ML010460130

Final Master Ro/Sro - Watts Bar Exam 50-390, 391/2001-301 Jan 29 - Feb 6, 2001 - Final Ro/Sro Written Exams & Answer Keys

ML010460130
Person / Time
Site:	Watts Bar
Issue date:	02/15/2001
From:	Operator Licensing and Human Performance Branch
To:
References
-RFPFR, 50-390/01301, 50-391/01301
Download: ML010460130 (135)

See also: IR 05000390/2001301

Text

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FINAL SUBMITTAL

( WATTS BAR EXAM

50-390, 391/2001-301

JANUARY 29 - FEBRUARY 6,

2001

FINAL RO WRITTEN EXAMINATION

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WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26101

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18. 0000 43. 0000

19. 0000 44. 0000

20. 0000 45. 0000

21. 0000 46. 0000

22. 0000 47. 0000

23.-0000 48.0000

24-.0000 40. 0000

25-.0000( 50. 0000

Page 1

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

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Page 2

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

1. 005AK3.02 001

Given the following plant conditions:

- Reactor is at 75% with a power increase in progress using control rods.

- The OAC determines that Control Bank D rod H-12 is not moving and is

14 steps below the other rods in D bank.

- Crew is performing AOI-2, "Malfunction of Reactor Control System" to

realign control rod H-12 with the bank.

- The e-c,4-) r,-,P A1 *,dan)A, fn,"J I h/v's

c-:'f

Which ONE of the following describes how control rod H-12 will be realigned to

control bank D and how control bank insertion limit will change following the

realignment?

a. Control Bank D will be realigned to control rod H-12 and control bank D

insertion limit will be higher.

-/b. Control Bank D will be realigned to control rod H-12 and control bank D

insertion limit will be lower

c. Control rod H-12 will be realigned to Control Bank D and control bank D

insertion limit will be lower.

d. Control rod H-12 will be realigned to Control Bank D and control bank D

insertion limit will be higher.

2. 015AK1.05 001

Given the following plant conditions:

- Reactor power is stable at 30%

- Loop 1 RCP trips

Assuming reactor power remains constant, core exit temperature will:

,/a. increase, then stabilize at a higher value.

b. decrease, then stabilize at a lower value.

c. increase, then return to the original steady-state value.

d. decrease, then return to the original steady-state value.

Page 1

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

3. 017AK3.03 001

Given the following conditions:

- Unit at 60% power.

- Confirmed Loop 1 RCP shaft vibration of 25 mils.

Which ONE of the following statements is correct per AOI-5, "Unscheduled

Removal of One RCP", regarding the sequence of actions?

a. RCP should be tripped prior to the reactor trip to minimize pump damage.

b. The reactor should be tripped prior to tripping the RCP to prevent pressurizer

level from dropping below 17%.

c. RCP should be tripped prior to the reactor trip to prevent Reactor Coolant

Bus voltage from dropping and tripping additional RCPs.

,/d. The reactor should be tripped prior to tripping the RCP to prevent an

automatic trip and an unnecessary challenge to a safety system.

4. 017AA1.13 001

Given the following plant conditions:

- Unit was operating at 58% power.

- Problems with #4 RCP required the pump to be shut down

in accordance with AOI-5, "Unscheduled Removal of One RCP".

Which ONE of the following identifies the maximum power level allowed by AOI-5

for restart of #4 RCP?

Va. P-10.

b. P-9.

c. P-8.

d. Mode 3.

Page 2

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

5. 024AK1.02 001

Given the following plant conditions:

- Plant was operating at 100% power when a Main Feedwater pump trip

resulted in a turbine runback.

- All systems in automatic and responded as expected to stabilize the

plant.

- Control rods inserted beyond the Lo-Lo Rod Insertion limits.

- Operators implemented AOI-34, "Immediate Boration", in accordance

with the ARI.

Which ONE of the following indicates the final, stable plant conditions

AFTER completion of the boration as compared to those PRIOR to the boration?

Reactor Power Rod Position Tavq

a. Same Higher Higher

,/1b. Same Higher Same

c. Lower Lower Same

d. Lower Lower Lower

Page 3

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

6. 027AA2.02 001

Given the following plant conditions:

- The plant is at steady state 100% power equilibrium xenon with all

control systems in automatic.

- Pressurizer level control is transferred to MANUAL and level is slowly

increased to 75% and maintained.

Which ONE of the following describes the PZR pressure response?

a. Pressure is essentially unaffected.

b. Pressure will continuously cycle between 2235 and 2260 psig.

c. Pressure will increase until the spray valves open and control pressure at

2260 psig.

Vd. Pressure will increase until the spray valves open and slowly return pressure

to steady state 2235 psig.

Page 4

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

7. 027AA2.12 001

Given the following plant conditions:

- Plant is operating at 100% power.

- One pressurizer safety valve failed full OPEN.

- Operating crew initiated reactor trip/safety injection and entered the

EOPs.

- Safety Injection signal is not reset.

Which ONE of the following is the status of Pressurizer level and pressure control

10 minutes following the reactor trip/safety injection?

a. PZR level indication offscale LOW.

PZR heaters ON.

b. PZR level indication offscale LOW.

PZR heaters OFF.

c. PZR level indication offscale HIGH.

PZR heaters ON.

,d. PZR level indication offscale HIGH.

PZR heaters OFF.

Page 5

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

8. 057AA1.05 001

Given the following plant conditions:

- Plant is operating at 100% power.

- A loss of 120V AC Vital Instrument Power Board 1-1 occurred.

- The crew implements AOI-25.01, "Loss of 120V AC Vital Instrument

Power Board 1-l".

Which ONE of the following identifies the train selector switches that must be

selected for automatic control of feedwater and which loop 1 feedwater/steam

flow indications are available?

Feedwater/Steam Flow Feedwater/Steam Flow

Selector Switches Indications

a. A train Channel I

b. A train Channel II

c. B train Channel I

,/d. B train Channel II

Page 6

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

9. 068G2.3.10 001

Given the following:

- Committed Dose Equivalent (CDE) is 1875 mrem

- Deep Dose Equivalent (DDE) is 1620 mrem

- Lens Dose Equivalent (LDE) is 430 mrem

- Committed Effective Dose Equivalent (CEDE) is 260 mrem

- Total Organ Dose Equivalent (TODE) is 3685 mrem

- Shallow Dose Equivalent (SDE) is 295 mrem

What is the Total Effective Dose Equivalent (TEDE)?

a. 3980 mrem

b. 2170 mrem

c. 1915 mrem

,/d. 1880 mrem

10. 069AK2.03 001

Which ONE of the following conditions concerning the Personnel Airlock would

exceed a Limiting Condition for Operation and require entering an Action

Statement of Technical Specifications?

a. The lower containment airlock fails its LLRT while control rod unlatching is in

progress.

b. Welding cables are laid through both lower containment airlock doors during

RCS fill and vent at the end of an outage.

c. The lower containment airlock door interlocks are defeated while reactor

vessel head is being tensioned.

,/d. The outer and inner doors are opened simultaneously during a normal

cooldown prior to aligning RHR to the RCS.

Page 7

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

11. 074EK1.03 001

Given the following plant conditions:

- Inadequate core cooling conditions exist

- Crew is performing FR-C.1, Inadequate Core Cooling

Which ONE of the following sets of actions states the proper sequence of the

major action categories to be performed for removing decay heat from the core?

a. Rapid secondary depressurization; reinitiation of high head safety injection;

RCP restart

v/b. Reinitiation of high head safety injection; rapid secondary depressurization;

RCP restart

c. Rapid secondary depressurization; RCP restart; reinitiation of high head

safety injection

d. RCP restart; rapid secondary depressurization; reinitiation of high head safety

injection

12. 076AA1.04 001

Which ONE of the following correctly describes the indication on the main steam

line radiation monitors when the MR/HR AUTO pushbutton is lit on the RM-23

readout module?

a. Indicates low range output only.

,/b. Indicates high range output only.

c. Automatically switches between the low and high range outputs every 45

seconds.

d. Automatically switches between low and high range output based upon

activity level in order to maintain accurate indication.

Page 8

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

13. E06EK2.1 001

Given the following plant conditions:

- Operators are responding to a large break LOCA and have determined

that degraded core cooling conditions exist.

- The crew has implemented FR-C.2, "Degraded Core Cooling".

- Preparations are in progress to depressurize all intact S/Gs to

atmospheric pressure in accordance with FR-C.2.

Which ONE of the following is the reason the procedure directs all RCPs be

stopped prior to performing the depressurization?

a. Reduces the core AP which will enhance the ability of the RHR pumps to

inject into the core.

b. Minimizes heat input to the S/Gs allowing them to depressurize faster.

c. Limits heat removal requirements to the core decay heat only.

,/d. Anticipates a loss of RCP #1 seal AP requirements.

14. E07EK2.1 001

Given the following plant conditions:

- A large break LOCA has occurred that resulted in saturated core cooling

conditions.

- RWST level is 28%

- Crew is performing step 4 of FR-C.3, Saturated Core Cooling to

establish SI pump valve alignment.

Which ONE of the following identifies valves that should be verified CLOSED

during performance of this step?

a. FCV-63-6, 7 and 177, SI pump and Charging pump suction from RHR.

b. FCV-63-47 and 48, SI pump suction valves

c. FCV-63-152 and 153, SI pump cold leg injection cross-tie valves

,/d. FCV-63-3, 4 and 175 SI pump mini-flow valves

Page 9

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

15. 060AA2.04 001

Given the following plant conditions:

- A Gas Decay Tank release in progress with ABGTS running for dilution

air flow.

- A leak occurs on the waste gas compressor which results in a gas

release to the Auxiliary Building.

- 0-RE-90-101, Auxiliary Building Vent Monitor, is in alarm.

Which ONE of the following indicates the effect this leak will have on the plant?

(Assume no operator action)

a. Gas Decay Tank release will be terminated; ABGTS will be stopped.

b. Gas Decay Tank release will be terminated; ABGTS will continue to run.

c. Gas Decay Tank release will continue; ABGTS will be stopped.

,/d. Gas Decay Tank release will continue; ABGTS will continue to run.

16. E14EK3.2 001

Which ONE of the following describes the reason for tripping all RCPs during

the performance of FR-Z.1, "High Containment Pressure"?

a. Removes heat transferred to the Containment atmosphere from the RCP

motors.

b. Prevents depletion of primary inventory out of the break during a small

LOCA.

vc. Containment Isolation OB isolates cooling water to the RCPs and thermal

barriers.

d. Removes additional energy to the RCS during a break and subsequent

release to containment.

Page 10

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

17. 003AA2.01 001

Given the following plant conditions:

- Unit is stable at 55% power.

- Recovery of dropped rod D-4 (Control Bank D, Group 1) is in progress.

- D-4 is at 50 steps.

- Remaining Bank D rods are at 125 steps.

Which ONE of the following Control Bank D indications will update as withdrawal

of the dropped rod continues?

a. Both Bank D step counters and P/A converter

b. Both Bank D step counters and Bank Overlap counter

,/c. Only Group 1 step counter and P/A converter

d. Only Group 1 step counter and Bank Overlap counter

Page 11

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

18. 007EK2.02 001

Given the following plant conditions:

- Unit 1 operating at 22% power.

- Reactor Trip Breakers "A" & "B" closed.

- Bypass Breaker B is racked in and closed.

"- "B" Train SSPS Input Error Inhibit Switch is in INHIBIT for surveillance

testing.

Which ONE of the following describes the response of the Reactor Trip and

Bypass Breakers if RCS pressure drops below the Low Pressure Reactor trip

setpoint with no operator action?

a. Reactor Trip Breakers "A" & "B" open, Bypass Breaker "B" opens.

b. Reactor Trip Breaker "A" opens and "B" remains closed, Bypass Breaker "B"

remains closed.

c. Reactor Trip Breaker "B" opens and "A" remains closed, Bypass Breaker "B"

opens.

Vd. Reactor Trip Breaker "A" opens and "B" remains closed, Bypass Breaker "B"

opens.

Page 12

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

19. 008AK1.01 001

Given the following plant conditions:

- Unit was at 100% power.

- All systems operating in automatic and all plant parameters at their

normal values.

- 1-PCV-68-340 failed partially open.

Which ONE of the following identifies the approximate maximum expected

temperature of the steam entering the PRT if the PRT pressure does not

exceed 45 psig?

a. 228TF.

b. 250 0 F.

c. 275 0 F

/d. 290°F

20. 008G2.2.25 001

According to the safety limit technical specification basis for RCS pressure, the

maximum transient pressure allowed is:

,/a. 110% of design pressure.

b. 110% of normal operating pressure.

c. 125% of design pressure.

d. 125% of normal operating pressure.

Page 13

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

21. 011EK2.02 001

Given the following conditions:

- A large break LOCA occurred

- Operators have just completed swapover to Containment Sump

- A loss of offsite power occurs

Which ONE of the following describes the actions required for this condition?

a. Pull to lock SI pumps and CCPs until the RHR pumps have been restarted

after the shutdown boards are reenergized.

,/b. Pull to lock the CCPs until the RHR pumps are restarted after the shutdown

boards are reenergized.

c. Ensure both RHR pumps are started by the blackout sequencer after the

diesel generators reenergize the shutdown boards then restart the SI pumps.

d. Ensure all ECCS pumps are started by the blackout sequencer when the

diesel generators reenergize the shutdown boards.

Page 14

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

22. 029EA1.02 001

Given the following plant conditions:

- ATWS without Safety Injection has occurred.

- Crew has implemented FR-S.1, "Nuclear Power Generation/ATWS", and

currently performing step 4 to borate the RCS.

Which ONE of the following identifies the correct Operator action that must be

taken in order to align charging pump suction?

a. CLOSE LCV-62-132 and 133, VCT outlet isolation, then OPEN LCV-62-135

and 136, RWST supply to charging pump suction.

,/b. OPEN LCV-62-135 and 136, RWST supply to charging pump suction, then

CLOSE LCV-62-132 and 133, VCT outlet isolation.

c. Verify LCV-62-135 and 136, RWST supply to charging pump suction AUTO

OPEN, then CLOSE LCV-62-132 and 133, VCT outlet isolation.

d. Verify LCV-62-135 and 136, RWST supply to charging pump suction and

LCV-62-132 and 133, VCT outlet isolation AUTO OPEN.

Page 15

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26101

23. 032AK3.02 001

Given the following plant conditions:

- The Unit is in MODE 6.

- Source Range Monitor (SRM) NI-132 has failed LOW resulting in a loss

of the audio count rate signal.

WHICH ONE of the following describes the actions necessary to restore the

audio count rate signal to the control room.

,a. Place the audio count rate CHANNEL SELECTOR switch on the front of the

Audio Count Rate Drawer to the SR N31 position.

b. Place the audio count rate CHANNEL SELECTOR switch on the front of the

Audio Count Rate Drawer to the SR N32 position.

c. Place the AMPLIFIER SELECT switch on the rear of the audio count rate

drawer assembly to the Al position.

d. Place the AMPLIFIER SELECT switch on the rear of the audio count rate

drawer assembly to the A2 position.

Page 16

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

24. 033AA1.01 001

Given the following plant conditions:

- A Reactor startup in progress.

- Reactor power is stable at 2 x 10-2% power on the Intermediate Range

- Intermediate Range channel N-135 was declared inoperable and

removed from service per AOI-4, "Nuclear instrumentation Malfunction".

Which ONE of the following describes the plant response if an I&C Technician

mistakenly removes the control power fuses for N-1 35 during troubleshooting

activities?

"Va. The trip bistable deenergizes and a reactor trip occurs because power is

below P-10.

b. The trip bistable deenergizes, however NO trip occurs because N-135 is

bypassed.

c. The trip bistable energizes, however NO trip occurs because N-135 is

bypassed.

d. The trip bistable energizes and a reactor trip occurs because power is below

P-10.

Page 17

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

25. 038EK1.01 001

Given the following plant conditions:

- Steam Generator Tube Rupture has occurred.

- Crew has implemented E-3, "Steam Generator Tube Rupture".

- The operators have completed cooldown to target incore temperature of

4800 F.

Which ONE of the following identifies the pressure that steam dumps will be set

to control RCS temperature at 480'F?

a. 580 - 585 psig.

,/b. 550 - 555 psig.

c. 580 - 585 psia.

d. 550 - 555 psia.

26. 058AK3.01 001

Given the following plant conditions:

- AUO reports Emergency Diesel Generator (D/G) 1A-A has lost 125V DC

control power from it's associated Diesel Battery Distribution Panel

- D/G 1A-A is NOT running.

Which ONE of the following describes how this loss of DC control power would

affect D/G operation?

a. D/G would start in response to an automatic or manual start signal.

,/b. D/G cannot be started by automatic or manual start signal.

c. D/G can only be started manually from local control panel.

d. D/G can only be started manually from the MCR panel.

Page 18

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

27. 059AK1.01 001

Given the following plant conditions:

- Plant is operating a 100% power.

- Plant systems aligned and operating normally.

- Annunciator, CCS HX A 1-RM-90-123 LIQ RAD HIGH, is in alarm.

Which ONE of the following lists the type and source of radiation sensed by the

radiation monitor that is in alarm?

Va. Gamma; Thermal Barrier leakage.

b. Beta; Thermal Barrier leakage.

c. Gamma; RCP motor cooler leakage.

d. Beta; RCP motor cooler leakage.

Page 19

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

28. 060AA2.05 001

Given the following conditions:

- Unit at 100% power.

- The Control Room Air Intake radiation monitor, 1-RM-90-125, alarms.

Which ONE of the following describes the response of the Control Building

Ventilation System?

,/a. Pressurization fans inlet dampers CLOSE

Emergency Pressurization fans inlet dampers OPEN

Air cleanup fans inlet dampers OPEN

b. Pressurization fans inlet dampers OPEN

Emergency Pressurization fans inlet dampers CLOSE

Air cleanup fans inlet dampers OPEN

c. Pressurization fans inlet dampers CLOSE

Emergency Pressurization fans inlet dampers OPEN

Air cleanup fans inlet dampers CLOSE

d. Pressurization fans inlet dampers OPEN

Emergency Pressurization fans inlet dampers CLOSE

Air cleanup fans inlet dampers CLOSE

29. EO1EK3.4 001

Once an operating crew has entered the EOP network, which ONE of the

following is the earliest that a transition may be made to ES-0.0, "Rediagnosis"?

Va. AFTER transition from E-0 and safety injection initiated.

b. AFTER transition from E-0 and NO safety injection initiated.

c. BEFORE transition from E-0 and safety injection initiated.

d. BEFORE transition from E-0 and NO safety injection initiated.

Page 20

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

30. E03EK1.3 001

Given the following plant conditions:

- A small break LOCA has occurred

- 1B-B CCP and SIP failed to start and could not be started manually.

- E-1 is completed and transition to ES-1.2, "Post LOCA Cooldown and

Depressurization", made.

- 6.9kV Shutdown Board 1A-A is de-energized due to a fault

- The following conditions are noted by the OAC

- RCS pressure is 1600 psig

- Containment pressure is 6 psig

Which ONE of the following describes the action that should be taken and the

basis for that action?

a. All RCPs should be stopped to limit heat input during the RCS cooldown.

,/b. All RCPs should be stopped because OB isolation has occurred.

c. All RCPs should NOT be stopped because no CCP or SIP is injecting into the

RCS.

d. All RCPs should NOT be stopped because the RCS pressure is above 1500

psig.

31. E03EK2.2 001

Which ONE of the following is the significance of draining the SG U-tubes and

blowing the inverted "loop seal" during a cold leg small break LOCA?

,'a. A steam vent path is established from the core to the break location and

mass loss from the system is decreased.

b. Core cooling will be lost after the loop seal is blown due to increased injection

flow being diverted to the break location.

c. RCS pressure control will be lost resulting in a challenge to Pressurized

Thermal Shock limits.

d. The heat sink effect of the water in the "crossover" leg is lost when the loop

seal is lost resulting in a degraded core cooling.

Page 21

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

32. E05EK2.1 001

Given the following plant conditions:

- Reactor trip and safety injection occurred.

- The crew implemented FR-H.1, "Loss of Secondary Heat Sink" due to

heat sink red path.

- Operators are preparing for main feedwater startup.

Which ONE of the following lists the minimum actions required to reset Main

Feedwater Pump 1A?

a. Reset safety injection and cycle reactor trip breakers.

b. Reset safety injection and reset feedwater isolation signal.

c. Cycle the reactor trip breakers and reset feedwater isolation signal.

,/d. Reset safety injection, cycle reactor trip breakers, and reset feedwater

isolation signal.

33. El1EA1.2 001

Given the following plant conditions:

- Reactor trip and SI occurred at 0200 due to a small LOCA.

- At 0300 the crew transitioned to ECA-1.1, "Loss of RHR Sump

Recirculation", due to the failure of both RHR pumps.

- Crew has reduced ECCS flow to 1 SIP and 1 CCP per ECA-1.1.

- At 0500 the crew is performing step 17 RNO to establish the minimum

required ECCS flow to remove decay heat.

Using Figure 1 from ECA-1I.1, which ONE of the following flow rates would satisfy

the intent of the RNO?

a. 170 gpm

,/b. 210 gpm

c. 240 gpm

d. 280 gpm

Page 22

WBN LOSS OF RHR SUMP RECIRCULATION ECA-1.1

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03/05/99 27 of 30

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

34. 036AK1.03 001

Which ONE of the following describes why the baseline count rate used for

developing the 1/M plot must be re-calculated following movement of any source

bearing fuel assembly ?

a. Re-verify the operability of the source range instruments.

,/b. Ensures an accurate 1/M plot to monitor subcriticality.

c. Determine adequate shutdown margin during refueling.

d. Readjust the setpoint for the High Flux at Shutdown alarm.

35. 056AK3.02 001

Given the following plant conditions:

- A Loss of offsite power has occurred.

- A Natural circulation cooldown is in progress.

Which ONE of the following describes how the loss of 2 CRDM fans will affect the

cooldown?

a. No effect, because the amount of RCS heat removal by running the fans is

insignificant compared to that removed by steaming the secondary plant.

b. Less subcooling is required, and the T-cold cooldown rate will be more.

,/c. More subcooling is required, and the T-cold cooldown rate will be less.

d. The upper head will void, since adequate subcooling cannot be maintained

with only 2 CRDM fans.

Page 23

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26101

36. 065AA1.04 001

Following an automatic start due to low instrument air pressure, which ONE of

the following describes what will cause Aux Air Compressors to shutdown?

Va. Running unloaded for 5 minutes.

b. Running unloaded for 10 minutes.

c. Low crankcase oil pressure.

d. High discharge air temperature.

37. 001K5.28 001

Given the following plant conditions:

- The Unit is at 1% power after an extended shutdown.

- Core burnup is 2000 MWD/MTU.

- RCS boron concentration is 1000 ppm.

- Control rods at 175 steps

- The STA has determined that 236 pcm of reactivity must be added to

increase power to 10%.

Using the attached NUPOP curve and assuming no control rod movement, which

ONE of the following identifies the final boron concentration of the RCS after the

reactivity change has been made?

,/a. 966 ppm

b. 969 ppm

c. 1031 ppm

d. 1034 ppm

Page 24

WESTINGHOUSE PROPRIETARY CLASS 2C

-6. .0

- -5 - - --

fl4-6.

-7.

0

z

0

0

0

m -7.

oll

H 5

--8.

0

-9.

u &uu kuu Uu 80U 1000 1200 1400 1600 1800 2000

BORON CONCENTRATION (PPM)

Figure 6-22 Differential Boron Worth Versus Boron Concentration

at BOL, MOL, and EOL, HZP, With No Xenon

WCAP-15562 (Rev. 0) Bumup Dependent Parameters 6 - 27

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

38. 001K6.02 001

Unit is operating at 100% power with all systems in their normal configuration,

when Auctioneered High Tavg fails LOW.

Which ONE of the following describes the plant response?

a. Control rods will step in; Charging Flow Control valve, 1-FCV-62-93, opens.

,/b. Control rods will step out; Charging Flow Control valve, 1-FCV-62-93, closes.

c. Control rods will not move; Charging Flow Control valve, 1-FCV-62-93, opens.

d. Control rods will not move; Charging Flow Control valve, 1-FCV-62-93, closes.

39. 003A1.08 001

Given the following plant conditions:

- The Unit is operating at 100% power.

- All systems are operating normal.

- Annunciator "RCP #1 Seal Outlet Temp Hi" alarm actuates.

- The operator verifies that ALL RCP seal temperatures are 180'F rising.

Which ONE of the following is the most probable cause of this alarm?

a. The Charging Pump suction has swapped to the RWST.

b. The operator has just placed Excess Letdown in service at maximum flow

rate.

,/c. The Letdown Heat Exchanger temperature control valve 1-TCV-70-192 has

failed closed.

d. A loss of control air to charging flow control valve 1-FCV-62-93.

Page 25

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

40. 003G2.4.6 001

Which ONE of the following describes why the RCPs are tripped if the low

pressure trip criteria is reached during a small-break LOCA?

a. Eliminate heat input from the RCPs into the RCS.

b. Limit hydrogen buildup which could preclude core cooling.

c. Steam may be present in the RCS which will cause RCP impeller damage

from cavitation.

,/d. Excessive depletion of RCS water inventory might lead to core uncovery if

RCPs are tripped later in the accident.

41. 004K3.01 001

Given the following conditions:

- Reactor power 35%.

- Turbine load 32%

- Control Rods are in AUTOMATIC.

- CVCS Mixed Bed A was placed in service resulting in a T-avg increase

to 571 OF.

Which ONE of the following describes the response of the rod control system?

(assume no operator action)

a. Rods will step in at 8 steps per minute.

v/b. Rods will step in at 40 steps per minute.

c. Rods will step in at 64 steps per minute.

d. Rods will step in at 72 steps per minute.

Page 26

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

42. 004K2.03 001

Given the following plant conditions:

- The unit is at 100% power with 1A-A CCP is in operation.

- A loss of offsite power occurs

- All appropriate loads sequence onto the Shutdown Boards

- The crew has implemented E-0, "Reactor Trip or Safety Injection"

- While the immediate actions are being completed, a safety injection

signal (SI) is received.

Which ONE of the following describes the response of the Centrifugal Charging

Pumps (CCPs)?

a. 1A-A CCP load sheds on the Sl signal, and both CCPs auto sequence on the

shutdown boards.

b. 1A-A CCP load sheds on the SI signal, and must be restarted manually by

the operator.

c. 1A-A CCP does not load shed on the SI signal, and 1B-B CCP auto

sequences on the shutdown boards.

,/d. Both CCPs remain energized and running following the SI signal.

Page 27

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

43. 013K2.01 001

Given the following:

- 1A-A and 1B-B SI Pump breakers are "Racked In".

- A fuse blows in the NORMAL DC Trip circuit for the 1A-A SI pump.

- A safety injection (SI) actuation occurs.

Which ONE of the following describes the response of the SI Pumps to the SI

signal?

a. 1 B-B SI Pump will auto start, but 1A-A SI Pump will not auto start until the

control power supply is transferred.

b. 1 B-B SI Pump will auto start, but 1A-A Sl Pump will not auto start and must

be started from the MCR handswitch.

Vc. Both SI Pumps will auto start, but the 1A-A Sl Pump cannot be stopped from

the MCR.

d. Both SI Pumps will auto start, but the 1A-A SI Pump cannot be stopped

mechanically at the breaker.

44. 013K4.08 001

Which ONE of the following describes the logic for Safety Injection (SI) actuation

handswitches and reset pushbuttons?

a. Each actuation handswitch initiates both trains of S1.

Each reset pushbutton resets both trains of SI.

,/b. Each actuation handswitch initiates both trains of SI.

Each reset pushbutton resets only it's associated train of S1.

c. Each actuation handswitch initiates only it's associated train of SI.

Each reset pushbutton resets only it's associated train of SI.

d. Each actuation handswitch initiates only it's associated train of S1.

Each reset pushbutton resets both trains of SI.

Page 28

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

45. 015A2.03 001

Given the following plant conditions:

- Unit is operating at 75% power

- A plant transient has resulted in a xenon oscillation

- Control rods are currently at 216 steps on D bank

Which ONE of the following is the effect of the xenon oscillation on NIS and the

action required to dampen the oscillation?

Va. The oscillation affects AFD and is dampened by inserting control rods at its

most positive peak.

b. The oscillation affects AFD and is dampened by inserting control rods at its

most negative peak.

c. The oscillation affects QPTR and is dampened by dropping turbine load at its

highest value.

d. The oscillation affects QPTR and is dampened by dropping turbine load at its

lowest value.

46. 015K6.01 001

Given the following plant conditions:

- Plant is at 25% power with shutdown in progress.

- Power range upper detector, N43A, fails HIGH.

Which ONE of the following identifies the method used to block the "At Power"

reactor trips when turbine load is reduced to < 10%?

a. Manually blocked when 3/4 operable power range channels < 10% power.

-/b. Auto blocked when 3/4 power range channels < 10% power.

c. Manually blocked when 2/4 power range channels < 10% power.

d. Auto blocked when 2/4 power range channels < 10% power.

Page 29

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01126/01

47. 017A3.01 001

Given the following plant conditions:

- A small break LOCA has occurred.

- The crew responded lAW EOPs and tripped the RCPs when required.

- The crew is currently in ES-1.2, "Post LOCA Cooldown And

Depressurization".

- RCS pressure is 1490 psig.

- Wide range Tc's are 505'F and decreasing slowly.

- Wide range Th's are 515°F and decreasing slowly.

- Core exit thermocouples (CETC) are 551 OF and stable.

- Containment pressure is 1.5 psig.

- SG levels are being maintained at 38%.

- SG pressures are 715 psig and decreasing slowly.

Which ONE of the following describes the status of natural circulation for the

existing plant conditions?

Va. Cannot be assured, since there is inadequate sub-cooling.

b. Cannot be assured, since SG parameters are not satisfied.

c. Cannot be assured, since CETCs are not decreasing.

d. Exists since all natural circulation criteria are met.

48. 017K1.01 001

Which ONE of the following lists functions/components that receive input from

the Core Exit Thermocouples?

,/a. ICCM plasma display, ICS, RVLIS recorder.

b. ICS, Rod Insertion Limit computer, RVLIS recorder.

c. ICCM plasma display, OTAT calculator, RVLIS recorder.

d. Core quadrant average temperature, ICS, OPAT calculator.

Page 30

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26101

49. 022K4.03 001

Given the following plant conditions:

- Reactor trip & Safety Injection occurred due to Large Break LOCA.

- Containment OB isolation has occurred.

- All systems responded normally.

Which ONE of the following describes the response of the Lower Compartment

Coolers when 0B is reset?

a. Fans in A-P-AUTO start.

Cooler ERCW isolation valves open.

,/b. Fans in A-P-AUTO start.

Cooler ERCW isolation valves remain closed.

c. Fans in A-P-AUTO remain off.

Cooler ERCW isolation valves open.

d. Fans in A-P-AUTO remain off.

Cooler ERCW isolation valves remain closed.

50. 022A4.02 001

Given the following plant conditions:

- Main Steam Line Break occurred inside containment causing a reactor

trip and safety injection.

- Operators have implemented the EOPs.

- Containment pressure is 3.2 psig and dropping.

- OAC observes the "INSTR ROOM COOLER A/B FLOW LOW" alarm LIT.

Which ONE of the following ESFAS signals caused the Incore Instrument Room

Cooling fans, circ pump, and chiller to shut down?

a. Containment vent isolation (CVI).

,/b. OA containment isolation.

c. OB containment isolation.

d. Aux. Building Isolation (ABI)

Page 31

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

51. 025A3.02 001

Given the following plant conditions:

- Large break LOCA has occurred causing a reactor trip and safety

injection.

- OAC observes annunciator "Glycol Exp Tank Level Hi/Hi-Hi is LIT.

Which ONE of the following describes the most likely reason the annunciator is

LIT?

a. OA closes the glycol containment isolation valves; glycol inside containment

heats up and relief valves on the containment side of the isolation valves

relieve glycol into the glycol expansion tank.

,/b. OA closes the glycol containment isolation valves; glycol inside containment

heats up and expands into the glycol expansion tank.

c. OB closes the glycol containment isolation valves; glycol inside containment

heats up and relief valves on the containment side of the isolation valves

relieve glycol into the glycol expansion tank.

d. 0B closes the glycol containment isolation valves; glycol inside containment

heats up and expands into the glycol expansion tank.

Page 32

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

52. 056K1.03 001

Given the following plant conditions:

- Plant startup in progress.

- Tavg is being maintained at 557°F by Steam dumps.

- Operators are preparing to take the reactor critical.

- Standby Main Feedwater Pump in service supplying the SGs.

Which ONE of the following is the reason why a Condensate Booster Pump

should NOT be operated at this time?

a. To prevent overfeeding steam generators.

,/b. To prevent lifting the high pressure feedwater heater relief valves.

c. To prevent overpressurizaton and damage to the SG's feedwater preheat

section.

d. To prevent overpressurization and damage to the Standby Main Feedwater

Pump suction piping.

53. 059K3.04 001

Given the following conditions:

- Unit is operating at 100% power.

- FCV-2-35, Condensate Short Cycle valve fails OPEN

Which ONE of the following describes the effect on reactor power and the correct

operator response?

Reactor power will:

a. Increase; Borate the RCS.

v-b. Increase; Reduce turbine load.

c. Decrease; Dilute the RCS.

d. Decrease; Raise turbine load.

Page 33

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

54. 059A4.12 001

Given the following plant conditions:

- The plant was operating at 85% RTP when a loss of offsite power

occurred.

- The Emergency Diesel Generators started and re-energized the

Shutdown Boards.

- The operators have implemented the EOPs.

- #4 SG PORV developed a large packing leak after opening following

the reactor trip.

- The CRO has determined that the bypass feedwater isolation valves

are CLOSED.

Which ONE of the following signals caused the bypass feedwater isolation valves

to CLOSE?

a. North valve vault level increasing to 4 inches due to the PORV packing leak.

b. Lo-Lo S/G level as #4 S/G blows dry following MSIV isolation.

,/c. Tavg decreasing to 5640 F following the reactor trip.

d. AFW start signal following the blackout.

55. 061K5.02 001

Which ONE of the following describes the decay heat sources and design basis

for the Auxiliary Feedwater (AFW) System during a loss of offsite power?

a. Prevents relief through the PZR safety valves by removing core decay heat only.

b. Prevents relief through the S/G safety valves by removing core decay heat only.

,/c. Prevents relief through the PZR safety valves by removing core decay heat

and stored RCS heat.

d. Prevents relief through the S/G safety valves by removing core decay heat

and RCP heat.

Page 34

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

56. 071A1.06 001

Given the following plant conditions:

- Unit is at 100% power.

"- "A"Waste Gas Compressor is in service.

- Pressure in the "in service" Waste Gas Decay Tank (WGDT) is 60

psig.

- No WGDT release is in progress

- The relief valve on the "in service" WGDT begins to experience seat

leakage.

Which ONE of the following will provide the best indication that the relief valve on

the WGDT is leaking?

a. Increasing count rates on RM-90-101A, Auxiliary Building Vent Monitor.

vb. Increasing count rates on RM-90-400, Shield Building Vent Monitor.

c. FCV 77-119, Plant Vent Flow Control valve, isolates due to high radiation.

d. The Waste Gas Vent Header pressure increases causing the Waste Gas

Compressor to run continuously.

Page 35

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

57. 071G2.4.18 001

Given the following plant conditions:

- Loss of all Shutdown power occurred resulting in a reactor trip.

- Operators have implemented ECA-0.0, "Loss of Shutdown Power".

- RCS pressure is 280 psig.

- When RCS pressure could not be maintained > 280 psig, the Unit

Supervisor directed the OAC to vent nitrogen from the accumulators.

Which ONE of the following identifies the basis for venting nitrogen from the

accumulators?

a. Prevents injection of additional inventory into the RCS which could result in a

water solid condition and further degradation of the RCS pressure boundary.

b. Prevents erratic RVLIS indications due to pressure pulses as the

accumulators alternately start/stop injecting during RCS depressurization.

c. Prevents sudden cooldown of the RCS cold legs by allowing accumulator

injection to proceed more slowly along with depressurization of the RCS.

,/d. Prevents injection of nitrogen into the RCS which may impede further RCS

pressure control.

Page 36

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26101

58. 072K1.02 001

Given the following plant conditions:

- A source check is being performed on Spent Fuel Pool Monitor (RE-90-102).

- Auto Block handswitches are in the OFF position.

Which ONE of the following will occur when the control switch is placed and held

in "SOURCE CHECK"?

a. The fuel handling area ventilation system is diverted to the suction of the

EGTS system.

b. The green light on the monitor goes out indicating that the monitor is being

source checked.

v'c. Auxiliary Building Ventilation isolates, but no Auxiliary Building isolation signal

is generated.

d. A Containment Ventilation Isolation signal is generated.

59. 072A2.03 001

Given the following plant conditions:

- Plant is operating at 100% power

- Annunciator window 174E, "1-RR-90-1 Area Monitors Instr Malf" is in

alarm.

Which ONE of the following conditions would cause the annunciation?

,/a. Internal power supply blown fuse on 1-RM-90-1, Spent Fuel Pit Area radiation

monitor.

b. Vent Isolation Rad Mon Block switch, 0-HS-90-136A1, selected to 1-130 and

pulled.

c. Function switch for 1-RM-90-102, Spent Fuel Pit monitor, in the Alarm Adj

position.

d. 1-RM-90-6, CCS HXs radiation monitor becomes saturated (offscale high).

Page 37

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

60. 002K1.02 001

Given the following plant conditions:

- The reactor is at 100% power

- Rod control is in automatic.

- Power Range nuclear instrument N-42 fails HIGH.

Which ONE of the following describes the rod control and plant response?

a. Rods move in until the power mismatch rate signal decays, then move out to

the original position to correct the temperature error.

,/b. Rods move in until the power mismatch rate signal decays, then remain at

the new position with a reduced T-avg.

c. Rods move out until the power mismatch rate signal decays, then move in to

the original position to correct the temperature error.

d. Rods move out until the high power rod block is reached, then remain at the

new position with a higher T-avg.

61. 002K4.05 001

Given the following plant conditions:

- Unit was at 100% power.

- A spurious Safety Injection occurs.

- Operators are responding per the EOP network and have just transitioned

to ES-1.1, "SI Termination".

- PZR level is 25% and slowly rising.

- Annunciators "PRT LEVEL HI/LO, PRESS HI, and TEMP HI" alarm.

Assuming all systems function as designed, which ONE of the following describes

the probable cause of this alarm?

a. Pressurizer PORVs, 1-PCV-68-340 and 334, have lifted.

b. CVCS Letdown Header Relief valve, 1-RLF-62-662 has lifted.

c. RHR Pump Discharge Relief valve, 1-RLF-63-620, has lifted.

,/d. RCP #1 Seal Leakoff Relief Valve, 1-RLF-62-636, has lifted.

Page 38

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

62. 010K6.04 001

Given the following plant conditions:

- Operating at 100% power.

- PZR PORV, PCV 68-340, is leaking through.

- PRT pressure increases resulting in rupture of the PRT diaphragm.

What effect will the rupture of the PRT diaphragm have on PRT temperature and

leakage through the PORV?

PRT Temp PORV Leakage

a. Rises Rises

b. Rises Drops

,/c. Drops Rises

d. Drops Drops

63. 010A3.01 001

Given the following plant conditions:

- Unit is operating at 100% power.

- PZR PORV testing is in progress

- While Operators are raising PRT level to reduce PRT Oxygen content the

PRT PRESS HI alarm annunciates.

Which ONE of the following automatic actions will occur?

",/a. The WDS vent header control valve PCV-68-301 will CLOSE.

b. The primary water supply valve, FCV-68-303 will CLOSE.

c. The PRT drain valve to RCDT FCV-68-310 will OPEN.

d. The PRT nitrogen supply isolation valve FCV-68-305 will CLOSE.

Page 39

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

64. 012K5.02 001

Which ONE of the following would result in the OPAT reactor protection trip

setpoint being reduced? Consider each parameter independently.

a. AT increasing.

,/b. Tavg increasing.

c. PZR pressure decreasing.

d. Reactor Power decreasing.

65. 012A2.04 001

Given the following plant conditions:

- The operating crew is responding to a reactor trip due to a loss of 120V

AC Vital Instrument Power Bd I.

- PZR pressure transmitter 68-334 (Channel II) failed LOW.

Which ONE of the following describes the plant response?

a. Both trains of SSPS SI master relays would actuate AND both trains of ECCS

equipment auto start.

,4/. Both trains of SSPS SI master relays would actuate BUT only "B" train ECCS

equipment auto start.

c. Only the "B" train SSPS SI master relays would actuate BUT both trains of

ECCS equipment auto start.

d. Only the "B" train SSPS SI master relays would actuate AND only "B" train

ECCS equipment auto start.

Page 40

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

66. 016K3.03 001

Given the following plant conditions:

- Unit is in Mode 3 with Tavg at 557 0 F.

- Steam Dump Mode selector switch in the STEAM PRESSURE mode.

- Pressure transmitter, 1-PT-1-33, fails HIGH

Which ONE of the following describes the effect on the Steam Dump system?

a. Only six valves will open and remain open.

b. Only six valves will open and then close when Tavg decreases to 550 0 F.

c. Twelve valves will open and will remain open.

",/d. Twelve valves will open and then close when Tavg decreases to 550'F.

67. 016K5.01 001

Which ONE of the following correctly describes the operation of the Median

Signal Select (MSS) circuitry associated with Steam Generator (S/G) controls

and protection?

a. The MSS averages three channels from each S/G and assigns all control

and protection functions to the average values.

b. The MSS looks at all three channels of each S/G, selects the median

channel and assigns all protection and control functions to that channel.

c. The MSS compares the Median value of all S/Gs, averages them, then uses

this value for all control functions and allows all channels to retain their

separation as protection channels.

,/d. The MSS looks at all three channels of each S/G, selects the median

channel for control and allows all channels to retain their separation as

protection channels.

Page 41

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

68. 026A2.09 001

Given the following plant conditions:

- Large break LOCA has occurred.

- Swapover to containment sump was unsuccessful and crew has

implemented ECA-1.1, "Loss of RHR Sump Recirculation".

- Containment Spray has been aligned to the containment sump.

- Unit Supervisor has directed the OAC to initiate makeup to the RWST.

Which ONE of the following lists the preferred makeup source to the RWST?

a. Transfer water from the Holdup Tank.

b. Transfer water from the Spent Fuel Pit.

,/c. Align Containment Spray to the RWST.

d. Align CVCS blender to makeup.

69. 029A1.02 001

Given the following plant conditions:

- Plant is in MODE 6 with refueling in progress.

- During movement of an irradiated fuel assembly from the core it is

dropped and severely damaged.

- The containment airborne radioactivity increases.

Which ONE of the following describes the ESF actuation that would occur?

a. OA Containment Isolation from high radiation detected by upper containment

radiation monitor, 1-RM-90-112.

b. OA Containment Isolation from high radiation detected by Containment Purge

Exhaust radiation monitor, 1-RM-90-130.

c. Containment Vent Isolation from high radiation detected by upper

containment radiation monitor, 1-RM-90-112.

vd. Containment Vent Isolation from high radiation detected by Containment

Purge Exhaust radiation monitor, 1-RM-90-130.

Page 42

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

70. 035G2.4.34 001

Given the following plant conditions:

- Operators are performing AOI-27, "Main Control Room

Inaccessibility".

- Crew is ready to transfer controls back to Main Control Room (MCR).

- Auxiliary Feedwater level controllers in the Aux. Control Room (ACR)

are in automatic controlling S/G levels at 38%.

Which ONE of the following actions should be performed to prevent sudden

changes in S/G levels when the controllers are transferred to the Main Control

room (MCR)?

a. Place MCR controller in automatic, this will allow it to automatically track the

corresponding controller in the ACR.

b. Plant conditions must be established to allow modulating components to be

full open or closed prior to transfer.

c. Place ACR and MCR controller in manual, when transferred to NORMAL,

Eagle 21 control will match the two controller's outputs.

/d. Place the MCR controller in manual and adjust the controller output to

match the output of the ACR controller then transfer.

Page 43

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26101

71. 035K4.06 001

Given the following plant conditions:

- The unit is operating at 100% power

- The controlling #3 S/G pressure transmitter fails LOW.

Which ONE of the following describes the effect this will have on indicated steam

flow and the initial #3 S/G FW Reg valve response?

Indicated Steam Flow Valve Response

a. Drop FCV will open

A1. Drop FCV will close

c. Rise FCV will open

d. Rise FCV will close

72. 039A1.03 001

Given the following plant conditions:

- Startup in progress.

- Operators are warming the main steam lines using the MSIV bypasses.

- The OAC observes that the RCS has cooled down 108'F in the past hour.

- The CRO observes that the main steam lines have heated up 102 0 F in

the past hour.

Which ONE of the following indicates the actions that should be taken by the

operators and why?

,/a. Close the MSIV bypass valves; RCS cooldown limit was exceeded.

b. Close the MSIV bypass valves; main steam line heat-up limit was

exceeded.

c. Close the MSIV bypass valves; both RCS and main steam line limits were

exceeded.

d. Leave MSIV bypass valves open; NO RCS or main steam line limits were

exceeded.

Page 44

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

73. 039A3.02 001

Given the following plant conditions:

- Reactor coolant system pressure has decreased to 1930 psig during a

plant cooldown.

- The operator has placed the Low Steam Line Pressure Block switches

HS-63-135 A & B to BLOCK.

Which ONE of the following describes the status of the Safety Injection and Main

Steam Line isolation signals?

a. Only the low steamline pressure MSIV isolation is blocked; low steamline

pressure SI is operational.

b. Only the low steamline pressure SI signal is blocked; low steam line pressure

MSIV isolation is operational.

c. Both the high steamline pressure negative rate MSIV isolation and high

steamline pressure negative rate SI signal are operational,

"/d. Both the low steam line pressure MSIV isolation and low steam line pressure

SI signal are blocked.

Page 45

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

74. 063K2.01 001

Given the following plant conditions:

- Reactor tripped on Io-lo SG level.

- All MSIVs are closed.

- All feedwater reg and bypass reg valves are closed.

- Turbine Driven AFW pump is the ONLY AFW pump running.

- All DGs are running unloaded.

Which ONE of the following correctly lists the 125V DC Vital Battery Board(s) that

is/are deenergized?

a. Only Board I.

b. Only Board Ill.

,/c. Board I and II.

d. Board I and Ill.

75. 064K2.03 001

Given the following plant conditions:

- Unit at 100% power.

- 1A-A D/G Battery Abnormal annunciation is in alarm

- An AUO is dispatched and confirms that the power supply to the 1A-A

D/G Battery Charger is deenergized.

A loss of the bus from which ONE of the following power supplies would account

for this condition?

a. 480V Auxiliary Common Board

,/b. 1A2-A 480V Diesel Aux Board

c. 120V Vital Instrument Power Board I-I1l

d. 1A1-A 480V Reactor MOV Board

Page 46

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

76. 064K6.08 001

Given the following plant conditions:

Plant is at 100% power

- IA-A Diesel Generator (D/G) running for a surveillance test.

Which ONE of the following identifies how fuel oil makeup occurs to the 1A-A

D/G Day Tanks while the D/G is running?

,/a. Automatically from the 7-day tanks using the D/G mounted fuel oil

transfer pumps.

b. Manually from the 7-day tanks using the D/G mounted fuel oil transfer

pumps.

c. Automatically from the south (No. 1) Fuel Oil Storage Tank using the D/G

building transfer pump.

d. Manually from the south (No. 1) Fuel Oil Storage Tank using the D/G

building transfer pump.

77. 073K1.01 001

Given the following plant conditions:

- Unit is at 100% power

- High radiation alarms are in on Steam Generator Blowdown (SGBD)

radiation monitors 1-RM-90-120 and 121.

Which ONE of the following describes the SGBD System response?

a. The SGBD Containment isolation valves, FCV-15-181 through 184, close.

,/b. The SGBD Cooling Tower blowdown isolation valve, FCV-15-44, closes.

c. The SGBD to Condensate Header isolation Valve, FCV-15-6, closes.

d. The SGBD flow control valve, FCV-15-43, closes.

Page 47

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

78. 075K3.07 001

Given the following conditions:

- A loss of offsite power has occurred.

- Tavg is 557'F.

- Steam Dump controls are in the Steam Pressure mode.

- Steam dump demand is manually increased to begin cooldown.

- Steam Dump valves will NOT open.

Which ONE of the following explains why the Steam Dump valves will NOT open?

a. P-4, Reactor Trip, has not been actuated.

• /b. C-9, Condenser Available, interlock is not met.

c. P-12, Lo-Lo Tavg, has disarmed the Steam Dump system.

d. C-7, Load Rejection controller, has not been actuated.

79. 075A4.01 001

Given the following plant conditions:

- Reactor trip and safety injection occurred while the plant was operating at

100% power.

- Four ERCW pumps were running in their normal alignment before the SI

occurred.

Which ONE of the following identifies ERCW pump status after the SI and the

effect it has on the Condenser Circulating Water (CCW) system make-up?

a. Four ERCW pumps running; CCW make-up is provided only from ERCW

since RCW bypass strainer is isolated.

b. Eight ERCW pumps running; CCW make-up is provided only from RCW

since ERCW is routed through the overflow structure.

,/c. Four ERCW pumps running; CCW make-up provided from both RCW and

ERCW.

d. Eight ERCW pumps running; CCW make-up is not required since the unit is

tripped.

Page 48

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01126/01

80. 005K4.07 001

Given the following plant conditions:

- Unit was operating at 100% power.

- A large break LOCA resulted in a reactor trip and safety injection.

- Alignment to Cold Leg Recirculation is in progress.

- 1-FCV-63-8, 1A-A RHR Pump to CCP suction, will NOT open from the

Control Room.

Assuming all other equipment functions as expected, which ONE of the following

would prevent the valve from opening?

a. 1B-B SI pump minimum flow valve 1-FCV-63-175 open.

b. RHR pump suction from RWST 1-FCV-63-1 open.

"/c. Containment sump suction valve 1-FCV-63-72 closed.

d. The A train safety injection signal has been reset.

81. 005A2.01 001

Given the following plant conditions:

- Plant is at 100% power.

- While making plant rounds the Auxiliary Building NAUO discovered that

the 1A-A RHR Pump discharge flow indicating switch, 1-FIS-74-12, is

indicating 1500 gpm flow.

- An inadvertent safety injection occurs (SI).

Which ONE of the following identifies the impact of this instrument failure on

1A-A RHR pump mini-flow valve?

PRIOR to pump start AFTER Pump start

a. Open Open

,/b. Closed Closed

c. Closed Open

d. Open Closed

Page 49

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

82. 027K2.01 001

Given the following plant conditions

- Unit is at 100% power.

- 1A-A 6.9 KV Shutdown Board is out of service for maintenance.

- A reactor trip and safety injection (SI) is initiated due to a large break

LOCA.

- Automatic and manual "B" train Safety Injection fails to actuate.

With no further operator action, which ONE of the following describes the status

of the Emergency Gas Treatment System (EGTS)?

a. Both trains are running

b. Only "A" train is running

c. Only "B" train is running

Vd. Neither train is running

Page 50

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

83. 028K6.01 001

Given the following plant conditions:

- A large break LOCA occurs from 100% power.

"- "B" Hydrogen recombiner is tagged out.

"- "A" Hydrogen Recombiner has been placed in service.

- Subsequently the "A" Hydrogen Recombiner trips on overcurrent.

Which ONE of the following indicates how the concentration of hydrogen will be

controlled inside containment?

a. Containment Purge Supply and Exhaust fans are placed in service to dilute

the hydrogen concentration in containment.

b. A continuous vent path is provided that allows hydrogen to vent to the

annulus and then be removed by EGTS.

,/c. Air Return Fans create a mixing effect and the hydrogen igniters will burn

hydrogen to maintain it below an explosive concentration.

d. Emergency Gas Treatment System will remove hydrogen which collects in

the containment dome and discharge to the shield building vent.

84. 034K4.01 001

Which ONE of the following describes a feature of the Refueling Machine

designed to prevent the accidental release of a fuel assembly?

a. Gripper is mechanically engaged and disengaged by remote operating

handle on bridge and requires no power or air to operate.

,/b. Gripper requires air to disengage, however a mechanical latch prevents

gripper release under load even if air is applied.

c. Gripper disengages upon loss of air, however a mechanical latch prevents

griper release under load even if air is removed.

d. When gripper is engaged, operators mechanically lock gripper in place with

extension shaft which must be unlocked before gripper can release.

Page 51

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01126/01

85. 034A1.02 001

Given the following plant conditions:

- Core load is in progress.

- A failure of the Reactor Cavity Seal occurred.

- Cavity level is currently el. 748' and dropping slowly.

Which ONE of the following actions is required per AOI-29, "Dropped or

Damaged Fuel or Refueling Cavity Seal Failure"?

a. Align RHR suction to the RWST and discharge to the RCS through the hot legs.

,/b. Align CCP suction to RWST and discharge to the RCS through normal charging.

c. Start one SI pump in the cold leg injection flowpath for cavity makeup.

d. Align Refueling Water Purification pumps suction to RWST and discharge

directly to refueling cavity.

Page 52

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

86. 045A1.05 001

Given the following plant conditions:

- Unit 1 at 20% RTP

- Turbine trip occurs without a Reactor trip.

- The Steam Dump System is in T-avg Mode.

- Rod Control is in Automatic

Which ONE of the following describes the effect of the Turbine trip on the Steam

Dump and the Rod Control Systems? Assume no operator actions.

Va. The Steam Dump System will maintain T-avg at 5620 F with all Control Rods

fully inserted.

b. The Steam Dump System will maintain T-avg at 557' F with all Control Rods

fully inserted.

c. The Steam Dump System will maintain T-avg at 5620 F with Control Rods

maintaining z15% Reactor power due to C-5.

d. The Steam Dump System will maintain T-avg at 5570 F with Control Rods

maintaining ;15% Reactor power due to C-5.

87. 078K1.05 001

Which ONE of the following describes the source of instrument air and the effect

of a loss of instrument air on the Main Steam Isolation Valves (MSIVs)?

,/a. Non-essential air; MSIVs fail CLOSED.

b. Non-essential air; MSIVs fail OPEN.

c. Essential air; MSIVs fail CLOSED.

d. Essential air; MSIVs fail OPEN.

Page 53

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

88. G2.1.7 001

Given the following plant conditions:

- Unit at 100% RTP

- A S/G #1 safety valve begins leaking and power increases

to 105% RTP.

- The crew enters AOI-38 and reduces turbine load to 90% with the valve

position limiter.

- This load reduction caused reactor power to decrease to 95% RTP.

Which ONE of the following would be the correct crew response per AOI-38 if the

flow increased through the leaking safety valve causing the reactor power to

return to 101%?

a. Decrease turbine load at 5%/min to reduce reactor power to <100% and

continue AOI-38.

b. Use the valve position limiter to maintain power <100% and continue AOI-38.

Vc. Trip the reactor, close the MSIVs and bypasses, and go to E-0.

d. Trip the reactor, initiate SI, close the MSIVs and bypasses and go to E-0.

Page 54

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26101

89. G2.1.17 001

Given the following plant conditions:

- Inadvertent Safety Injection (SI) has occurred.

- The operating crew implemented the EOPs and is currently performing

ES-1.1, "SI Termination".

- The Unit Supervisor (US) directs the Operator at the Controls (OAC) to

"OPEN charging isolation 1-FCV-62-90 and 1-FCV-62-91".

Which ONE of the following communication exchanges between the OAC and

US would meet the minimum expectations of Watts Bar Communication

Guidelines for repeat back?

a. OAC - "Opening 1-FCV-62-90 and 1-FCV-62-91".

US - No response required.

b. OAC - "Opening the valves".

US - No response required.

,c. OAC -"Opening 1-FCV-62-90 and 1-FCV-62-91"

US - "That is correct".

d. OAC - "Opening the valves".

US - "That is correct".

Page 55

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

90. G2.1.19 001

Given the following plant conditions:

- Unit is at 100% power with automatic VCT make-up is in progress.

- A VCT level transmitter failure resulted in make-up stopping with

level at 34%.

Which ONE of the following identifies additional indications and effects of this

failure?

Indications Effects

a. Control board meter indicates 100% 1-LCV-62-118 full diverted

b. Control board meter indicates 0% 1-LCV-62-118 aligned to VCT

,/c. ICS computer indicates 100% 1-LCV-62-118 full diverted

d. ICS computer indicates 0% 1-LCV-62-118 aligned to VCT

91. G2.2.1 001

Given the following plant conditions:

- Unit is in Mode 3

- Reactor trip breakers are closed

- RCS Tavg is 559°F

- A dilution to obtain the calculated critical boron concentration in progress.

Which ONE of the following is allowed per GO-2, "Reactor Startup"?

a. Testing of one SRM.

b. Stopping of an operating RCP.

c. Withdrawal of the Shutdown Rods.

Ad. Energization of the PZR backup heaters.

Page 56

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

92. G2.2.13 001

Given the following plant conditions:

- Unit is operating at 100% power

- 1-FCV-62-93, Charging Flow Control Valve, is being tagged as a

boundary isolation valve for a clearance on the CVCS charging header.

Which ONE of the following is an acceptable for tagging the valve?

a. Tag the air isolation valve in the open position and tag the handswitch in the

closed position for 1-FCV-62-93.

,/b. Close the valve, install a jacking device, isolate the air supply for

1-FCV-62-93, and tag the jacking device.

c. Dog 1-FCV-62-93 closed with its handwheel, tag the valve handwheel, and

tag the air isolation valve.

d. Isolate and de-pressurize the air supply for 1-FCV-62-93 and tag the air

isolation valve.

93. G2.2.26 001

Given the following plant conditions:

- Unit is in Mode 6.

- Refueling operations are in progress.

- The 30th fuel assembly is being loaded into the core.

According to FHI-7, "Fuel Handling and Movement", which ONE of the following

would require fuel loading operations to be stopped immediately?

a. An unanticipated increase in count rate by a factor of two occurs on any

responding nuclear channel during any single loading step.

,/b. Communications is lost between Containment and the Control Room.

c. Water in the Spent Fuel Pit in not clear enough to view the Fuel top Nozzles

without supplemental lighting.

d. Boron concentration decreases by more than 10 ppm as determined by two

successive samples of Reactor Coolant.

Page 57

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

94. G2.2.28 001

Given the following plant conditions:

- Unit is in Mode 6.

- Refueling operations are in progress.

- An irradiated fuel assembly cannot be placed in its specified core

location.

Which ONE of the following describes an approved location for the fuel assembly

per FHI-7, Fuel Handling and Movement?

a. Fuel assembly can be placed in the New Fuel Elevator, but the elevator must

be full down with power removed.

b. Fuel assembly may be placed in a free-standing core location as long as no

other fuel assembly is free-standing.

c. Fuel assembly must be returned to the SFP until an alternate core location is

determined.

,/d. Fuel assembly may be temporarily stored in the RCCA change fixture.

Page 58

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

95. G2.3.1 001

The following conditions are encountered after a survey of a pump room in the

Auxiliary building:

- General area radiation level in the room 70 mrem/hr

- Radiation level 30 cm from the pump casing 350 mrem/hr

- Contamination levels 800 dpm/100cm 2 beta

0 dpm/100cm 2 alpha

Which ONE of the following identifies the correct radiological postings required to

reflect current radiological conditions for this room?

v/ a. High Radiation Area.

\ b. Contamination Area.

c. Radiation Area; Contamination Area.

d. High Radiation Area; Contamination Area.

96. G2.3.11 001

Which ONE of the following identifies the first radiation monitor that should

respond to a SGTR and the effect on the monitor?

a. Condenser Vacuum Exhaust Monitor RM-90-119 and the monitor will be

automatically isolated.

,/b. Condenser Vacuum Exhaust Monitor RM-90-119 and the monitor will NOT be

automatically isolated.

c. Steam Generator Blowdown Sample Monitor RM-90-120/121 and the monitor

will be automatically isolated.

d. Steam Generator Blowdown Sample Monitor RM-90-120/121 and the monitor

will NOT be automatically isolated.

Page 59

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

97. G2.4.1 001

Given the following conditions:

- Unit 1 in MODE 1 at 10% RTP.

- Turbine at 1800 rpm at no load (generator PCB open).

- Loss of offsite power occurs.

- Emergency Diesels fails to re-energize Shutdown Boards.

Which ONE of the following describes the correct usage of the Emergency

Instructions?

,/a. Go directly to ECA-0.0 without entering E-0.

b. Implement ECA-0.0 in conjunction with E-0.

c. Go to ECA-0.0 from E-0 after verifying reactor and turbine trip.

d. Complete E-0 IMMEDIATE ACTIONS then go immediately to ECA-0.0.

98. G2.4.19 001

A step in ES-1.3, "Transfer to RHR Containment Sump", reads as follows:

ISOLATE SI pump miniflow:

• CLOSE FCV-63-3.

• CLOSE FCV-63-175.

• CLOSE FCV-63-4.

The bullets ("-") indicate that:

a. The actions must be performed in the specified sequence, but once a step

is in progress, the next step may be started.

b. The actions must be performed and completed in the specified sequence.

c. These actions should have been completed, so only verification may be

required.

Vd. These actions must all be completed, but any sequence of completion is

allowed.

Page 60

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

99. G2.4.34 001

Given the following plant conditions:

- Control room was abandoned due to a fire.

- All controls have been transferred in accordance with AOI-30.2, Fire Safe

Shutdown.

- The plant is being maintained in Hot Standby

RCS temperature is being controlled using (1) and RCS pressure is

controlled using (2)  ?

a. (1) Condenser steam dumps; (2) PZR back-up heater group C.

b. (1) Condenser steam dumps; (2) PZR back-up heater groups A-A and B-B.

c. (1) Atmospheric steam dumps; (2) PZR back-up heater group C.

,/d. (1) Atmospheric steam dumps; (2) PZR back-up heater groups A-A and B-B.

Page 61

WATTS BAR NUCLEAR PLANT

REACTOR OPERATOR NRC EXAMINATION

01/26/01

100. G2.4.48 001

Following Safety Injection reset during ES-I.1 the following conditions exist:

- Tavg is 560TF.

- PZR level is 45%.

- PZR pressure is 2230 psig.

Which ONE of the following describes the PZR heater status the OAC would

observe?

a. Control group 1D OFF.

Backup group 1C OFF.

Backup group 1A-A OFF.

Backup group 1B-B OFF.

b. Control group 1D ON.

Backup group 1C OFF.

Backup group 1A-A OFF.

Backup group 1B-B OFF.

,/c. Control group 1D OFF.

Backup group 1C ON.

Backup group 1A-A OFF.

Backup group 1 B-B OFF.

d. Control group 1D OFF.

Backup group 1C OFF.

Backup group 1A-A ON.

Backup group 1B-B ON.

Page 62

FINAL SUBMITTAL

WATTS BAR EXAM

50-390, 391/2001-301

JANUARY 29 - FEBRUARY 6,

2001

FINAL SRO WRITTEN EXAMINATION

Lx) /77/ /Cý&/-9"

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26101

NAME SSN

1.0000 26. 0000

2. 0000 27. 0000

28. 0000

,.0000

4.@000 29. 0(D00

. ©0000 30. 0000

31. 0(D00

7.0000 32. 0000

8. 0000 33. 0000

9.0000

10. 0000 35. 0000

11. 0000 36.0000

12.00000

13. 0000 38. 0(D00

14. 0000D( 0000

,37. @(DODD@

39.

15. 0000 40. 0(D00

16. 0000D( 41. 0000

17. 0000D( 42. 0(D00

18. 0000 43. 0000

19. 0000 44. 0000

20. 0000D( 45. 0000

21. 0000 46. 0000D(

22. 0000D( 47. 0000

23. 0000 48.0000

24. 0000D(

25. 0000 50-.0000

Page 1

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

NAME SSN

51. 0000 76.0000

52. 0000 77. 0000

53 0000 78. 0000

54. 0000 70. 0000

55. 0000 800000DD(

56. 0000 81.0000

57. @(©D( 82-.0000

58.©000 13. 0000

59- 0000D( 84. 0000D(

60. 0000D( 85. 0000

61. 0000 86. 0000

62. 0000D( 87-.0000

63. 0000D( 88. 0000

64. 0000D( 89. 0000

65. 0000 90. 0000D(

66. 0000 91. 0000

67. 0000 92.0000

68. 0000 93. (o(00

,-, I a-...

69. 0000D( 94- 0000

70. 0000 95. 0000

71. 0000D( 96. 0000

72. 0000 97. 0000

73. 0000 98. 0000

74 0000 99. 0000

75. @ D000D loo-.0000

Page 2

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

1. 005AK3.02 001

Given the following plant conditions:

- Reactor is at 75% with a power increase in progress using control rods.

- The OAC determines that Control Bank D rod H-12 is not moving and is

14 steps below the other rods in D bank.

- Crew is performing AOI-2, "Malfunction of Reactor Control System" to

realign control rod H-12 with the bank.

-TAe~ tLj,4,oi ,-ok Aa& bee, rn,ýI'+40 ~-e)~(

Which ONE of the following describes how control rod H-12 will be realigned to

control bank D and how control bank insertion limit will change following the

realignment?

a. Control Bank D will be realigned to control rod H-12 and control bank D

insertion limit will be higher.

,/b. Control Bank D will be realigned to control rod H-12 and control bank D

insertion limit will be lower

c. Control rod H-12 will be realigned to Control Bank D and control bank D

insertion limit will be lower.

d. Control rod H-12 will be realigned to Control Bank D and control bank D

insertion limit will be higher.

Page 1

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26101

2. 011EK2.02 001

Given the following conditions:

- A large break LOCA occurred

- Operators have just completed swapover to Containment Sump

- A loss of offsite power occurs

Which ONE of the following describes the actions required for this condition?

a. Pull to lock SI pumps and CCPs until the RHR pumps have been restarted

after the shutdown boards are reenergized.

,t/. Pull to lock the CCPs until the RHR pumps are restarted after the shutdown

boards are reenergized.

c. Ensure both RHR pumps are started by the blackout sequencer after the

diesel generators reenergize the shutdown boards then restart the SI pumps.

d. Ensure all ECCS pumps are started by the blackout sequencer when the

diesel generators reenergize the shutdown boards.

3. 015AK1.05 001

Given the following plant conditions:

- Reactor power is stable at 30%

- Loop 1 RCP trips

Assuming reactor power remains constant, core exit temperature will:

,/a. increase, then stabilize at a higher value.

b. decrease, then stabilize at a lower value.

c. increase, then return to the original steady-state value.

d. decrease, then return to the original steady-state value.

Page 2

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

4. 017AK3.03 001

Given the following conditions:

- Unit at 60% power.

- Confirmed Loop 1 RCP shaft vibration of 25 mils.

Which ONE of the following statements is correct per AOI-5, "Unscheduled

Removal of One RCP", regarding the sequence of actions?

a. RCP should be tripped prior to the reactor trip to minimize pump damage.

b. The reactor should be tripped prior to tripping the RCP to prevent pressurizer

level from dropping below 17%.

c. RCP should be tripped prior to the reactor trip to prevent Reactor Coolant

Bus voltage from dropping and tripping additional RCPs.

Ad. The reactor should be tripped prior to tripping the RCP to prevent an

automatic trip and an unnecessary challenge to a safety system.

5. 017AA1.13 001

Given the following plant conditions:

- Unit was operating at 58% power.

- Problems with #4 RCP required the pump to be shut down

in accordance with AOI-5, "Unscheduled Removal of One RCP".

Which ONE of the following identifies the maximum power level allowed by AOI-5

for restart of #4 RCP?

,/a. P-10.

b. P-9.

c. P-8.

d. Mode 3.

Page 3

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

6. 024G2.4.16 001

Given the following plant conditions:

- Unit has experienced a Reactor trip.

- The crew transitions to ES-0.1, Reactor Trip Response.

- RCS temperature has dropped to 542 0 F.

- Step 2 RNO states:

- REFER to AOI-34, Immediate Boration.

As the procedure reader, which ONE of the following is the proper method of

applying this step?

a. Transition from ES-0.1 to AOI-34 and when AOI-34 is completed return to

ES-0.1.

b. Read steps from AOI-34 in conjunction with ES-0.1 on a not to interfere

basis.

,/c. Continue in ES-0.1 and assign AOI-34 to another control room team member.

d. Assign ES-0.1 to another control room team member and transition to

AOI-34.

Page 4

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

7. 024AK1.02 001

Given the following plant conditions:

- Plant was operating at 100% power when a Main Feedwater pump trip

resulted in a turbine runback.

- All systems in automatic and responded as expected to stabilize the

plant.

- Control rods inserted beyond the Lo-Lo Rod Insertion limits.

- Operators implemented AOI-34, "Immediate Boration", in accordance

with the ARI.

Which ONE of the following indicates the final, stable plant conditions

AFTER completion of the boration as compared to those PRIOR to the boration?

Reactor Power Rod Position Tavq

a. Same Higher Higher

,t/. Same Higher Same

c. Lower Lower Same

d. Lower Lower Lower

Page 5

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

8. 029EA1.02 001

Given the following plant conditions:

- ATWS without Safety Injection has occurred.

- Crew has implemented FR-S.1, "Nuclear Power Generation/ATWS", and

currently performing step 4 to borate the RCS.

Which ONE of the following identifies the correct Operator action that must be

taken in order to align charging pump suction?

a. CLOSE LCV-62-132 and 133, VCT outlet isolation, then OPEN LCV-62-135

and 136, RWST supply to charging pump suction.

,/b. OPEN LCV-62-135 and 136, RWST supply to charging pump suction, then

CLOSE LCV-62-132 and 133, VCT outlet isolation.

c. Verify LCV-62-135 and 136, RWST supply to charging pump suction AUTO

OPEN, then CLOSE LCV-62-132 and 133, VCT outlet isolation.

d. Verify LCV-62-135 and 136, RWST supply to charging pump suction and

LCV-62-132 and 133, VCT outlet isolation AUTO OPEN.

9. 055EA2.05 001

Given the following plant conditions:

- The reactor trips due to a loss of all AC power (Station Blackout)

- The crew is currently performing ECA-0.0, Loss of Shutdown Power.

- Non-essential 125V and 250V battery loads are being shed per

AOI-40, Station Blackout.

- The power loss occurred at 0938 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.56909e-4 months <br />.

Which ONE of the following is the latest time that AC power must be restored to

ensure the station batteries are not fully discharged?

a. 1138

,/b. 1338

c. 1538

d. 1738

Page 6

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

10. 055G2.4.45 001

Given the following plant conditions:

- Plant was operating at 100% power when a loss of offsite power

occurred.

- Emergency Diesel Generators (D/G) failed to start and tie on to their

associated 6.9KV Shutdown Boards.

- The operating Crew implemented ECA-0.0, "Loss of Shutdown Power".

- The OAC has started 1A-A D/G and re-energized it's associated

Shutdown Board.

- Annunciator, "LOGIC PNL 1A-A LOAD STRIP RELAYS OUT OF SYNC

OR UV TEST" (BO-AN alarm), is still LIT.

Which ONE of the following actions is required before this annunciator may be reset?

a. Reset D/G 1A-A 86 LOR relay.

,/b. Reset 1A-A Shutdown Board BOX and BOY relays.

c. Transfer 1A-A Shutdown Board to it's normal power supply.

d. Shutdown all the D/Gs that are not tied to associated Shutdown Board.

Page 7

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

11. 057AA1.05 001

Given the following plant conditions:

- Plant is operating at 100% power.

- A loss of 120VAC Vital Instrument Power Board 1-1 occurred.

- The crew implements AOI-25.01, "Loss of 120V AC Vital Instrument

Power Board 1-1".

Which ONE of the following identifies the train selector switches that must be

selected for automatic control of feedwater and which loop 1 feedwater/steam

flow indications are available?

Feedwater/Steam Flow Feedwater/Steam Flow

Selector Switches Indications

a. A train Channel I

b. A train Channel II

c. B train Channel I

,/d. B train Channel II

12. 059AK1.01 001

Given the following plant conditions:

- Plant is operating a 100% power.

- Plant systems aligned and operating normally.

- Annunciator, CCS HXA 1-RM-90-123 LIQ RAD HIGH, is in alarm.

Which ONE of the following lists the type and source of radiation sensed by the

radiation monitor that is in alarm?

,/a. Gamma; Thermal Barrier leakage.

b. Beta; Thermal Barrier leakage.

c. Gamma; RCP motor cooler leakage.

d. Beta; RCP motor cooler leakage.

Page 8

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

13. 069AK2.03 001

Which ONE of the following conditions concerning the Personnel Airlock would

exceed a Limiting Condition for Operation and require entering an Action

Statement of Technical Specifications?

a. The lower containment airlock fails its LLRT while control rod unlatching is in

progress.

b. Welding cables are laid through both lower containment airlock doors during

RCS fill and vent at the end of an outage.

c. The lower containment airlock door interlocks are defeated while reactor

vessel head is being tensioned.

vd. The outer and inner doors are opened simultaneously during a normal

cooldown prior to aligning RHR to the RCS.

14. 074EA2.04 001

Which ONE of the following is the reason S/Gs are depressurized to atmospheric

pressure during the performance of FR-C.1, "Response to Inadequate Core

Cooling"?

a. Reduces RCS temperature to increase the thermal driving head for natural

circulation.

b. Reduces RCS temperature to collapse any steam voids in the upper part of

the vessel.

c. Reduces RCS pressure which prevents the formation of superheated steam

in the core as water exceeds the critical point.

,/d. Reduces RCS pressure to allow the ECCS accumulators and RHR pumps to

inject water to the RCS.

Page 9

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01126/01

15. 074EK1.03 001

Given the following plant conditions:

- Inadequate core cooling conditions exist

- Crew is performing FR-C.1, Inadequate Core Cooling

Which ONE of the following sets of actions states the proper sequence of the

major action categories to be performed for removing decay heat from the core?

a. Rapid secondary depressurization; reinitiation of high head safety injection;

RCP restart

,/b. Reinitiation of high head safety injection; rapid secondary depressurization;

RCP restart

c. Rapid secondary depressurization; RCP restart; reinitiation of high head

safety injection

d. RCP restart; rapid secondary depressurization; reinitiation of high head safety

injection

16. 076AA1.04 001

Which ONE of the following correctly describes the indication on the main steam

line radiation monitors when the MR/HR AUTO pushbutton is lit on the RM-23

readout module?

a. Indicates low range output only.

,/b. Indicates high range output only.

c. Automatically switches between the low and high range outputs every 45

seconds.

d. Automatically switches between low and high range output based upon

activity level in order to maintain accurate indication.

Page 10

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26101

17. E01EK3.4 001

Once an operating crew has entered the EOP network, which ONE of the

following is the earliest that a transition may be made to ES-0.0, "Rediagnosis"?

,a. AFTER transition from E-0 and safety injection initiated.

b. AFTER transition from E-0 and NO safety injection initiated.

c. BEFORE transition from E-0 and safety injection initiated.

d. BEFORE transition from E-0 and NO safety injection initiated.

18. E02EA2.2 001

Given the following conditions:

- Main steam line break has occurred outside containment, resulting in

a reactor trip/safety injection (SI).

- MSIV closure stopped the steam release.

- SI termination criteria was met and the crew is currently terminating the

SI per ES-1.1, "SI Termination."

Which ONE of the following combinations of parameters would require an

immediate reinitiation of safety injection?

Maximum RCS RCS PZR

CNTMT Press Subcoolinq Pressure Level

a. 1 psig 75 0 F Stable 18%

b. 2 psig 72 0 F Decreasing 20%

c. 3 psig 87 0 F Decreasing 34%

-/d. 4 psig 60°F Stable 24%

Page 11

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

19. E06EK2.1 001

Given the following plant conditions:

- Operators are responding to a large break LOCA and have determined

that degraded core cooling conditions exist.

- The crew has implemented FR-C.2, "Degraded Core Cooling".

- Preparations are in progress to depressurize all intact S/Gs to

atmospheric pressure in accordance with FR-C.2.

Which ONE of the following is the reason the procedure directs all RCPs be

stopped prior to performing the depressurization?

a. Reduces the core AP which will enhance the ability of the RHR pumps to

inject into the core.

b. Minimizes heat input to the S/Gs allowing them to depressurize faster.

c. Limits heat removal requirements to the core decay heat only.

/d. Anticipates a loss of RCP #1 seal AP requirements.

20. E07EK2.1 001

Given the following plant conditions:

- A large break LOCA has occurred that resulted in saturated core cooling

conditions.

- RWST level is 28%

- Crew is performing step 4 of FR-C.3, Saturated Core Cooling to

establish SI pump valve alignment.

Which ONE of the following identifies valves that should be verified CLOSED

during performance of this step?

a. FCV-63-6, 7 and 177, SI pump and Charging pump suction from RHR.

b. FCV-63-47 and 48, SI pump suction valves

c. FCV-63-152 and 153, SI pump cold leg injection cross-tie valves

Vd. FCV-63-3, 4 and 175 SI pump mini-flow valves

Page 12

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

21. E09G2.1.34 001

Given the following plant conditions:

- Reactor trip has occurred in conjunction with a loss of offsite power.

- The operating crew is currently performing steps of ES-0.2, "Natural

Circulation Cooldown".

- Boration to Cold Shutdown boron concentration of 870 ppm has

been completed.

- Chemistry reports the following boron concentrations:

850 ppm in the pressurizer.

1000 ppm in the RCS cold legs.

Which ONE of the following explains the difference in the boron concentration

between the value calculated for Cold Shutdown and the values reported by

Chemistry?

,/a. Mixing only occurs in the active portions of the RCS cold legs causing RCS

boron concentration to be higher than calculated.

b. The cold legs remain subcooled during this event which causes boron to

concentrate in these areas.

c. PZR spray valves failed to automatically open on increasing pressure to

ensure mixing between the cold legs and PZR.

d. Due to the loss of power the PZR heaters are unavailable to promote mixing

between the loops and the PZR.

Page 13

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

22. E1OEA2.1 001

Given the following plant conditions:

- Reactor trip occurred with subsequent loss of RCPs.

- Operators have implemented ES-0.2, "Natural Circulation Cooldown".

- A cooldown rate of 25°F/hour has been established.

- RCS depressurization has been initiated while maintaining subcooling

> 165 0 F.

- Operators are monitoring PZR level and RVLIS for void formation.

- The OAC observes that loss of inventory in the Condensate Storage Tank

is imminent.

Which ONE of the following describes the appropriate procedural actions?

a. Stop the cooldown and remain in ES-0.2.

b. Raise the cooldown rate and remain in ES-0.2.

c. Transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in

Vessel (With RVLIS) and lower the cooldown rate.

,/d. Transition to ES-0.3, "Natural Circulation Cooldown With Steam Voids in

Vessel (With RVLIS) and raise the cooldown rate.

Page 14

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

23. E12EA2.2 001

Given the following plant conditions:

- Unit was at 100% power.

- A main steam line break occurred in the Turbine Building.

- Operators were unable to close the MSIVs and transitioned to

ECA-2.1, Uncontrolled Depressurization of All Steam Generators.

- SI termination steps are in progress.

- Loop 3 MSIV is closed locally.

- The CRO observes the #3 SG pressure increasing slowly.

Which ONE of the following actions should be performed?

a. Transition to E-2, "Faulted SG Isolation".

b. Transition to ES-1.1, "SI Termination".

c. Remain in ECA-2.1 until RHR is in service.

v'd. Remain in ECA-2.1 until SI is terminated.

24. E14EK3.2 001

Which ONE of the following describes the reason for tripping all RCPs during

the performance of FR-Z.1, "High Containment Pressure"?

a. Removes heat transferred to the Containment atmosphere from the RCP

motors.

b. Prevents depletion of primary inventory out of the break during a small

LOCA.

,c. Containment Isolation OB isolates cooling water to the RCPs and thermal

barriers.

d. Removes additional energy to the RCS during a break and subsequent

release to containment.

Page 15

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

25. 007EA2.06 001

Given the following plant conditions:

- Reactor was at 100% power.

- A rod control system failure causes all shutdown rods to fall into the

core.

- Power Range Indicators are at 6% and slowly decreasing (-0.1 DPM

SUR).

- E-0, "Reactor Trip or Safety Injection" is implemented.

- Operators actuate both manual Rx trip handswitches.

- Both Rx trip breakers remain closed.

Which ONE of the following identifies the correct procedural response?

a. Go to step 2 of E-0, "Reactor Trip or Safety Injection".

b. Hold at step 1 of E-0 until Rx trip breakers are open locally.

vcc. Transition to and perform FR-S. 1, "Nuclear Power Generation/ATWS", then

transition back to E-0.

d. Transition to and perform FR-S.1, "Nuclear Power Generation/ATWS", and

transition back to E-0 when control rods are fully inserted into the core.

Page 16

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01126/01

26. 007EK2.02 001

Given the following plant conditions:

- Unit 1 operating at 22% power.

- Reactor Trip Breakers "A" & "B" closed.

- Bypass Breaker B is racked in and closed.

- "B" Train SSPS Input Error Inhibit Switch is in INHIBIT for surveillance

testing.

Which ONE of the following describes the response of the Reactor Trip and

Bypass Breakers if RCS pressure drops below the Low Pressure Reactor trip

setpoint with no operator action?

a. Reactor Trip Breakers "A" & "B" open, Bypass Breaker "B" opens.

b. Reactor Trip Breaker "A" opens and "B" remains closed, Bypass Breaker "B"

remains closed.

c. Reactor Trip Breaker "B" opens and "A" remains closed, Bypass Breaker "B"

opens.

,/d. Reactor Trip Breaker "A" opens and "B" remains closed, Bypass Breaker "B"

opens.

Page 17

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01126/01

27. 008AK1.01 001

Given the following plant conditions:

- Unit was at 100% power.

- All systems operating in automatic and all plant parameters at their

normal values.

- 1-PCV-68-340 failed partially open.

Which ONE of the following identifies the approximate maximum expected

temperature of the steam entering the PRT if the PRT pressure does not

exceed 45 psig?

a. 228 0 F.

b. 250 0 F.

c. 275°F

,/d. 290°F

28. 027AA2.02 001

Given the following plant conditions:

- The plant is at steady state 100% power equilibrium xenon with all

control systems in automatic.

- Pressurizer level control is transferred to MANUAL and level is slowly

increased to 75% and maintained.

Which ONE of the following describes the PZR pressure response?

a. Pressure is essentially unaffected.

b. Pressure will continuously cycle between 2235 and 2260 psig.

c. Pressure will increase until the spray valves open and control pressure at

2260 psig.

,/d. Pressure will increase until the spray valves open and slowly return pressure

to steady state 2235 psig.

Page 18

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

29. 027AK3.02 001

Given the following plant conditions:

- The Unit is at 100% load.

- Pressurizer pressure channel selector switch, 1-XS-68-340D, is in the

PT-68-340 & 334 position.

- Instrument Maintenance has 1-PT-68-323 (CH III) OOS for a loop calibration.

- PZR Pressure transmitter, 1-PT-68-334 (CH II) has just failed AS IS.

- The operating crew implements AOI-18, "Malfunction of Pressurizer Pressure

Control System".

Which ONE of the following channels will be selected on 1-XS-68-340D and

position of the master controller following completion of AOI-1 8, Malfunction of

Pressurizer Pressure Control System?

a. Channel I and III selected with 1-PIC-68-340A in AUTO.

b. Channel I and III selected with 1-PIC-68-340A in MANUAL.

,/c. Channel I and IV selected with 1-PIC-68-340A in AUTO.

d. Channel I and IV selected with 1-PIC-68-340A in MANUAL.

Page 19

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

30. 032AK3.02 001

Given the following plant conditions:

- The Unit is in MODE 6.

- Source Range Monitor (SRM) NI-132 has failed LOW resulting in a loss

of the audio count rate signal.

WHICH ONE of the following describes the actions necessary to restore the

audio count rate signal to the control room.

,a. Place the audio count rate CHANNEL SELECTOR switch on the front of the

Audio Count Rate Drawer to the SR N31 position.

b. Place the audio count rate CHANNEL SELECTOR switch on the front of the

Audio Count Rate Drawer to the SR N32 position.

c. Place the AMPLIFIER SELECT switch on the rear of the audio count rate

drawer assembly to the Al position.

d. Place the AMPLIFIER SELECT switch on the rear of the audio count rate

drawer assembly to the A2 position.

Page 20

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

31. 033AA1.01 001

Given the following plant conditions:

- A Reactor startup in progress.

- Reactor power is stable at 2 x 10-2% power on the Intermediate Range

- Intermediate Range channel N-135 was declared inoperable and

removed from service per AOI-4, "Nuclear instrumentation Malfunction".

Which ONE of the following describes the plant response if an I&C Technician

mistakenly removes the control power fuses for N-135 during troubleshooting

activities?

,/a. The trip bistable deenergizes and a reactor trip occurs because power is

below P-10.

b. The trip bistable deenergizes, however NO trip occurs because N-135 is

bypassed.

c. The trip bistable energizes, however NO trip occurs because N-135 is

bypassed.

d. The trip bistable energizes and a reactor trip occurs because power is below

P-10.

Page 21

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

32. 038EK1.01 001

Given the following plant conditions:

- Steam Generator Tube Rupture has occurred.

- Crew has implemented E-3, "Steam Generator Tube Rupture".

- The operators have completed cooldown to target incore temperature of

4800F.

Which ONE of the following identifies the pressure that steam dumps will be set

to control RCS temperature at 480°F?

a. 580 - 585 psig.

-b. 550 - 555 psig.

c. 580 - 585 psia.

d. 550 - 555 psia.

33. 058AK3.01 001

Given the following plant conditions:

- AUO reports Emergency Diesel Generator (D/G) 1A-A has lost 125V DC

control power from it's associated Diesel Battery Distribution Panel

- D/G 1A-A is NOT running.

Which ONE of the following describes how this loss of DC control power would

affect D/G operation?

a. D/G would start in response to an automatic or manual start signal.

,/b. D/G cannot be started by automatic or manual start signal.

c. D/G can only be started manually from local control panel.

d. D/G can only be started manually from the MCR panel.

Page 22

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

34. 060AA2.05 001

Given the following conditions:

- Unit at 100% power.

- The Control Room Air Intake radiation monitor, 1-RM-90-125, alarms.

Which ONE of the following describes the response of the Control Building

Ventilation System?

-/a. Pressurization fans inlet dampers CLOSE

Emergency Pressurization fans inlet dampers OPEN

Air cleanup fans inlet dampers OPEN

b. Pressurization fans inlet dampers OPEN

Emergency Pressurization fans inlet dampers CLOSE

Air cleanup fans inlet dampers OPEN

c. Pressurization fans inlet dampers CLOSE

Emergency Pressurization fans inlet dampers OPEN

Air cleanup fans inlet dampers CLOSE

d. Pressurization fans inlet dampers OPEN

Emergency Pressurization fans inlet dampers CLOSE

Air cleanup fans inlet dampers CLOSE

Page 23

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

35. 060AA2.04 001

Given the following plant conditions:

- A Gas Decay Tank release in progress with ABGTS running for dilution

air flow.

- A leak occurs on the waste gas compressor which results in a gas

release to the Auxiliary Building.

- 0-RE-90-1 01, Auxiliary Building Vent Monitor, is in alarm.

Which ONE of the following indicates the effect this leak will have on the plant?

(Assume no operator action)

a. Gas Decay Tank release will be terminated; ABGTS will be stopped.

b. Gas Decay Tank release will be terminated; ABGTS will continue to run.

c. Gas Decay Tank release will continue; ABGTS will be stopped.

,/d. Gas Decay Tank release will continue; ABGTS will continue to run.

36. 065AA1.04 001

Following an automatic start due to low instrument air pressure, which ONE of

the following describes what will cause Aux Air Compressors to shutdown?

,'a. Running unloaded for 5 minutes.

b. Running unloaded for 10 minutes.

c. Low crankcase oil pressure.

d. High discharge air temperature.

Page 24

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

37. E03EK1.3 001

Given the following plant conditions:

- A small break LOCA has occurred

- 1B-B CCP and SIP failed to start and could not be started manually.

- E-1 is completed and transition to ES-1.2, "Post LOCA Cooldown and

Depressurization", made.

- 6.9kV Shutdown Board 1A-A is de-energized due to a fault

- The following conditions are noted by the OAC

- RCS pressure is 1600 psig

- Containment pressure is 6 psig

Which ONE of the following describes the action that should be taken and the

basis for that action?

a. All RCPs should be stopped to limit heat input during the RCS cooldown.

,/b. All RCPs should be stopped because OB isolation has occurred.

c. All RCPs should NOT be stopped because no CCP or SIP is injecting into the

RCS.

d. All RCPs should NOT be stopped because the RCS pressure is above 1500

psig.

38. E03EK2.2 001

Which ONE of the following is the significance of draining the SG U-tubes and

blowing the inverted "loop seal" during a cold leg small break LOCA?

Va. A steam vent path is established from the core to the break location and

mass loss from the system is decreased.

b. Core cooling will be lost after the loop seal is blown due to increased injection

flow being diverted to the break location.

c. RCS pressure control will be lost resulting in a challenge to Pressurized

Thermal Shock limits.

d. The heat sink effect of the water in the "crossover" leg is lost when the loop

seal is lost resulting in a degraded core cooling.

Page 25

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01126/01

39. E05EK2.1 001

Given the following plant conditions:

- Reactor trip and safety injection occurred.

- The crew implemented FR-H.1, "Loss of Secondary Heat Sink" due to

heat sink red path.

- Operators are preparing for main feedwater startup.

Which ONE of the following lists the minimum actions required to reset Main

Feedwater Pump 1A?

a. Reset safety injection and cycle reactor trip breakers.

b. Reset safety injection and reset feedwater isolation signal.

c. Cycle the reactor trip breakers and reset feedwater isolation signal.

",/d. Reset safety injection, cycle reactor trip breakers, and reset feedwater

isolation signal.

40. E1 EA1.2 001

Given the following plant conditions:

- Reactor trip and SI occurred at 0200 due to a small LOCA.

- At 0300 the crew transitioned to ECA-1.1, "Loss of RHR Sump

Recirculation", due to the failure of both RHR pumps.

- Crew has reduced ECCS flow to 1 SIP and 1 CCP per ECA-1.1.

- At 0500 the crew is performing step 17 RNO to establish the minimum

required ECCS flow to remove decay heat.

Using Figure 1 from ECA-1.1, which ONE of the following flow rates would satisfy

the intent of the RNO?

a. 170 gpm

,/b. 210 gpm

c. 240 gpm

d. 280 gpm

Page 26

C:3

z

I

CD,

CD,

U,)

CA,

m

C')

C-,

m

(D

-I

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01126/01

41. 028G2.2.9 001

Given the following plant conditions:

- The Unit is at 100% power.

- PZR level channel 1-LT-68-335 has failed HIGH

- Operating nrew hat addressed the failure per AOI-20, Malfunction of

Pressurizer Level Control

In response to the failure, which ONE of the following will most likely require a

safety evaluation?

a. A non-intent procedure change to AOI-20 is submitted to clarify a step.

,/b. A special test is performed on PZR level channel 1-LT-68-335 to determine

automatic actions.

c. A surveillance is required to be performed on channel 1-LT-68-339 while

1-LT-68-335 is out of service.

d. Post maintenance test is required to be performed on 1-LT-68-335 prior to

returning channel to service.

42. 036AA2.01 001

Given the following plant conditions:

- Plant is in Mode 6 with core offload in progress.

- The fuel assembly being withdrawn into the refueling mast is dropped

onto the lower core plate.

- The refuel crew observes bubbles coming from the dropped fuel

assembly.

Which ONE of the following identifies the most likely indications/actions as a

result of this incident?

,/a. Upper Cntmt area radiation monitor, 1-RM-90-59, alarms only.

b. Spent Fuel Pit area radiation monitor, 1-RM-90-102, alarms only.

c. Shield Bldg vent monitor, 1-RM-90-400, initiates Containment Vent Isolation.

Page 27

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

43. 036AK1.03 001

Which ONE of the following describes why the baseline count rate used for

developing the 1/M plot must be re-calculated following movement of any source

bearing fuel assembly ?

a. Re-verify the operability of the source range instruments.

,,t. Ensures an accurate 1/M plot to monitor subcriticality.

c. Determine adequate shutdown margin during refueling.

d. Readjust the setpoint for the High Flux at Shutdown alarm.

44. 001K5.28 001

Given the following plant conditions:

- The Unit is at 1% power after an extended shutdown.

- Core burnup is 2000 MWD/MTU.

- RCS boron concentration is 1000 ppm.

- Control rods at 175 steps

- The STA has determined that 236 pcm of reactivity must be added to

increase power to 10%.

Using the attached NUPOP curve and assuming no control rod movement, which

ONE of the following identifies the final boron concentration of the RCS after the

reactivity change has been made?

,/a. 966 ppm

b. 969 ppm

c. 1031 ppm

d. 1034 ppm

Page 28

WESTINGHOUSE PROPRIETARY CLASS 2C

-6. 0

-6. 5

00

-7.

0

0

0

-7.

5 -

°OL

EO ,°

Eiff

-8.

Pz

Q*

4

H

-8.

-9.0 .I . . I I. I. I

IIII

I . 1

0

1 1 , 1I

200 400 600 800 1000 1200 1400 1600 1800 2000

BORON CONCENTRATION (PPM)

Figure 6-22 Differential Boron Worth Versus Boron Concentration

at BOL, MOL, and EOL, HZP, With No Xenon

WCAP-15562 (Rev. 0) Bumup Dependent Parameters 6 - 27

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

45. 001K6.02 001

Unit is operating at 100% power with all systems in their normal configuration,

when Auctioneered High Tavg fails LOW.

Which ONE of the following describes the plant response?

a. Control rods will step in; Charging Flow Control valve, 1-FCV-62-93, opens.

,/b. Control rods will step out; Charging Flow Control valve, 1-FCV-62-93, closes.

c. Control rods will not move; Charging Flow Control valve, 1-FCV-62-93, opens.

d. Control rods will not move; Charging Flow Control valve, 1-FCV-62-93, closes.

46. 003G2.4.48 001

Given the following plant conditions:

- Unit is operating at 20% power with a startup in progress.

- A problem develops which requires removal of Loop 1 RCP

- At 1101, using ICS, you determine the following conditions exist:

- Motor Bearing Temperature is 180°F and increasing at 1F/min.

- Motor Winding Temperature is 315°F and stable.

- Pump Bearing Temperature is 220°F and increasing at 1lF/min.

Which ONE of the following correctly describes when loop 1 RCP must be

removed from service and the effects on loop 1 steam flow when the RCP is

stopped?

,/a. 1101; RCS loop 1 hot leg temperature decreases; Steam flow decreases.

b. 1101; RCS loop 1 hot leg temperature increases; Steam flow decreases.

c. 1106; RCS loop 1 hot leg temperature decreases; Steam flow increases.

d. 1106; RCS loop 1 hot leg temperature increases; Steam flow increases.

Page 29

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

47. 003A1.08 001

Given the following plant conditions:

- The Unit is operating at 100% power.

- All systems are operating normal.

- Annunciator "RCP #1 Seal Outlet Temp Hi" alarm actuates.

- The operator verifies that ALL RCP seal temperatures are 180'F rising.

Which ONE of the following is the most probable cause of this alarm?

a. The Charging Pump suction has swapped to the RWST.

b. The operator has just placed Excess Letdown in service at maximum flow

rate.

,/c. The Letdown Heat Exchanger temperature control valve 1-TCV-70-192 has

failed closed.

d. A loss of control air to charging flow control valve 1-FCV-62-93.

48. 004K3.01 001

Given the following conditions:

- Reactor power 35%.

- Turbine load 32%

- Control Rods are in AUTOMATIC.

- CVCS Mixed Bed A was placed in service resulting in a T-avg increase

to 571 OF.

Which ONE of the following describes the response of the rod control system?

(assume no operator action)

a. Rods will step in at 8 steps per minute.

,/b. Rods will step in at 40 steps per minute.

c. Rods will step in at 64 steps per minute.

d. Rods will step in at 72 steps per minute.

Page 30

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01126/01

49. 004K2.03 001

Given the following plant conditions:

- The unit is at 100% power with 1A-A CCP is in operation.

- A loss of offsite power occurs

- All appropriate loads sequence onto the Shutdown Boards

- The crew has implemented E-0, "Reactor Trip or Safety Injection"

- While the immediate actions are being completed, a safety injection

signal (SI) is received.

Which ONE of the following describes the response of the Centrifugal Charging

Pumps (CCPs)?

a. 1A-A CCP load sheds on the SI signal, and both CCPs auto sequence on the

shutdown boards.

b. 1A-A CCP load sheds on the SI signal, and must be restarted manually by

the operator.

c. 1A-A CCP does not load shed on the SI signal, and 1B-B CCP auto

sequences on the shutdown boards.

,/d. Both CCPs remain energized and running following the SI signal.

Page 31

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

50. 013K2.01 001

Given the following:

- 1A-A and 1B-B SI Pump breakers are "Racked In".

- A fuse blows in the NORMAL DC Trip circuit for the 1A-A Sl pump.

- A safety injection (SI) actuation occurs.

Which ONE of the following describes the response of the SI Pumps to the Sl

signal?

a. 1B-B Sl Pump will auto start, but 1A-A SI Pump will not auto start until the

control power supply is transferred.

b. 1B-B Sl Pump will auto start, but 1A-A SI Pump will not auto start and must

be started from the MCR handswitch.

,/c. Both Sl Pumps will auto start, but the 1A-A Sl Pump cannot be stopped from

the MCR.

d. Both SI Pumps will auto start, but the 1A-A Sl Pump cannot be stopped

mechanically at the breaker.

51. 013K4.08 001

Which ONE of the following describes the logic for Safety Injection (SI) actuation

handswitches and reset pushbuttons?

a. Each actuation handswitch initiates both trains of SI.

Each reset pushbutton resets both trains of SI.

,/b. Each actuation handswitch initiates both trains of SI.

Each reset pushbutton resets only it's associated train of SI.

c. Each actuation handswitch initiates only it's associated train of SI.

Each reset pushbutton resets only it's associated train of SI.

d. Each actuation handswitch initiates only it's associated train of SI.

Each reset pushbutton resets both trains of SI.

Page 32

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

52. 015A2.03 001

Given the following plant conditions:

- Unit is operating at 75% power

- A plant transient has resulted in a xenon oscillation

- Control rods are currently at 216 steps on D bank

Which ONE of the following is the effect of the xenon oscillation on NIS and the

action required to dampen the oscillation?

Va. The oscillation affects AFD and is dampened by inserting control rods at its

most positive peak.

b. The oscillation affects AFD and is dampened by inserting control rods at its

most negative peak.

c. The oscillation affects QPTR and is dampened by dropping turbine load at its

highest value.

d. The oscillation affects QPTR and is dampened by dropping turbine load at its

lowest value.

Page 33

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

53. 017A3.01 001

Given the following plant conditions:

- A small break LOCA has occurred.

- The crew responded lAW EOPs and tripped the RCPs when required.

- The crew is currently in ES-1.2, "Post LOCA Cooldown And

Depressurization".

- RCS pressure is 1490 psig.

- Wide range Tc's are 505°F and decreasing slowly.

- Wide range Th's are 515'F and decreasing slowly.

- Core exit thermocouples (CETC) are 551'F and stable.

- Containment pressure is 1.5 psig.

- SG levels are being maintained at 38%.

- SG pressures are 715 psig and decreasing slowly.

Which ONE of the following describes the status of natural circulation for the

existing plant conditions?

,/a. Cannot be assured, since there is inadequate sub-cooling.

b. Cannot be assured, since SG parameters are not satisfied.

c. Cannot be assured, since CETCs are not decreasing.

d. Exists since all natural circulation criteria are met.

Page 34

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

54. 022K4.03 001

Given the following plant conditions:

- Reactor trip & Safety Injection occurred due to Large Break LOCA.

- Containment OB isolation has occurred.

- All systems responded normally.

Which ONE of the following describes the response of the Lower Compartment

Coolers when OB is reset?

a. Fans in A-P-AUTO start.

Cooler ERCW isolation valves open.

,/b. Fans in A-P-AUTO start.

Cooler ERCW isolation valves remain closed.

c. Fans in A-P-AUTO remain off.

Cooler ERCW isolation valves open.

d. Fans in A-P-AUTO remain off.

Cooler ERCW isolation valves remain closed.

55. 022A4.02 001

Given the following plant conditions:

- Main Steam Line Break occurred inside containment causing a reactor

trip and safety injection.

- Operators have implemented the EOPs.

- Containment pressure is 3.2 psig and dropping.

- OAC observes the "INSTR ROOM COOLER A/B FLOW LOW" alarm LIT.

Which ONE of the following ESFAS signals caused the Incore Instrument Room

Cooling fans, circ pump, and chiller to shut down?

a. Containment vent isolation (CVI).

-b. OA containment isolation.

c. OB containment isolation.

d. Aux. Building Isolation (ABI)

Page 35

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

56. 025A3.02 001

Given the following plant conditions:

- Large break LOCA has occurred causing a reactor trip and safety

injection.

- OAC observes annunciator "Glycol Exp Tank Level Hi/Hi-Hi is LIT.

Which ONE of the following describes the most likely reason the annunciator is

LIT?

a. OA closes the glycol containment isolation valves; glycol inside containment

heats up and relief valves on the containment side of the isolation valves

relieve glycol into the glycol expansion tank.

,-b. OA closes the glycol containment isolation valves; glycol inside containment

heats up and expands into the glycol expansion tank.

c. 0B closes the glycol containment isolation valves; glycol inside containment

heats up and relief valves on the containment side of the isolation valves

relieve glycol into the glycol expansion tank.

d. 0B closes the glycol containment isolation valves; glycol inside containment

heats up and expands into the glycol expansion tank.

Page 36

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

57. 026A2.09 001

Given the following plant conditions:

- Large break LOCA has occurred.

- Swapover to containment sump was unsuccessful and crew has

implemented ECA-1.1, "Loss of RHR Sump Recirculation".

- Containment Spray has been aligned to the containment sump.

- Unit Supervisor has directed the OAC to initiate makeup to the RWST.

Which ONE of the following lists the preferred makeup source to the RWST?

a. Transfer water from the Holdup Tank.

b. Transfer water from the Spent Fuel Pit.

Vc. Align Containment Spray to the RWST.

d. Align CVCS blender to makeup.

58. 059K3.04 001

Given the following conditions:

- Unit is operating at 100% power.

- FCV-2-35, Condensate Short Cycle valve fails OPEN

Which ONE of the following describes the effect on reactor power and the correct

operator response?

Reactor power will:

a. Increase; Borate the RCS.

,/b. Increase; Reduce turbine load.

c. Decrease; Dilute the RCS.

d. Decrease; Raise turbine load.

Page 37

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26101

59. 061K5.02 001

Which ONE of the following describes the decay heat sources and design basis

for the Auxiliary Feedwater (AFW) System during a loss of offsite power?

a. Prevents relief through the PZR safety valves by removing core decay heat only.

b. Prevents relief through the S/G safety valves by removing core decay heat only.

,Ic. Prevents relief through the PZR safety valves by removing core decay heat

and stored RCS heat.

d. Prevents relief through the S/G safety valves by removing core decay heat

and RCP heat.

60. 063K2.01 001

Given the following plant conditions:

- Reactor tripped on Io-lo SG level.

- All MSIVs are closed.

- All feedwater reg and bypass reg valves are closed.

- Turbine Driven AFW pump is the ONLY AFW pump running.

- All DGs are running unloaded.

Which ONE of the following correctly lists the 125V DC Vital Battery Board(s) that

is/are deenergized?

a. Only Board I.

b. Only Board Ill.

,/c. Board I and 11.

d. Board I and Ill.

Page 38

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

61. 071A1.06 001

Given the following plant conditions:

- Unit is at 100% power.

- "A" Waste Gas Compressor is in service.

- Pressure in the "in service" Waste Gas Decay Tank (WGDT) is 60

psig.

- No WGDT release is in progress

- The relief valve on the "in service" WGDT begins to experience seat

leakage.

Which ONE of the following will provide the best indication that the relief valve on

the WGDT is leaking?

a. Increasing count rates on RM-90-101A, Auxiliary Building Vent Monitor.

,/4. Increasing count rates on RM-90-400, Shield Building Vent Monitor.

c. FCV 77-119, Plant Vent Flow Control valve, isolates due to high radiation.

d. The Waste Gas Vent Header pressure increases causing the Waste Gas

Compressor to run continuously.

Page 39

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

62. 072K1.02 001

Given the following plant conditions:

- A source check is being performed on Spent Fuel Pool Monitor (RE-90-102).

- Auto Block handswitches are in the OFF position.

Which ONE of the following will occur when the control switch is placed and held

in "SOURCE CHECK"?

a. The fuel handling area ventilation system is diverted to the suction of the

EGTS system.

b. The green light on the monitor goes out indicating that the monitor is being

source checked.

,/c. Auxiliary Building Ventilation isolates, but no Auxiliary Building isolation signal

is generated.

d. A Containment Ventilation Isolation signal is generated.

63. 002K1.02 001

Given the following plant conditions:

- The reactor is at 100% power

- Rod control is in automatic.

- Power Range nuclear instrument N-42 fails HIGH.

Which ONE of the following describes the rod control and plant response?

a. Rods move in until the power mismatch rate signal decays, then move out to

the original position to correct the temperature error.

,'b. Rods move in until the power mismatch rate signal decays, then remain at

the new position with a reduced T-avg.

c. Rods move out until the power mismatch rate signal decays, then move in to

the original position to correct the temperature error.

d. Rods move out until the high power rod block is reached, then remain at the

new position with a higher T-avg.

Page 40

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01126/01

64. 002K4.05 001

Given the following plant conditions:

- Unit was at 100% power.

- A spurious Safety Injection occurs.

- Operators are responding per the EOP network and have just transitioned

to ES-1.1, "SI Termination".

- PZR level is 25% and slowly rising.

- Annunciators "PRT LEVEL HI/LO, PRESS HI, and TEMP HI" alarm.

Assuming all systems function as designed, which ONE of the following describes

the probable cause of this alarm?

a. Pressurizer PORVs, 1-PCV-68-340 and 334, have lifted.

b. CVCS Letdown Header Relief valve, 1-RLF-62-662 has lifted.

c. RHR Pump Discharge Relief valve, 1-RLF-63-620, has lifted.

• /d. RCP #1 Seal Leakoff Relief Valve, 1-RLF-62-636, has lifted.

65. 010K6.04 001

Given the following plant conditions:

- Operating at 100% power.

- PZR PORV, PCV 68-340, is leaking through.

- PRT pressure increases resulting in rupture of the PRT diaphragm.

What effect will the rupture of the PRT diaphragm have on PRT temperature and

leakage through the PORV?

PRT Temp PORV Leakage

a. Rises Rises

b. Rises Drops

,Ic. Drops Rises

d. Drops Drops

Page 41

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

66. 010A3.01 001

Given the following plant conditions:

- Unit is operating at 100% power.

- PZR PORV testing is in progress

- While Operators are raising PRT level to reduce PRT Oxygen content the

PRT PRESS HI alarm annunciates.

Which ONE of the following automatic actions will occur?

,a. The WDS vent header control valve PCV-68-301 will CLOSE.

b. The primary water supply valve, FCV-68-303 will CLOSE.

c. The PRT drain valve to RCDT FCV-68-310 will OPEN.

d. The PRT nitrogen supply isolation valve FCV-68-305 will CLOSE.

Page 42

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

67. 011G2.4.45 001

Given the following plant conditions:

- Unit is operating at 100% power.

- Letdown isolation valve, 1-FCV-62-70, has failed CLOSED.

- The OAC reported annunciator, "PZR LEVEL HI-DEVN BACKUP HTRS

ON", LIT with PZR level at 72% and slowly rising.

Which ONE of the following identifies the procedural actions that should be taken

to address this transient if 1-FCV-62-70 could not be re-opened?

,/a. Close charging valves 1-FCV-62-90 and 91; Maintain seal flow between 8

13 gpm with 1-FCV-62-93, charging flow control; Place excess letdown in

service.

b. Close charging valves 1-FCV-62-90 and 91; Maintain seal flow between 8

13 gpm with 1-FCV-62-89, charging hdr-RCP seal flow control; Place

Back-up heaters to OFF.

c. Reduce charging flow to minimum with 1-FCV-62-89 and 93; Place Back-up

heaters OFF; Place excess letdown in service.

d. Reduce charging flow to minimum with 1-FCV-62-89 and 93; Maintain seal

flow between 8 - 13 gpm with 1-FCV-62-93, charging flow control; Place

excess letdown in service.

68. 012K5.02 001

Which ONE of the following would result in the OPAT reactor protection trip

setpoint being reduced? Consider each parameter independently.

a. AT increasing.

,4/. Tavg increasing.

c. PZR pressure decreasing.

d. Reactor Power decreasing.

Page 43

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

69. 012A2.04 001

Given the following plant conditions:

- The operating crew is responding to a reactor trip due to a loss of 120V

AC Vital Instrument Power Bd I.

- PZR pressure transmitter 68-334 (Channel II) failed LOW.

Which ONE of the following describes the plant response?

a. Both trains of SSPS SI master relays would actuate AND both trains of ECCS

equipment auto start.

,-b. Both trains of SSPS SI master relays would actuate BUT only "B" train ECCS

equipment auto start.

c. Only the "B" train SSPS SI master relays would actuate BUT both trains of

ECCS equipment auto start.

d. Only the "B" train SSPS Sl master relays would actuate AND only "B" train

ECCS equipment auto start.

70. 027K2.01 001

Given the following plant conditions

- Unit is at 100% power.

- 1A-A 6.9 KV Shutdown Board is out of service for maintenance.

- A reactor trip and safety injection (SI) is initiated due to a large break

LOCA.

- Automatic and manual "B" train Safety Injection fails to actuate.

With no further operator action, which ONE of the following describes the status

of the Emergency Gas Treatment System (EGTS)?

a. Both trains are running

b. Only "A" train is running

c. Only "B" train is running

,/d. Neither train is running

Page 44

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

71. 028K6.01 001

Given the following plant conditions:

- A large break LOCA occurs from 100% power.

- "B" Hydrogen recombiner is tagged out.

- "A" Hydrogen Recombiner has been placed in service.

- Subsequently the "A" Hydrogen Recombiner trips on overcurrent.

Which ONE of the following indicates how the concentration of hydrogen will be

controlled inside containment?

a. Containment Purge Supply and Exhaust fans are placed in service to dilute

the hydrogen concentration in containment.

b. A continuous vent path is provided that allows hydrogen to vent to the

annulus and then be removed by EGTS.

,/c. Air Return Fans create a mixing effect and the hydrogen igniters will burn

hydrogen to maintain it below an explosive concentration.

d. Emergency Gas Treatment System will remove hydrogen which collects in

the containment dome and discharge to the shield building vent.

72. 034K4.01 001

Which ONE of the following describes a feature of the Refueling Machine

designed to prevent the accidental release of a fuel assembly?

a. Gripper is mechanically engaged and disengaged by remote operating

handle on bridge and requires no power or air to operate.

,-b. Gripper requires air to disengage, however a mechanical latch prevents

gripper release under load even if air is applied.

c. Gripper disengages upon loss of air, however a mechanical latch prevents

griper release under load even if air is removed.

d. When gripper is engaged, operators mechanically lock gripper in place with

extension shaft which must be unlocked before gripper can release.

Page 45

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26101

73. 034A1.02 001

Given the following plant conditions:

- Core load is in progress.

- A failure of the Reactor Cavity Seal occurred.

- Cavity level is currently el. 748' and dropping slowly.

Which ONE of the following actions is required per AOI-29, "Dropped or

Damaged Fuel or Refueling Cavity Seal Failure"?

a. Align RHR suction to the RWST and discharge to the RCS through the hot legs.

,/b. Align CCP suction to RWST and discharge to the RCS through normal charging.

c. Start one Sl pump in the cold leg injection flowpath for cavity makeup.

d. Align Refueling Water Purification pumps suction to RWST and discharge

directly to refueling cavity.

74. 039A1.03 001

Given the following plant conditions:

- Startup in progress.

- Operators are warming the main steam lines using the MSIV bypasses.

- The OAC observes that the RCS has cooled down 108'F in the past hour.

- The CRO observes that the main steam lines have heated up 102'F in

the past hour.

Which ONE of the following indicates the actions that should be taken by the

operators and why?

,/a. Close the MSIV bypass valves; RCS cooldown limit was exceeded.

b. Close the MSIV bypass valves; main steam line heat-up limit was

exceeded.

c. Close the MSIV bypass valves; both RCS and main steam line limits were

exceeded.

d. Leave MSIV bypass valves open; NO RCS or main steam line limits were

exceeded.

Page 46

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

75. 039A3.02 001

Given the following plant conditions:

- Reactor coolant system pressure has decreased to 1930 psig during a

plant cooldown.

- The operator has placed the Low Steam Line Pressure Block switches

HS-63-135 A & B to BLOCK.

Which ONE of the following describes the status of the Safety Injection and Main

Steam Line isolation signals?

a. Only the low steamline pressure MSIV isolation is blocked; low steamline

pressure SI is operational.

b. Only the low steamline pressure SI signal is blocked; low steam line pressure

MSIV isolation is operational.

c. Both the high steamline pressure negative rate MSIV isolation and high

steamline pressure negative rate SI signal are operational.

,/d. Both the low steam line pressure MSIV isolation and low steam line pressure

SI signal are blocked.

Page 47

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

76. 064G2.2.18 001

Given the following plant conditions:

- Plant is in Mode 5.

- "A" train RHR is in operation controlling RCS temperature at 120'F.

- RCS level is at elevation 718'10"

- MEG requests that Emergency Diesel Generator (D/G) 1A-A be tagged

out to replace the voltage regulator with a new model.

Which ONE of the following describes how this request should be handled?

,/a. D/G 1A-A may NOT be removed from service at this time to protect

RHR train "A".

b. D/G lA-A may NOT be removed from service at this time since both the

1A-A and 1B-B D/G are required to be operable by Tech Specs.

c. D/G 1A-A may be removed from service at this time as long as one offsite

circuit is operable.

d. D/G 1A-A may be removed from service at this time as long as risk guidance

was obtained from the PSA engineering group.

77. 073K1.01 001

Given the following plant conditions:

- Unit is at 100% power

- High radiation alarms are in on Steam Generator Blowdown (SGBD)

radiation monitors 1-RM-90-120 and 121.

Which ONE of the following describes the SGBD System response?

a. The SGBD Containment isolation valves, FCV-15-181 through 184, close.

,/b. The SGBD Cooling Tower blowdown isolation valve, FCV-15-44, closes.

c. The SGBD to Condensate Header isolation Valve, FCV-15-6, closes.

d. The SGBD flow control valve, FCV-15-43, closes.

Page 48

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

78. 075K3.07 001

Given the following conditions:

- A loss of offsite power has occurred.

- Tavg is 557°F.

- Steam Dump controls are in the Steam Pressure mode.

- Steam dump demand is manually increased to begin cooldown.

- Steam Dump valves will NOT open.

Which ONE of the following explains why the Steam Dump valves will NOT open?

a. P-4, Reactor Trip, has not been actuated.

,/b. C-9, Condenser Available, interlock is not met.

c. P-12, Lo-Lo Tavg, has disarmed the Steam Dump system.

d. C-7, Load Rejection controller, has not been actuated.

79. 075A4.01 001

Given the following plant conditions:

- Reactor trip and safety injection occurred while the plant was operating at

100% power.

- Four ERCW pumps were running in their normal alignment before the SI

occurred.

Which ONE of the following identifies ERCW pump status after the SI and the

effect it has on the Condenser Circulating Water (CCW) system make-up?

a. Four ERCW pumps running; CCW make-up is provided only from ERCW

since RCW bypass strainer is isolated.

b. Eight ERCW pumps running; CCW make-up is provided only from RCW

since ERCW is routed through the overflow structure.

,/c. Four ERCW pumps running; CCW make-up provided from both RCW and

ERCW.

d. Eight ERCW pumps running; CCW make-up is not required since the unit is

tripped.

Page 49

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

80. 005K4.07 001

Given the following plant conditions:

- Unit was operating at 100% power.

- A large break LOCA resulted in a reactor trip and safety injection.

- Alignment to Cold Leg Recirculation is in progress.

- 1-FCV-63-8, 1A-A RHR Pump to CCP suction, will NOT open from the

Control Room.

Assuming all other equipment functions as expected, which ONE of the following

would prevent the valve from opening?

a. 1B-B SI pump minimum flow valve 1-FCV-63-175 open.

b. RHR pump suction from RWST 1-FCV-63-1 open.

,/c. Containment sump suction valve 1-FCV-63-72 closed.

d. The A train safety injection signal has been reset.

Page 50

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01126/01

81. 041G2.4.21 001

Given the following plant conditions:

- A reactor trip and turbine trip occurs while at 25% power due to lo S/G

level.

- Simultaneously, loop 4 Tcold fails HIGH.

- You are currently performing ES-0.1, Reactor Trip Response.

Which ONE of the following describes the response of the Steam Dump system

and the Steam Dump Mode Switch alignment when procedure is completed?

a. Load rejection arms Steam Dump valves;

Tavg will be reduced to no-load Tavg.

Mode switch in STEAM PRESS.

b. Load rejection arms Steam Dump valves;

Tavg will be reduced to Lo-Lo Tavg.

Mode switch in OFF.

c. Reactor trip arms Steam Dump valves;

Tavg will be reduced to no-load Tavg.

Mode switch in OFF.

,/d. Reactor trip arms Steam Dump valves;

Tavg will be reduced to Lo-Lo Tavg.

Mode switch in STEAM PRESS.

Page 51

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

82. 045A1.05 001

Given the following plant conditions:

- Unit 1 at 20% RTP

- Turbine trip occurs without a Reactor trip.

- The Steam Dump System is in T-avg Mode.

- Rod Control is in Automatic

Which ONE of the following describes the effect of the Turbine trip on the Steam

Dump and the Rod Control Systems? Assume no operator actions.

,/a. The Steam Dump System will maintain T-avg at 5620 F with all Control Rods

fully inserted.

b. The Steam Dump System will maintain T-avg at 5570 F with all Control Rods

fully inserted.

c. The Steam Dump System will maintain T-avg at 5620 F with Control Rods

maintaining &15% Reactor power due to C-5.

d. The Steam Dump System will maintain T-avg at 557' F with Control Rods

maintaining z1 5% Reactor power due to C-5.

83. 078K1.05 001

Which ONE of the following describes the source of instrument air and the effect

of a loss of instrument air on the Main Steam Isolation Valves (MSIVs)?

Va. Non-essential air; MSIVs fail CLOSED.

b. Non-essential air; MSIVs fail OPEN.

c. Essential air; MSIVs fail CLOSED.

d. Essential air; MSIVs fail OPEN.

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WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

84. G2.1.6 001

Given the following plant conditions:

- A large break LOCA has occurred.

- The operating crew has entered the EOPs and is currently implementing

E-0, "Reactor Trip or Safety Injection".

Which ONE of the following describes when a crew brief should be held?

a. After step 4 of E-0 is complete.

b. After step 11 of E-0 is complete.

/c. Upon transitioning from E-0.

d. Upon making the Emergency Classification

85. G2.1.7 001

Given the following plant conditions:

- Unit at 100% RTP

- A S/G #1 safety valve begins leaking and power increases

to 105% RTP.

- The crew enters AOI-38 and reduces turbine load to 90% with the valve

position limiter.

- This load reduction caused reactor power to decrease to 95% RTP.

Which ONE of the following would be the correct crew response per AOI-38 if the

flow increased through the leaking safety valve causing the reactor power to

return to 101%?

a. Decrease turbine load at 5%/min to reduce reactor power to <100% and

continue AOI-38.

b. Use the valve position limiter to maintain power <100% and continue AOI-38.

vc. Trip the reactor, close the MSIVs and bypasses, and go to E-0.

d. Trip the reactor, initiate SI, close the MSIVs and bypasses and go to E-0.

Page 53

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

86. G2.1.11 001

Given the following conditions:

- Plant was operating at 100% power when a Main Feedwater pump

tripped causing a plant runback.

- The OAC observes AFD to be outside the "doghouse" on PRM channels

N41, and N44.

Which ONE of the following identifies the minimum actions required and the

maximum time allowed to comply with Technical Specifications?

a. Restore AFD to within limits AND Reduce power to < 50% within 30 minutes.

b. Restore AFD to within limits AND Reduce power to < 50% within 15 minutes.

-/c. Restore AFD to within limits OR Reduce power to < 50% within 30 minutes.

d. Restore AFD to within limits OR Reduce power to < 50% within 15 minutes.

87. G2.1.12 001

Given the following conditions:

- Plant is at 100% power.

- RCS pressure is 2235 psig and T-avg is 588 0 F.

- RHR discharge relief valve 1-63-637 is leaking to the PRT at a rate of

2.5 gpm.

Which ONE of the following describes the type of leakage and the action required

by Technical Specifications? (Assume all other systems are operating normally

and no other RCS leakage)

a. Unidentified leakage that requires shutdown.

b. Pressure boundary leakage that requires shutdown.

,/c. Identified leakage, but does not require shutdown.

d. Controlled leakage, but does not require shutdown.

Page 54

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

88. G2.1.33 001

Given the following plant conditions:

- Plant is in Mode 3

- During performance of Control Building routine rounds the AUO discovers

the 125V DC supply breaker to 120V AC Vital Inverter 1-11 in the

TRIPPED position.

Which ONE of the following describes the correct action which must be taken

with regard to Tech Specs?

a. Attempt to close the supply breaker one time, if the breaker can be closed,

Tech Spec LCO action entry is NOT required.

,/b. The Tech Spec LCO action for the inverter must be entered until the breaker

can be closed.

c. If the inverter is aligned to it's AC supply and the voltage is normal, Tech

Spec LCO action entry is NOT required.

d. If the inverter is aligned to it's AC supply and the voltage is normal, enter the

appropriate Tech Spec LCO action for the inverter for tracking only until the

breaker can be closed.

Page 55

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01126/01

89. G2.2.20 001

Given the following plant conditions:

- Plant is in Mode 3 with startup in progress.

- The breaker for "C" hotwell pump will not close.

- The Shift Manager and Work Week Manager determined that trouble

shooting could be conducted as "minor work" if the pump is tagged

out.

Which ONE of the following describes how this trouble shooting activity should

be documented?

a. WO is NOT required since only trouble shooting is planned and will have no

operational impact, no detailed planning or documentation is required.

b. WO is NOT required since a PER will be written to address the condition

adverse to quality and trouble shooting may be documented in the PER.

,/c. WO is required, the WO may be sent directly to the craft after OPS approval

and the work may be documented on the WO form.

d. WO is required, the WO must be routed to planning after OPS approval and

the work will be conducted and documented in the work package developed

by the planner.

90. G2.2.22 001

Given the following plant conditions:

- Unit is in Mode 3 with cooldown to Cold Shutdown in progress.

- A transient occurred resulted in the pressurizer going solid and RCS

pressure increasing to 2835 psig.

Which ONE of the following actions is required?

a. Be in hot shutdown with RCS pressure within its limit in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

b. Be in hot shutdown with RCS pressure within its limit in 30 minutes.

c. Reduce RCS pressure to within its limit within 15 minutes.

,/d. Reduce RCS pressure to within its limit within 5 minutes.

Page 56

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01126/01

91. G2.2.24 001

Given the following plant conditions:

- Unit is operating at 100% power.

- PZR Pressure channel II, 1-PT-68-33/, has failed HIGH.

- All required actions for this instrument failure have been completed.

- The surveillance for Pressurizer pressure channel IV, 1-PT-68-322, will

become late at the end of this shift.

Which ONE of the following actions should be taken?

a. Apply Tech Spec SR 3.0.3 to extend the surveillance for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to allow

completion of maintenance on 1-PT-68-33/

b. Bypass the bistables on 1-PT-68-322, enter LCO 3.0.3 and then perform

surveillance on 1-PT-68-322.

-/c. Bypass the bistables on 1-PT-68-33,A 'nd then allow surveillance to be

performed on 1-PT-68-322.

d. Do not allow surveillance to be performed and enter Tech Spec 3.0.3 when

the surveillance period expires.

Page 57

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

92. G2.2.28 001

Given the following plant conditions:

- Unit is in Mode 6.

- Refueling operations are in progress.

- An irradiated fuel assembly cannot be placed in its specified core

location.

Which ONE of the following describes an approved location for the fuel assembly

per FHI-7, Fuel Handling and Movement?

a. Fuel assembly can be placed in the New Fuel Elevator, but the elevator must

be full down with power removed.

b. Fuel assembly may be placed in a free-standing core location as long as no

other fuel assembly is free-standing.

c. Fuel assembly must be returned to the SFP until an alternate core location is

determined.

-/d. Fuel assembly may be temporarily stored in the RCCA change fixture.

93. G2.3.1 001

The following conditions are encountered after a survey of a pump room in the

Auxiliary building:

- General area radiation level in the room 70 mrem/hr

- Radiation level 30 cm from the pump casing 350 mrem/hr

- Contamination levels 800 dpm/100cm 2 beta

0 dpm/100cm 2 alpha

Which ONE of the following identifies the correct radiological postings required to

reflect current radiological conditions for this room?

Va. High Radiation Area.

wurof! 4. Contamination Area.

c. Radiation Area; Contamination Area.

d. High Radiation Area; Contamination Area.

Page 58

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26101

94. G2.3.4 001

Given the following plant conditions:

- A LOCA has occurred and a SAE has been declared.

- The TSC and OSC have been activated.

- To prevent core damage it is recommended that entry be made into

Safety Injection Pump Room 1A.

- Projected dose rate in the pump room is 1.16x10 5 mr/hr.

- Duration of the exposure is expected to be 3 minutes.

Which ONE of the following must authorize this exposure?

a. Radcon Manager

,/b. Site Emergency Director

c. Plant Manager

d. Site Vice President

95. G2.3.6 001

Given the following plant conditions:

- Unit is operating at 100% power.

- A release of the Monitor Tank to Cooling Tower Blowdown is planned.

- 1-RM-90-122, Liquid Radwaste Effluent Monitor is inoperable.

Which ONE of the following identifies the requirements to make the planned

release under these conditions?

a. No release can be made until 1-RM-90-122 is returned to service.

b. Sample results must show that activity of the release liquid is <2x1 0-4

microcuries per milliliter.

,c. Two separate samples must be analyzed and two independent qualified

members of facility staff verify release rate and discharge valve lineup.

d. The tank must be recirculated for two volumes and a licensed Senior Reactor

Operator must confirm release rate and discharge valve lineup.

Page 59

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

96. G2.3.11 001

Which ONE of the following identifies the first radiation monitor that should

respond to a SGTR and the effect on the monitor?

a. Condenser Vacuum Exhaust Monitor RM-90-119 and the monitor will be

automatically isolated.

v,. Condenser Vacuum Exhaust Monitor RM-90-119 and the monitor will NOT be

automatically isolated.

c. Steam Generator Blowdown Sample Monitor RM-90-120/121 and the monitor

will be automatically isolated.

d. Steam Generator Blowdown Sample Monitor RM-90-120/121 and the monitor

will NOT be automatically isolated.

97. G2.4.1 001

Given the following conditions:

- Unit 1 in MODE 1 at 10% RTP.

- Turbine at 1800 rpm at no load (generator PCB open).

- Loss of offsite power occurs.

- Emergency Diesels fails to re-energize Shutdown Boards.

Which ONE of the following describes the correct usage of the Emergency

Instructions?

,/a. Go directly to ECA-0.0 without entering E-0.

b. Implement ECA-0.0 in conjunction with E-0.

c. Go to ECA-0.0 from E-0 after verifying reactor and turbine trip.

d. Complete E-0 IMMEDIATE ACTIONS then go immediately to ECA-0.0.

Page 60

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

98. G2.4.7 002

Given the following plant conditions:

- Reactor trip and SI have occurred.

- Operators are using E-3, "Steam Generator Tube Rupture", to mitigate

the event.

Which ONE of the following correctly describes the applicability of the low RCS

pressure RCP trip criteria on the Foldout Page while performing steps of E-3?

a. RCPs should be tripped during the performance of E-3 ANY TIME the

foldout page low pressure RCP trip criteria are met.

b. Low RCS pressure RCP trip criteria is not applicable in E-3 EXCEPT as an

RNO if excessive RCS inventory loss is also experienced.

,/c. RCPs should be tripped during E-3 ONLY if the low RCS pressure RCP trip

criteria is met before beginning the cooldown and depressurization.

d. RCPs should be tripped during E-3 ONLY if the low RCS pressure RCP trip

criteria is met during the performance of step 1 when the operator is

specifically required to check the criteria.

Page 61

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

99. G2.4.19 001

A step in ES-1.3, "Transfer to RHR Containment Sump", reads as follows:

ISOLATE SI pump miniflow:

• CLOSE FCV-63-3.

• CLOSE FCV-63-175.

• CLOSE FCV-63-4.

The bullets ("*") indicate that:

a. The actions must be performed in the specified sequence, but once a step

is in progress, the next step may be started.

b. The actions must be performed and completed in the specified sequence.

c. These actions should have been completed, so only verification may be

required.

,/d. These actions must all be completed, but any sequence of completion is

allowed.

Page 62

WATTS BAR NUCLEAR PLANT

SENIOR REACTOR OPERATOR NRC EXAMINATION

01/26/01

100. G2.4.48 001

Following Safety Injection reset during ES-1.1 the following conditions exist:

- Tavg is 560TF.

- PZR level is 45%.

- PZR pressure is 2230 psig.

Which ONE of the following describes the PZR heater status the OAC would

observe?

a. Control group 1D OFF.

Backup group 1C OFF.

Backup group 1A-A OFF.

Backup group 1B-B OFF.

b. Control group 1D ON.

Backup group 1C OFF.

Backup group 1A-A OFF.

Backup group 1B-B OFF.

,/c. Control group 1D OFF.

Backup group 1C ON.

Backup group 1A-A OFF.

Backup group 1B-B OFF.

d. Control group 1D OFF.

Backup group 1C OFF.

Backup group 1A-A ON.

Backup group 1B-B ON.

Page 63