flow requirements of Table 1.1 No. 2 are met.

(2) Hot Shutdown or 350EF < Tcold < 515EF (a) The reactor coolant loops listed below shall be operable:

(i) Reactor coolant loop 1 and at least one associated reactor coolant pump.

(ii) Reactor coolant loop 2 and at least one associated reactor coolant pump.

(b) At least one of the above reactor coolant loops shall be in operation.

Exceptions All reactor coolant pumps may be de-energized for up to one hour provided (1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and (2) core outlet temperature is maintained at least 10EF below saturation temperature.

2.1 - Page 1 Amendment No. 46,47,56, 256

TECHNICAL SPECIFICATIONS 2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Reactor Coolant System (Continued) 2.1.1 Operable Components (Continued)

(c) If fewer than the above required reactor coolant loops are OPERABLE, the required loops shall be restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or the reactor shall be placed in COLD SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

(3) 210°F Tcold 350°F or Tcold < 210°F with fuel in the reactor and all reactor vessel head closure bolts fully tensioned.

(a) At least two (2) of the decay heat removal loops listed below shall be OPERABLE:

(i) Reactor coolant loop 1 and its associated steam generator and at least one associated reactor coolant pump.

(ii) Reactor coolant loop 2 and its associated steam generator and at least one associated reactor coolant pump.

(iii) One shutdown cooling pump, one shutdown cooling heat exchanger, and associated shutdown cooling piping.

(iv) One shutdown cooling pump, in addition to that in (iii) above, one shutdown cooling heat exchanger, in addition to that in (iii) above, and associated shutdown cooling piping.

(b) At least one (1) of the decay heat removal loops listed above shall be IN OPERATION.

(c) With no coolant loop IN OPERATION, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and initiate corrective action to return the required coolant loop to operation in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

(d) For the purposes of items a(iii) and a(iv) above, the containment spray pumps can be considered as available shutdown cooling pumps only if both of the following conditions are met:

(i) Reactor Coolant System temperature is less than 120EF.

(ii) The Reactor Coolant System is vented with a vent area greater than or equal to 47 in2.

(4) DELETED 2.1 - Page 2 Amendment No. 39,56,136,188, 256

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 12 OF 19 126 LONG TERM STEADY STATE (104.5) 100.8 INSERTION LIMIT (94.5)

GROUP 4 (82.5) 75.6 SHORT TERM INSERTION LIMIT PPDIL 126 50.4 100.8 25.2 CEA GROUP POSITIONS (INCHES WITHDRAWN)

PDIL or TRANSIENT GROUP 3 INSERTION LIMIT 75.6 0 50.4 EMERGENCY BORATION LIMIT (35.2) 12 BELOW PDIL - REFER TO AOP-3 25.2 126 (25.2)

(13.2) 0 100.8 GROUP 2 75.6 50.4 126 25.2 100.8 0 GROUP 1 75.6 50.4 25.2 0

0 20 40 60 80 10 0 REACTOR POWER (% OF ALLOWED POWER)

COLR POWER DEPENDENT INSERTION LIMIT FIGURE 2

R36

ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: 03/27/2009 Facility/Unit: Fort Calhoun Region: I II III IV X Reactor Type: W CE X BW GE Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to complete the combined examination, and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months if you are only taking the SRO portion.

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

Applicants Signature Results RO/SRO-Only/Total Examination Values / / Points Applicants Scores / / Points Applicants Grade / / Percent ES-401, Page 31 of 33

2009 FORT CALHOUN SRO EXAM (1)

A reactor trip has just occurred and the Standard Post Trip Actions are being performed in accordance with EOP-00, STANDARD POST TRIP ACTIONS.

Which of the following parameters requires you to take contingency actions?

A. All trippable control element assemblies are fully inserted except for B-15. All non-trippable control element assemblies are fully withdrawn.

B. Instrument air pressure is 85 psig and stable.

C. Both steam generator wide range levels are 85% and stable.

D. Pressurizer pressure is 2060 psia and increasing.

page 1

2009 FORT CALHOUN SRO EXAM (2)

Given the following plant conditions:

A loss of load event resulted in a high pressure reactor trip Both of the Power-Operated Relief Valves (PORVs) opened One of the PORVs failed to close when pressurizer pressure lowered below it's setpoint Power was not available to the open PORV's block valve during performance of Standard Post Trip Actions EOP-03, LOSS OF COOLANT ACCIDENT, was entered Power has now been restored to the open PORV's block valve The PORV block valve associated with the open PORV should NOT be closed if:

A. Pressurizer level is at 100%.

B. Pressurizer pressure is 2010 psia.

C. Reactor vessel level is 83%.

D. RCS subcooling is 0°F.

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2009 FORT CALHOUN SRO EXAM (3)

Given the following plant conditions:

The plant is in hot shutdown Charging and letdown were isolated in response to RCS leakage Isolation of charging and letdown terminated the RCS leakage Pressurizer heaters have just lost power due to the low level cutout All Reactor Coolant Pumps are operating as designed How much time do the operators have to reestablish charging flow to the RCS before the pressurizer empties assuming RCS cold leg temperature stays steady at 532°F?

A. 3.5 - 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months B. 5.0 - 6.0 hours0 days 0 hours 0 weeks 0 months C. 6.5 - 7.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months D. 8.0 - 9.0 hours0 days 0 hours 0 weeks 0 months page 3

2009 FORT CALHOUN SRO EXAM (4)

The following plant conditions exist during a RCS heatup:

T-cold is 410°F.

T-hot is 411°F.

Core Exit Thermocouples are reading between 410°F and 415°F.

Pressurizer pressure indicates 955 psia.

No operations are in effect that could cause a RCS dilution.

Which one of the following Reactor Coolant Pump operating conditions is NOT allowed by the requirements of T.S. 2.1.1?

A. RC-3A and RC-3C are operable, but not operating. RC-3B and RC-3D are not operable. RC-3A has been shutdown for 35 minutes.

B. RC-3A is operating. RC-3C is operable, but not operating. RC-3B and RC-3D are not operable. RC-3C has been shutdown for 75 minutes.

C. RC-3B and RC-3D are operable, but not operating. RC-3A and RC-3C are not operable. RC-3D has been shutdown for 35 minutes.

D. RC-3C is operating. RC-3D is operable, but not operating. RC-3A and RC-3B are not operable. RC-3D has been shutdown for 75 minutes.

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2009 FORT CALHOUN SRO EXAM (5)

Given the following plant conditions:

RCS temperature is 105°F Pressurizer pressure is 15 psia Shutdown Cooling was in operation per OI-SC-1, SHUTDOWN COOLING INITIATION LPSI pump, SI-1A, was running The pressurizer manway is removed Offsite power has just been lost The Emergency Diesel Generators operate as designed What action (if any) should you perform after the Emergency Diesel Generators start and their output breakers close?

A. Manually restart the LPSI pumps.

B. Un-isolate the LPSI system from the RCS and restart the LPSI pumps.

C. No action is necessary; the Emergency Diesel Generators will pick up the LPSI pumps as dead bus loads.

D. No action is necessary; the sequencers will restart LPSI pumps within one minute of the breaker closing.

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2009 FORT CALHOUN SRO EXAM (6)

The following plant conditions exist:

The plant was operating at 65% power with all systems are aligned for normal operation The "CC WATER SURGE TANK AC-2 HI OR LO LEVEL" alarm was received The Auxiliary Building Operator reported that he heard a loud rumbling noise from the operating CCW pump, AC-3A You observe fluctuating current and discharge pressure for AC-3A The CCW surge tank level is 8 inches and lowering The reactor was manually tripped two minutes after the AUXILIARY COOLANT FROM CRDM FLOW LO alarm was received What action should be performed in addition to Standard Post Trip Actions in accordance with AOP-11?

A. Trip one RCP in each loop within 3 minutes. Trip the remaining RCPs if high bearing temperature alarms are received.

B. Trip one RCP in each loop within 5 minutes. Trip the remaining RCPs if high bearing temperature alarms are received.

C. Shutdown all RCP's within 3 minutes.

D. Shutdown all RCP's within 5 minutes.

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2009 FORT CALHOUN SRO EXAM (7)