ML010460130
| 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
/1 / FINAL SUBMITTAL (WATTS BAR EXAM 50-390, 391/2001-301
JANUARY 29 -FEBRUARY 6, 2001 FINAL RO WRITTEN EXAMINATION
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I WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION
01/26101 SSN NAME2.Q0000 3.0000 4.0000 5. 0000 6. 0000 7.0000 8. 0000 9-0000 10. 0000 "1. 0000 12. 0000 13. 0000 14. @0000 15. 0000D( 16. 0000 17. 0000 18. 0000 19. 0000 20. 0000 21. 0000 22. 0000 23.-0000 24-.0000 25-.0000(26. 0000 27. 000 28. 0000 29. 0000 30. 0000 31. 0000 32-.0000( ( 3. 0000 34. 0000 35. 0000 36. 0000 37. Q 38.0000 39. 0000 40. 0000 41. 0000 42. 0000 43. 0000 44. 0000 45. 0000 46. 0000 47. 0000 48. 0000 40. 0000 50. 0000 Page 1
WATTS BAR NUCLEAR PLANT REACTOR OPERATOR NRC EXAMINATION
01/26/01 SSN NAME 51. @0000 52. 0000D( 53. 0000D 55. 0000( ( 56. 0000D( 58. 0000( ( 59 0000 60. 0000D( 61. 0000D( 62. 0000D( 63. 0000 64. 0000D( 65. 0000D( 6 6. 0000D( 67. 0000D( 68.0000 ( ( 69. 0000DE 70. 0000D( 71. 0000D( 72. 0000D( 73. 0000D( 75. 0000D(76. 0000 77. 0000 79. 0000 80. 0000 81.0000 82. 0(D00 830000( ( ( 84. 0000 85. 0000 86. 0000 87. 0000 88. 0000 89. 0000 9o. 0000 91. 0000 92. 0000 93. 0000 94. 0000 95. ,000 96.0000(D( 97- 0000 98. 0000 99. ©©D( loo. 0000 c~~r~ar ~ 3.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 fn,"J -:'f c I h/v's 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 480 0 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
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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.fl4-6. -7. z 0 0 0 m -7. H --8.-9..0 ------5 0 oll 5 0 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 Bumup Dependent
Parameters
6 -27 WCAP-15562 (Rev. 0)
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
,/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
-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
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
-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.
Blowdown Sample Monitor RM-90-120/121
and the monitor will be automatically
isolated.
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 SSN 1.0000 2. 0000 ,.0000 4.@000 .©0000 7.0000 8. 0000 9.0000 10. 0000 11. 0000 12.00000 13. 0000 14. 0000D( 15. 0000 16. 0000D( 17. 0000D( 18. 0000 19. 0000 20. 0000D( 21. 0000 22. 0000D( 23. 0000 24. 0000D( 25. 0000 26. 0000 27. 0000 28. 0000 29. 0(D00 30. 0000 31. 0(D00 32. 0000 33. 0000 35. 0000 36. 0000 ,37. @(DODD@ 38. 0(D00 39. 0000 40. 0(D00 41. 0000 42. 0(D00 43. 0000 44. 0000 45. 0000 46. 0000D( 47. 0000 48.0000 50-.0000 Page 1 NAME
WATTS BAR NUCLEAR PLANT SENIOR REACTOR OPERATOR NRC EXAMINATION
01/26/01 SSN 51. 0000 52. 0000 53 0000 54. 0000 55. 0000 56. 0000 57. @ (©D( 58.©000 59- 0000D( 60. 0000D( 61. 0000 62. 0000D( 63. 0000D( 64. 0000D( 65. 0000 66. 0000 67. 0000 68. 0000 69. 0000D( 70. 0000 71. 0000D( 72. 0000 73. 0000 74 0000 75. @ D000D 76.0000 77. 0000 78. 0000 70. 0000 800000DD( 81. 0000 82-.0000 13. 0000 84. 0000D( 85. 0000 86. 0000 87-.0000 88. 0000 89. 0000 90. 0000D( 91. 0000 92.0000 93. (o(00 94- 0000 95. 0000 96. 0000 97. 0000 98. 0000 99. 0000 loo-.0000 Page 2 NAME ,-, I a-...
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
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
z C:3 U,)I CD, CD, 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.-6. -7. -7. -8.-8.0 5 00 5 -°OL EO ,° Eiff-9.0 0 IIII 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 0 0 0 Pz 4 H 1 1 ...I I ..I I I , 1I I .1
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. 1 B-B Sl Pump will auto start, but 1A-A SI Pump will not auto start until the control power supply is transferred.
b. 1 B-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
-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 1 B-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.Page 52
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.
Blowdown Sample Monitor RM-90-120/121
and the monitor will be automatically
isolated.
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 1 B-B OFF. d. Control group 1D OFF. Backup group 1C OFF. Backup group 1A-A ON. Backup group 1B-B ON.Page 63