ML033460269
| ML033460269 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/15/2003 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Gordon Peterson Duke Energy Corp |
| References | |
| 50-413/03-301, 50-414/03-301 50-413/03-301, 50-414/03-301 | |
| Download: ML033460269 (78) | |
See also: IR 05000414/2003301
Text
Final Submittal
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CATAWBA APRIL 2003 EXAM
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50-413 & 50-414/2003-301
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MARCH 31 APRIL 4 &
APRIL 30,2003
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1. Reactor Operator Written Examination
NRC Official Use Only
Nuclear Regulatory Commission
Reactor Operator Licensing
Examination
Catawba Nuclear Station
This document is removed from
Official Use Only category on
Date of examination
NRC Official Use Only
Date: 4/18/2003 Facility/Unit: Catawba
Region: II Reactor Type: W
Start Time: Finish Time:
NUREG-I021, Draft Revision 9
Question #l Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is performing a plant startup when a problem occurs in the main
feedwater system.
The following events and conditions occur:
2A main feedwater pump is running
2B main feedwater pump turbine is not reset
Reactor power is 25%
The 2A main feedwater pump trips
The operator manually trips the plant
All steam generator levels decrease to 20%
Assuming systems operate as designed, when did the turbine dnven CA
pump receive an auto-start signal (if at all)?
A. When the 2A main feedwater pump tripped.
B. When narrow range level decreased below 36%.
C. When the reactor trip occurred.
Ques-0 16.2 For Official Use Only Page 1
Question #2 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 was conducting a reactor startup following a refueling outage. Given
the following conditions:
N41- N44 indicate 0%
N-31 indicates 2. lx104cps
N-32 indicates 2 . 0 ~ 1 cps
0~
N-35 indicates 8.5x10-" amps
N-36 indicates 1 . 51~O-' amps
Rods are in manual with no rod motion
SR and IR NIs are slowly increasing
T,, is holding steady
Which one of the following best explains the indications?
A. N-35 compensating voltage is set too high
B. N-35 compensating voltage is set too low
C. N-36 compensating voltage is set too high
D. N-36 compensating voltage is set too low
Ques-0 37 For Official Use Only Page 2
Question #3 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 containment pressure is 4.0 psig. All equipment is operating as designed.
Safety injection has been RESET.
Which one of the following action(s) is necessary for the operator to reopen
1KC-425A (Reactor Building Non-Essential Supply Header Isolation)?
A. Press the OPEN pushbutton on MC-11.
B. Reset phase B and then press the OPEN pushbutton on MC-11.
C. Wait until containment pressure is less than 3 psig and then press the
OPEN pushbutton on MC-11.
D. Wait until containment pressure is less than 0.3 psig and then press
the OPEN pushbutton on MC-11.
Ques-039.1 For Official Use Only Page 3
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Question #4 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 was operating at 100% power when an electrical fire started inside the
auxiliary building cable room corridor. What type of fire suppression system
is installed in this area and what arc the hazards to personnel if they enter this
room?
A. A manual deluge (Mulsifyre) System is installed. An electrical
shock hazard exists due to the use of water to combat an
electrical fire.
B. An automatic sprinkler system is installed. An electrical shock
hazard exists due to the use of water to combat an electrical fire.
C. An automatic Halon system is installed. An asphyxiation hazard
exists due to the presence of Halon gas.
D. A manual Cardox system is installed. An asphyxiation hazard
exists due to the presence of carbon dioxide gas.
Ques-060.1 For Official Use Only Page 4
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Question #5 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is responding to a loss of main feedwater event from 100% power.
Given the following events and conditions:
e The reactor has tripped
e The 2A and 2B motor-hven CA pumps started in auto
e The turbine-driven CA pump (CAPT) started in auto
e Train A CA has been reset
e Train B CA has failed to reset
e The CA pumps are aligned to the CACST
Which one of the following automatic system responses will occur as storage
tank and CA pump suction pressures decrease?
A. 2A CA pump trips.
CAPT #2 pump trips.
2B CA pump shifts to the RN system.
B. 2A CA pump suction shifts to the RN system.
CAPT #2 suction shifts to the RN system.
2B CA pump trips.
C. 2A CA pump suction shifts to the RN system.
CAPT #2 pump trips.
2B CA pump trips.
D. 2A CA pump trips.
CAPT #2 suction shifts to the RN system.
2B CA pump suction shifts to the RN system.
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Ques-260.2 For Official Use Only Page 5
Question #6 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 is shutdown in mode 6 with fuel movement in progress. Given the
following events and conditions:
The new fuel elevator fails to operate in the up direction
Which one of the following statements describes the cause of this problem?
A. 1EMF-15 (SPENT FUEL BLDGREFUEL BRIDGE) has failed
high.
B. 1EMF-20 (NEW FUEL STOR I A ) has failed high.
C. The load in the new fuel elevator weighs 1100 lbs.
D. The spent fuel bridge crane is NOT indexed over the new fuel
elevator.
Ques-263 For Official Use Only Page 6
Question #7 Catawba Nuclear Station RO Exam
1 Pt(s) Which one of the following statements correctly describes the sequence and
position of VI system valves in response to a loss of VI header pressure?
A. VI-SO0 (VI supply to VS) opens
VS-78 (VS supply to VI) opens
B. VI-SO0 (VI supply to VS) opens
VS-78 (VS supply to VI) closes
C. VI-SO0 (VI supply to VS) closes
VS-78 (VS supply to VI) opens
D. VI-SO0 (VI supply to VS) closes
VS-78 (VS supply to VI) closes
Ques-282.2 For Official Use Only Page 7
Question #8 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 was responding to a steamline break inside containment on the 1C S/G
per E-2 (Faulted Steam Generator Isolation). All equipment has operated as
designed.
Which one of the following action statements correctly describes the
expected method for isolating steam to the CAPT from the faulted S/G?
A. Manually close the CAPT #1 trip and throttle valve (1SA-145).
B. Manually close the 1C MSIV and MSIV bypass valve.
C. Manually close the maintenance isolation valve (1SA-4).
Ques-300.2 For Official Use Only Page 8
Question #9 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 was operating at 100% power when a design basis LOCA into
containment occurred. Given the following conditions:
2EMF-53- (Containment TRNMB (HI Range)) are both inoperable
Which one of the following indications would most accurately determine the
dose rates inside containment for the offsite dose assessment calculations?
A. 2EMF-38,39,40 (Containment PAWGASflOD) indications
B. 2EMF-5 (LIQ R/w COAT AREA) indications
C. 2EMF-54(") (Unit Vent Gamma (HI-HIRange)) indications
D. Portable instruments readings taken on the containment wall
and appropriately scaled for shielding factors
Ques-3 24 For Official Use Only Page 9
Question #10 Catawba Nuclear Station RO Exam
1 Pt(s) A technician is performing a calibration procedure, which requires a series of
approximately 10 sequential steps to be conducted while standing in a
contaminated area. The communicator holds the procedure and reads each
step sequentially by radio and the technician performs the step out of sight of
the communicator.
If the performer does not have the procedure in hand as he/she performs the
steps, what are the requirements of NSD 704 (Technical Procedure Use and
Adherence) regarding the sign off for each step?
A. Only the performer can sign off the steps upon completion of the
task after leaving the contaminated area.
B. The communicator signs off each step as the step is completed
using hidher own initials and the initials of the performer.
C. The communicator signs off each step as the step is completed
using hidher own initials along with the time.
D. The communicator signs off each step as the step is completed
using the performer's initials along with the time.
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Ques-331.1 For Official Use Only Page 10
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Question #11 Catawba Nuclear Station RO Exam
1 Pt(s) A radiation worker is repairing a valve in a contaminated area, which has the
following radiological characteristics:
The workers present exposure is 1943 mrem for the year
General area dose rate = 30 rnrem/hr
0 Airborne contamination concentration = 10.0 DAC
The job will take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> if the worker wears a hll-face respirator. It will
only take 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if the worker does NOT wear the respirator.
If the RP Manager grants all applicable dose extensions, which one of the
following choices for completing this job would maintain the workers
exposure within the station administrative requirements?
A. The worker should NOT wear the respirator because the
calculated TEDE dose received will be less than if he wears one.
B. The worker should NOT wear the respirator because the dose
received without wearing a respirator will exceed site annual
personnel dose limits.
C. The worker should wear the respirator because the calculated
TEDE dose received will be less than if he does not wear one.
D. The worker should wear the respirator otherwise he could exceed
DAC limits.
Ques-3 53.3 For Official Use Only Page 11
Question #12 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is in mode 6 and refueling operations are currently in progress. Given
the following events and conditions:
The Fuel Handling Manipulator Crane Operator (FHMCO) has indexed the
mast over the location where fuel assembly H-8 will be inserted.
All conditionshndications on the fuel handling manipulator crane are
satisfied for inserting the fuel assembly located at H-8, in accordance with
procedure.
Which one of the following statements describes the responsibility of the
"Operator at the Controls", associated with inserting the fuel assembly?
A. Receives notification of assembly insertion from the Fuel Handling
SRO, and tracks core response to reactivity changes.
B. Specifies the acceptable storage locations per Tech Specs and
informs the Fuel Handling SRO.
C. Grants permission to the FHMCO for inserting the fuel assembly
from the control room via the engineer communicating with the
refueling crew.
D. Verifies proper l/m plot results and gives permission to the
FHMCO to unlatch the assembly.
Ques-363.2 For Official Use Only Page 12
Question #13 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 was operating at 100% with the pressurizer level controller in the 1-2
position. Given the following initial response:
Charging flow reduces to minimum
Backup heaters immediately energize
Actual level begins to decrease
Which one of the following failures has occurred to cause this plant
response?
A. PZR level channel 1 detector reference leg has ruptured
B. PZR level channel 1 detector variable leg has ruptured
C. PZR level channel 2 detector reference leg has ruptured
Ques-399 For Official Use Only Page 13
Question #14 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 is responding to a station blackout. Given the following events and
conditions:
A fault occurred on the IEMXE load center that supplied power to the
1A D/G battery charger. Repairs to this load center have not been
made.
RN was manually lined up to supply the DG KD system
After two hours, the operators are ready to start the 1A diesel to restore
power on 1ETA.
What effect will the loss of power on IEMXE have on diesel generator
1A?
A. The diesel will start and run normally due to backup control
power from -%'ADA.
B. The diesel will not start due to loss of control power.
C. The diesel will start but the output breaker will not close due to
loss of breaker control power.
D. The diesel will start and the output breaker will close.
Ques-436.1 For Official Use Only Page 14
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Question #15 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 was operating at 100% power when a loss of condenser vacuum
occurred. Given the following events and conditions:
The operators initiated M I 0 9 (Rapid Downpower)
0 Reactor power dropped to 80%
0 Turbine load dropped to 82% based on turbine impulse pressure
0 The operator reports that condenser vacuum is 23.8 inches vacuum
and is continuing to decrease slowly.
Which one of the following statements correctly describes the required
action?
A. Manually trip the turbine then trip the reactor and enter E-0
(Reactor Trip or Safety Injection) immediately.
B. Manually trip the reactor then trip the turbine and enter AP/2
(Turbine Generator Trip) immediately.
C. If vacuum reaches 21.8 inches, manually trip the reactor and
enter E-0.
Ques-453.3 For Official Use Only Page 15
Question #16 Catawba Nuclear Station RO Exam
1 Pt(s) If a large fire was reported in a vital area inside the RCA, which one of the
following responses is correct by station procedures?
A. The Fire Brigade must suppress this fire without assistance
because the Bethel Volunteer Fire Department is not allowed to
access vital areas under the NRCs post-9/11 anti-terrorist
orders.
B. The Fire Brigade must suppress this fire because Bethel
Volunteer Fire Department is not qualified to fight fire in a
radiologically controlled area.
C. The Fire Brigade is initially responsible for fire suppression
activities at the scene. Upon arrival, the Bethel Volunteer Fire
Department will take over control of the scene.
D. The Fire Brigade is primarily responsible for fire suppression
activities at the scene. The Bethel Volunteer Fire Department
will respond promptly to the scene and will function under the
Site Incident Commander.
Ques-460.2 For Official Use Only Page 16
Question #17 Catawba Nuclear Station RO Exam
1 Pt(s) During an outage, air-operated valves 2NV- 122B & 123B (Loop C To Excess
Ltdn Hxlsol) are being used to isolate valve 2NV 124B (Excess Ltdn Press Cont)
for maintenance.
Which one of the following statements correctly describes the requirements for
using 2NV- 122/123 as an isolation boundary?
A. Tag shut the air supply to the valves and tag open the air regulator
petcocks. Tags should also be firmly fixed around the remote
operating switch on the main control board.
B. Tag shut the air supply to the valves and tag closed the air
regulator petcocks. Tags should also be firmly fixed around the
remote operating switch on the main control board.
C. Tag shut the air supply to the valves and tag closed the air
regulator petcocks. A switch label should also be firmly fixed
around the remote operating switch on the main Control board.
D. Tag shut the air supply to the valves and tag open the air regulator
petcocks. A switch labels should also be firmly fixed around the
remote operating switch on the main control board.
Ques-482.1 For Official Use Only Page 17
Question #18 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 was operating at 100% power following a refueling shutdown. Unit 2
was shutdown in mode 6. It was discovered that a spent fuel element from
the unit 1 refueling had been incorrectly stored in a filler location in the spent
fuel pool. The element had exceeded the burnup (GWDMTU) requirements
to qualify for storage in a filler location.
Which one of the following statements describes the correct action(s)
required by Tech Specs to preserve spent he1 pool shutdown margin?
A. Immediately initiate action to move the non-complying fuel
assembly to an unrestricted storage location.
B. Immediately initiate actions to move the non-complying fuel
assembly to a restricted storage location and to shutdown Unit 1
within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
C. Initiate action to move the non-complying fuel assembly to a
restricted storage location within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
D. Initiate actions to move the non-complying fuel assembly to an
unrestricted storage location and to shutdown Unit 1 within 1
hour.
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Ques-489.1 For Official Use Only Page 18
Question #19 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 was holding at 72% power during a load increase to 100% power
when one group of control rods in bank D failed to move with the rest of the
bank during a Xenon burnout transient. Given the following events and
conditions:
e Rod control was in automatic
e Rod control urgent failure alarm had NOT actuated
Bank D group counter is at 112 steps
2 rods in bank D are at 120 steps
3 rods in bank D are at 108 steps
Which one of the following statements correctly describes the operator
actions prior to attempting rod realignment?
A. Place control rods in manual and do not move control rods. Hold
rods at present position until realignment.
B. Place control rods in manual and insert the 2 rods in bank D to
108 steps within one hour.
C. Place control rods in manual and withdraw the 3 rods in bank D
to 120 steps within one hour.
D. Trip the reactor and enter E-0.
Ques-493.1 For Official Use Only Page 19
Question #20 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 was operating at 100% power when a terrorist attack in the control
room caused the operators to rapidly evacuate to the Auxiliary Shutdown
Panel. The operators were not able to perform AP/I 7 (Loss of Control
Room) actions prior to evacuation at 0200.
The terrorists tripped the turbine but did not operate any other controls.
There are no other local operator actions taken. Given the following steam
generator narrow range levels:
0200 0202 0204 0206 0208
2ASlGNR 65% 37% 22% 15% 25%
2BSfGNR 64% 38% 23 % 18% 26%
2CS/GNR 63% 39% 25% 16% 24%
2DS/GNR 65% 38% 26% 20% 27%
Which one of the following statements describeg the complete list of
running feedwater pumps that can be monitored from the Auxiliary
Shutdown Complex when the operators first arrive at the panels at 02 10 to
take local control ofthe plant? 4 mofi b-i-bpm
~ 9 Tr ~ I g~ d
6 O S w G r Q G ~ D o u T O F QUmP b p e q & ~ > k j &
A. Both motor driven CA pumps PRKQWETERQ
B. Both motor driven CA pumps and the turbine driven CA
Pump
C. Both motor driven CA pumps and both CF pumps (at
minimum speed)
Ques-501.1 For Official Use Only Page 20
Question #21 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is responding to a LOCA into the Auxiliary Building in ECA- 1.2
(LOCA Outside ofCuntainment). Upon completion of ECA-I .2, NC system
pressure continues to decrease.
Which one of the following statements correctly describes the correct major
action to assure proper method of removing decay heat under these
conditions?
A. Transition back to E-1 (Loss of Reactor or Secondary Coolant).
B. Transition to ECA-1.1 (Loss of Emergency Coolant Recirculation).
C. Transition to ES-1.2 (Post LOCA Cooldown and Depressurization).
D. Transition to ES-1.3 (Transition to Cold Leg Recirc).
Ques-507 For Official Use Only Page 2 1
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Question #22 Catawba Nuclear Station RO Exam
1 Pts Unit 2 is responding to a main steam line break inside containment. Given
the following events and conditions:
e Containment pressure is 0.1 psig
a The pressurizer is solid
a ES- 1.1 (Safety Injection Termination) has been implemented
Which one of the following statements correctly describes the status of the
ECCS systems upon successful completion of ES- 1.l ?
A. One NS pump running to provide containment pressure control
B. One ND pump running to provide adequate heat removal
C. One NI pump running to provide adequate inventory control
D. One NV pump running to provide a normal charging lineup
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Ques-508.1 For Official Use Only Page 22
Question #23 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is responding to a LOCA outside containment. The operators have
reached step 22 of E- 1 when the STA reports the following critical safety
functions (CSFs) status indications on the OAC:
CSF Status
1. NC INVENTORY Yellow
2. CORE COOLING Red
3. CONTAINMENT Green
4. NC INTEGRITY Green
5. HEAT SINK Red
6. SUBCRITICALITY Yellow
What is the correct order in which these CSFs shall be prioritized for
response?
A. 5,2,6,4,3,1
B. 2,5,6, 1,4,3
C. 5,2,6, 1,4,3
Ques-5 11.1 For Official Use Only Page 23
Question #24 Catawba Nuclear Station RO Exam
1 Pt(s) why do some of the phase A containment isolation valves located in lower
containment for the KC system have a separate manual reset on 1MC7?
A. The valves use air operators, which are not subject to spurious
repositioning should they be submerged during containment
flooding therefore they may be reset and repositioned if required
by procedure.
B. The valves are all above the containment flooding level and are
not subject to spurious repositioning during containment
flooding therefore they may be reset and repositioned if required
by procedure.
C. A separate reset is required because a containment phase A
signal removes power from these valves causing them to fail
closed to prevent them from spuriously repositioning due to
containment flooding.
D. A separate reset is required because a containment phase A
signal disables the open circuits for these valves to prevent them
from spuriously repositioning due to containment flooding.
Ques-518.1 For Official Use Only Page 24
Question #25 Catawba Nuclear Station RO Exam
1 Pt(s) Step 9.e of ECA-1.1 (Loss of Emergency Coolant Recirculation) requires
operators to initiate NC system cooldown to cold shutdown:
"9.e Dump steam to condenser while maintaining cooldown rate
based on NC T-colds as close as possible without exceeding IO0 4"
in an hour. 'I
Which one of the following statements is in accordance with this step?
A. Attention should be paid to maintaining the cooldown rate at
100 OF/hr as an ideal value but not to be overly concerned if the
exact value is not achieved. Any previous cooldown that had
been conducted within the last hour needs to be considered.
B. Attention should be paid to maintaining the cooldown rate at
100 "F/hr as an ideal value but not to be overly concerned if the
exact value is not achieved. Any previous cooldown that had
been conducted within the last hour does NOT need to be
considered.
C. Considerable attention must be devoted to achieving and
maintaining this cooldown rate - OMP 1-4 guidance on setpoints
does not apply to this step. Any previous cooldown that had been
conducted within the last hour needs to be considered.
D. Considerable attention must be devoted to achieving and
maintaining this cooldown rate - OMP 1-4 guidance on setpoints
does not apply to this step. Any previous cooldown that had been
conducted within the last hour does NOT need to be considered.
Ques-521 For Official Use Only Page 25
Question #26 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is operating at 75% power. Given the following events and
conditions:
0 2CM-83 is in AUTO
0 A load rejection occurs
Which one of the following statements correctly describes the response of
2CM-83, (Generator Load Rejection Bypass valve) during the load rejection?
A. 2CM-83 opens to provide condensate flow around the hotwell pumps
to assure minimum flow requirements.
B. 2CM-83 opens to provide additional condensate pressure to the
condensate booster pumps and bypass portions of the low pressure
CM system.
C. 2CM-83 closes to prevent a loss of water from the "C" heater drain
tank to the condensate booster pump suction.
D. 2CM-83 closes to prevent condensate water from being recirculated
to the suction of the condensate booster pumps.
Ques-531.1 For Official Use Only Page 26
Question #27 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is responding to a LOCA.
Given the following sequence of events and conditions:
A reactor trip and safety injection occurred
All NV, NI and ND pumps sequenced on properly
ECCS was reset
The 2ETA bus momentarily lost power but was reenergized by the 2A D/G
Which one of the following statements describes the correct restoration
process for the train A NV, NI and ND pumps?
A. 2A NV pump must be restarted by operator action
2A NI pump will automatically restart
2A ND pump will automatically restart
B. 2A NV pump will automatically restart
2A NI pump will automatically restart
2A ND pump will automatically restart
C. 2A NV pump will automatically restart
2A NI pump must be restarted by operator action
2A ND pump must be restarted by operator action
D. 2A NV pump must be restarted by operator action
2A NI pump automatically restart
2A ND pump must be restarted by operator action
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Ques-540.1 For Official Use Only Page 27
Question #28 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is responding to a small break LOCA in ES- 1.2, (Post LOCA
Cooldown and Depressurization). Step 16 of ES- 1.2 requires the operators
to depressurize the NC system.
Which one of the following statements correctly describes the priority and
reasons for using the prescribed methods of depressurizing the NC system?
A.
1. Pressurizer spray - preferred method to be used if NC pump
is running
2. Auxiliary Spray - alternate method - better control over
depressurization rate
3. PORV - method of last resort - lack of control of
depressurization rate - results in rupturing the PRT
B.
1. Pressurizer spray - preferred method to be used if NC pump
is running
2. PORV - alternate method - better than auxiliary spray
3. Auxiliary Spray - method of last resort - too slow and may
thermal shock the spray nozzles and degrade regenerative
heat exchanger
C.
1. PORV - preferred method - rapid depressurization rate
2. Pressurizer spray - alternative method - next most rapid
depressurization rate
3. Auxiliary spray - method of last resort - too slow and may
thermal shock the spray nozzles
D.
1. Auxiliary spray - preferred method - does not degrade
containment
2. Pressurizer spray - alternative method - will not work if NC
pump is not running
3. PORV - method of last resort - will rupture PRT and degrade
containment environment
Ques-571.1 For Official Use Only Page 28
Question #29 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 is in mode 3. NC pressure is 1940 psig. CA auto start defeat
"Defeated" lights are lit
The following sequence of events occur on unit 1 while in mode 3:
1. CF isolation and the running CFPT trips on S/G Hi-Hi level
2. The S/G Hi-Hi level clears
3. CF isolation is reset
4. T-ave increases and NC pressure increases to 1960 psig
Which of the following correctly explains when (if at all) any CA pump(s)
should have automatically started?
A. Following the CF isolation reset.
B. When the S/G Hi-Hi level cleared.
C. When pressure increased above P-11.
D. The CA pumps have remained off for these events.
Ques-592.1 For Official Use Only Page 29
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Question #30 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 is at 4% power, conducting a plant startup. Given the following
events and conditions:
0 A control bank A rod drops
NCS temperature decreases to 550°F
Which one of the following statements correctly describes the required
actions (if any)?
A. No technical specification action is required, however, the plant
must be shutdown to mode 3 to recover the rod.
B. Within 30 minutes, adjust power range N/Is to increase reactor
power so that reactor power and thermal power best estimate are
equal.
C. Within 30 minutes be in mode 2 with Kffless than 1.0.
D. Immediately trip the reactor and enter E-0 (Reactor Trip or
Safety Injection).
Ques-6 00 For Official Use Only Page 30
Question #31 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is responding to a LOCA. The crew has entered ES-I .2, Post LOCA
Cooldown and Depressurization.
Given the following events and conditions:
Pressurizer level is steady
Only one train of ECCS is injecting
Loop A temperatures are representative of all 4 loops
MSIVs and steam dumps are open
Which one of the following sets of plant parameters is indicative of h l l y
established natural circulation as outlined in Enclosure 3, Natural Circulation
Monitoring Parameters?
REFERENCES PRO WDED
Time 0200 -
- 0205 - 0210 - 0215
A. Steam Header Pressure (psig) 742 715 676 645
NC System Pressure (psig) 968 964 960 958
LOOP A T-hot (F) 544 536 535 527
LOOP A T-cold ( O F ) 512 510 502 497
B. Steam Header Pressure (psig) 742 709 676 645
NC System Pressure (psig) 968 972 975 981
LOOP A T-hot (OF) 547 552 555 563
LOOP A T-cold (OF) 548 544 540 536
C. Steam Header Pressure (psig) 742 747 750 762
NC System Pressure (psig) 968 964 960 958
LOOP A T-hot (OF) 544 536 535 527
LOOP A T-cold (OF) 512 514 515 517
D. Steam Header Pressure (psig) 742 737 740 732
NC System Pressure (psig) 938 942 945 941
LOOP A T-hot (OF) 539 542 545 545
LOOP A T-cold (F) 513 510 510 506
Ques-602.1. For Official Use Only Page 31
Question #32 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 trips from 100% power due to an electrical fault.
5 minutes later, 1EMF-33 (Condenser Air Ejector Exhaust) alarms in trip 2.
Which one of the following indications will provide the best indication (most
sensitive and timely) to confirm that a S/G tube leak has just occurred?
A. Observing lEMF-26,27,28 and 29 (Steamline IA - I D )
B. Comparing S/G feed flow to steam flow mismatch
C. Observing lEMF-34(L) (S/G sample (lo range))
D. Observing lEMF-71,72,73,74 (S/GA-D leakage)
Ques-605.1 For Official Use Only Page 32
Question #33 Catawba Nuclear Station RO Exam
1 Pt(s) Federal Regulations require the emergency core cooling system to be
designed to maintain peak cladding temperature below 2200 OF.
Which one of the following statements correctly describes the basis for this
design criterion?
A. To prevent acceleration of the zircalloy-water reaction.
B. To prevent exceeding the zircalloy clad melting point.
C. To prevent exceeding the fuel melting point.
D. To prevent the onset of full film boiling and DNB.
Ques-73 1 For Official Use Only Page 33
Question #34 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is in the process of conducting a plant startup.
Power range channels indicate the following:
0 PRN41=8%
0 PRN42=8%
PRN43=10%
0 PRN44=8%
Assuming no operator action, which of the following conditions would result
in an automatic reactor trip?
A. All four RCPs trip.
B. One turbine impulse pressure channel fails high.
C. NCS controlling pressurizer level channel fails low.
D. NCS controlling pressurizer pressure channel fails high.
Ques-736.1 For Official Use Only Page 34
Question #35 Catawba Nuclear Station RO Exam
1 Pt(s) Units 1 and 2 are operating at 100% power with a normal service water line-up
and RN pump 2A running. Given the following conditions and indications:
0 F W pumps IA, 1B and 2B start.
0 1 and 2 RN-48B (RNSUPPLYX-OYER ISOL) close
0 1 and 2 RN-47A (RNSUPPLYX-OYER ISOL) remain open
0 RN suction and discharge valves swap to the SNSWP. ,
Which one of the following conditions correctly describes the cause of this
condition?
A. The Lake Wylie dam failed.
B. RN pump intake pit A screens are clogged.
C. RN pump intake pit A level indicator (RNINTAKE PIT L KZ A 3
failed low.
D. There was a spurious containment phase B actuation on Unit 1.
Ques-757 For Official Use Only Page 35
Question #36 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 is recovering from a loss of secondary coolant accident. Safety
injection initiated properly. A total loss of feedwater has caused the
operators to implement FR-H. 1, (Loss ofSecondary Heat Sink). Given the
following plant conditions:
NCS Pressure 2335psig
NCS Temperature 565°F
S/G lA, lB, 1C Pressure 118Opsig
S/G lA, IB, 1C Level (WR) 12%
S/G 1D Pressure lOOpsig
S/G 1D Level (WR) 35%
VI system pressure 1Opsig
Containment pressure 3.4psig
Which one of the following actions is initially required to assure the
maintenance of adequate core cooling?
A. Depressurize S/G lA, lB, and 1C to allow feeding the S/G using
the condensate system.
B. Reset the CAPT and align it to feed S/Gs lA, 1B and 1C.
C. Open 1NC-32B (PZR PURV and 1NC-34A (PZR PORI? using
nitrogen pressure.
. . _.
D. Reset safety injection and containment phase A isolation
signals to re-establish instrument air pressure to open 1NC-32B
and 1NC-34A.
Ques-769.1 For Official Use Only Page 36
Question #37 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is operating at 100% power with all rods out.
An operator notices that one core exit thermocouple (T/C) for quadrant I1
on the plasma display was 620°F but suddenly spiked to 670°F.
Other nearby T/Cs indicate a steady 620°F with no change in indicated
temperature.
The reference junction effective temperature is designed to be controlled
at 165°F for all T/Cs.
The following instrument diagram represents the T/C measuring circuit.
Which one of the following statements correctly describes the reason for this
'
thermocouple to read much higher than the other thermocouples?
A. The thermocouple measuring junction has been shorted.
B. The thermocouple measuring junction has an open circuit.
C. The thermocouple reference junction effective temperature has
increased by 50°F.
D. The thermocouple reference junction effective temperature has
decreased by 50°F.
Ques-793.2 For Official Use Only Page 37
Question #38 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 was operating at 100% power. Given the following events and
conditions:
1 AD-6 F/10, (PRTHI TEMP) in alarm
1 AD-6 FA1 (PRT HI PRESS) in alarm
Lower containment temperature = 124 O F
The NC system is at normal operating temperature
Letdown is in service
Which one of the following statements correctly describes a condition that
could cause these alarms?
A. The PRT has heated up due to ambient containment
temperature.
B. 1 ND-3 or 1ND-38, (NO SUCTION RELIEF VALVES) have lifted.
C. 1 NV-15B (LETDN CUNT ISOL) has spuriously closed.
D. The reactor vessel inner O-ring has leaked.
Ques-796 For Official Use Only Page 38
Question #39 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1was operating at 7% power when an electrical problem causes the loss
of 1T1B. Given the following events and conditions in chronological
sequence:
Voltage on short buses 1TB and 1TD drops to 75%
0 Frequency on short buses 1TB and ITD decreases to 55 hertz.
0 The 1TB-to-1TD fast bus transfer fails to occur
0 All equipment operates as designed.
0 No operator action
What is the current status of the unit?
A. The reactor does not trip, B and D NCPs trip.
B. The reactor does not trip, all NCPs trip.
C. The reactor trips, B and D NCPs trip.
D. The reactor trips, all NCPs trip.
Ques-828 For Official Use Only Page 39
Question #40 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 was operating at 100% power when the crew detects indications of a
loss of NC inventory. Given the following events and conditions:
e All systems are in automatic
e Indicated letdown flow is 62 gpm
e 1NV-13A (LTDNORIF IA OTLT CONTISOL) is open
e Letdown pressure is 350 psig
e Seal return - 3.5 gpm per NCP
e Indicated charging flow - 90 gpm
e Indicated seal injection flow - 35 gpm
e VCT level is decreasing
e Pressurizer pressure and level are constant
e Containment humidity is increasing
Which one of the following statements correctly describes the location of the
leak?
A. Letdown line, between the letdown orifice and the containment
isolation valve.
B. Charging line between 1NV-309 (Seal WaterInjectiun Flow) and
1NV-294 (NVPumps A&B Disch Flow CTRL).
C. Charging line inside containment.
D. One of the RCS loops.
Ques-829 For Official Use Only Page 40
Question #41 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 was operating at 100% when a design basis LOCA occurred.
Radiation monitoring teams at the site boundary report that projected Iodine
131 dose is 25 rem.
Which one of the following statements correctly describes the cause of this
problem on the VE filter trains?
A. The HEPA filters are saturated
B. The charcoal filters are saturated
C. The prefilter/demisters are saturated
D. The VE filter unit preheaters are energized
Ques-834 For Oficial Use Only Page 41
Question #42 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 is operating at 75% power and Unit 2 is at 100% power. Given the
following events and conditions:
0 Switchyard breakers PCB 20 and 21 open.
Which one of the following statements correctly describes the effect on units
1 and2?
A. Unit 1 will remain at 75% power and unit 2 will runback to
approximately 56%.
B. Unit 1 will runback to approximately 30% and unit 2 will remain
at loo%/
C. Unit 1 will runback to approximately 56% and unit 2 will remain
at 100%.
D. Both units 1 and 2 will runback to approximately 56%.
Ques-843.1 For Official Use Only Page 42
Question #43 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is operating at 100% power. Pressurizer level is on program, and
normal charging is in service and letdown flow is through a 75 gpm orifice.
Given the following events and conditions:
0 2NV-3 14B (CHARGINGLINE CUNT OUTSIDE ISOL) spuriously closes
due a relay failure
0 Flashing in the letdown line reduces letdown flow to 5 gpm
Without operator action, approximately how long before a pressurizer level
deviation alarm actuates?
Assume 135 gallons = 1% pressurizer level
A. A low-level deviation alarm will occur in less than one hour.
B. A low-level deviation alarm will occur in greater than one hour.
C. A high-level deviation alarm will occur in less than one hour.
D. A high-level deviation alarm will occur in greater than one hour.
Ques-857.2 For Official Use Only Page 43
Question #44 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is at full power when the following events occur:
0 Reactor power is approximately 98%
NCS T,, is increasing
Main turbine load is 1150 MWe
0 Feedwater flow continues to operate as designed
0 The RO is manually inserting rods
Which one of the following statements correctly describes the EOP basis in
FR-S. 1 (Response to Nuclear Power Generation for immediately
tripping the turbine?
A. Prevent an uncontrolled cooldown and positive reactivity
addition.
B. Maintain or extend steam generator inventory.
C. Prevent turbine overspeed when the main generator trips.
D. Minimize the peak pressure transient for the event.
Ques-865.2 For Official Use Only Page 44
Question #45 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 was operating at 100%power. Given the following trends on the
1A NCP:
Time -
0200 -0205 - 0210 - 0215
Motor bearing temp ( O F ) 180 184 186 195
Lower pump bearing temp ( O F ) 221 225 228 231
- 1 seal outlet temp ( O F ) 205 227 235 251
Motor winding temp (F) 312 314 316 323
What is the earliest time at which the 1A NCP must be secured?
A. 0200
B. 0205
c. 0210
D. 0215
Ques-870 For Official Use Only Page 45
Question #46 Catawba Nuclear Station RO Exam
1 Pt(s) A station emergency battery is supplying DC bus loads without a battery
charger on line.
If the equipment load on the DC bus does not change, which one of the
following battery discharge curves describes the battery capacity as a
function of the battery discharge rate?
mum PtClrr ba
1
A alscbargoraw B alschargeraw L
alschrmoraw alscbameraw
___F
Ques-906.1 For Official Use Only Page 46
Question #47 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 is responding to a S/G tube rupture in E-3 (Steam Generator Tube
Rupture). Given the following events and conditions:
0 The target temperature has been determined.
0 P- 11 has been reached and the operators have blocked main steam
isolation signal.
0 Operators are preparing to open the steam dumps to cooldown to the
target temperature at step 19f of E-3.
What is the applicable limit for the operator opening the steam dumps?
A. The steam dumps should be opened as far as possible to dump
steam at a maximum rate while attempting to avoid a main
steam isolation.
B. Steam dumps should be opened to limit the cooldown rate to less
than 100 degreedhow to prevent exceeding Tech Spec limits.
C. Steam dumps should be opened to limit the cooldown rate to less
than 25 degreedhow to prevent pressurized thermal shock
concerns.
D. All steam dumps should be fully opened to depressurize the S/Gs
as quickly as possible.
Ques-907.1 For Official Use Only Page 47
Question #48 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 was operating at 100% power when a loss of offsite power caused a
reactor tip. The crew has verified natural circulation in ES-0.1 (Reactor
Trip Response). Ten minutes later, the operator notes that the thermocouple
input to both plasma displays is malhnctioning.
Which one of the following correctly describes a valid indication that natural
circulation is continuing?
A. SIG saturation temperatures are decreasing and REACTOR VESSEL
UR LEVEL indication is greater than 100 %.
B. S/G pressures are decreasing and Tcold is at SIG saturation
temperature.
C. SIG pressures are decreasing and REACTOR VESSEL D R indication
is greater than 100%.
D. S/G pressure is at saturation pressure for Tcold and REACTOR
VESSELDLP indication is greater than 100 YO.
Ques-911.1 For Official Use Only Page 48
Question #49 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 is operating at fill power. Given the following containment
ventilation lineup:
3 Lower Containment Ventilation Units ( L C W s )
0 1 Pipe Tunnel Booster Fan (PTBF)
0 3 Control Rod Drive Mechanism (CRDM) Vent Fans
0 1 Incore Instrument Room Air Handling Units (IIRAHUs)
0 3 Upper Containment Ventilation Units (UCWs)
0 Both Containment Auxiliary Charcoal Filter Units (CACFUs) are
shutdown
A loss of offsite power occurs on Unit 1. Both diesel generators start and
energize ETA and ETB. Sequencing is complete. No operator action has
been taken regarding the electric plant.
What is the expected Containment Ventilation lineup?
A. LCVUs, UCVUs and CRDM fans will be running; all other
equipment will be shutdown.
B. LCVUs, UCVUs, CACFUs and CRDM fans will be running; all
other equipment will be shutdown.
C. LCVUs, UCVUs, CACFUs, PTBFs and CRDM fans will be
running; all other equipment will be shutdown.
D. LCVUs, UCVUs, PTBFs, IIRAHUs and CRDM fans will be
running; all other equipment will be shutdown.
Ques-957.1 For Official Use Only Page 49
___
Question #50 Catawba Nuclear Station RO Exam
1 Pt(s) Which one of the following statements correctly describes how a severe axial
flux imbalance that is outside of the normal limits (as defined in the ROD
Book section 3.9 (OACManual Input Data)) could affect automatic and
manual rod withdrawal at 100% power?
A. AFD inputs to OTDT cause the OTDT setpoint to increase,
which could actuate a C3 rod stop to prevent automatic rod
withdrawal. Operator would manually insert rods to restore
AFD within the target band and clear the rod stop.
B. AFD inputs to OPDT cause the OPDT setpoint to decrease,
which could actuate a C3 rod stop to prevent automatic or
manual rod withdrawal. Operator would manually insert rods to
restore AFD within the target band and clear the rod stop.
C. AFD inputs to OPDT and OTDT cause both setpoints to
decrease, which could actuate a C3 or C4 rod stop to prevent
automatic or manual rod withdrawal. A turbine runback would
automatically reduce NC temperature below the OPDT or
OTDT setpoints to clear the rod stop.
D. AFD inputs to OPDT and OTDT cause both setpoints to
increase, which would actuate a C3 o r C4 rod stop to prevent
automatic rod withdrawal. Manual rod withdrawal would still
operate and a turbine runback would not occur. Operators
would manually insert or withdraw rods to restore AFD within
the target band and clear the rod stop.
Ques-963 For Official Use Only Page 50
Question #51 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 is operating at 100% power. Given the following events and
conditions:
0 Train A equipment is in service.
1ETA is deenergized due to a bus fault and power cannot be restored.
All plant safety equipment operates automatically as designed.
0 No operator action has been taken.
What would be the immediate impact (if any) of the loss of lETA on the
NCPs?
A. All NCPs would continue to be cooled.
B. Only A and D NCPs would lose cooling.
C. Only B and C NCPs would lose cooling.
D. All NCPs would lose cooling.
Ques-964 For Official Use Only Page 5 1
Question #52 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 was operating at 100% when a large-break LOCA occurred inside
containment at 0200. Given the following events and conditions:
e 020 I - containment pressure = 1.O psig
e 0205 - containment pressure = 3 .O psig
e 02 10 - containment pressure = 0.5 psig
e 02 15 - containment pressure = 0.1 psig
What should be the status of the Containment Air Return dampers and fans at
time X
! J)?
A. Dampers open; fans running.
B. Dampers open; the fans never started.
C. Dampers opened but have closed; fans started but have stopped.
D. Dampers opened but have closed; the fans never started.
Ques-965 For Official Use Only Page 52
~~
Question #53 Catawba Nuclear Station RO Exam
1 Pt(s) During a reactor start-up, the following conditions are noted:
The reactor is at normal operating pressure and temperature.
0 Four NCPs are running.
NCS temperature is being controlled using the steam dumps.
The reactor power is 5%.
Which of the following describes the change in actual plant parameters if the
controlling steam header pressure transmitter fails high?
A. Steam dump demand increases. Steam header pressure
decreases, and NCS temperature decreases.
B. Steam dump demand decreases. Steam header pressure
increases, and NCS temperature increases.
C. Steam dump demand increases, Steam header pressure
increases, and NCS temperature decreases.
I). Steam dump demand decreases. Steam header pressure
decreases, and NCS temperature decreases.
Ques-966 For Official Use Only Page 53
~ ~~
Question #54 Catawba Nuclear Station RO Exam
1 Pt(s) A unit 1 containment purge is in progress using OP/l/A6450/015. Given the
following events and conditions:
0 lEMF-39(L) (Containment Gas (Lo Range)) spiked to a trip 2 condition
then cleared
Which one of the following statements correctly describes the action
required?
A. The VP release may not be reinitiated until RP draws a new
containment air activity sample.
B. The VP release may be reinitiated after the spike clears. If 1EMF-39
spikes a second time, the release cannot be reinitiated without RP
sampling containment air for activity.
C. The VP release may be reinitiated after the spike clears. If 1EMF-39
spikes a second time, the release may also be reinitiated.
D. The VP release may be reinitiated if grab samples are taken of Unit
vent activity during subsequent reinitiation.
- - 11 -----
- -1 -1 -I- ---- 1 - --
Ques-968.3 For Official Use Only Page 54
~~
Question #55 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 is at 75% power when a plant trip occurs due to P-14 actuation. Given
the following events and conditions:
0 The plant is currently stable.
The steam dumps have just closed at no-load Tave.
Steam generator levels are 35% in unaffected steam generators and 80%
in the affected steam generator.
What action must the operator take to reset CF isolation?
A. Cycle the reactor trip breakers only.
B. Cycle the reactor trip breakers and depress the CF isolation reset
pushbuttons.
C. Lower the affected steam generator level and cycle the reactor trip
breakers.
D. Lower the affected steam generator level, cycle the reactor trip
breakers and depress the CF isolation reset pushbuttons.
Ques-970 For Official Use Only Page 55
Question #56 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 was operating at 100% power when a small break LOCA occurred.
Given the following events and conditions:
lEMF-53AB (Containment TRNHB (Hi Range)) = 36 Rkr
Containment pressure = 0.5 psig
The operators enter FR-Z.3 (Response to Containment High Radiation
Level)
Which one of the following statements correctly describes the proper (major
action) response in FR-Z.3 to reduce airborne radiation levels inside
containment?
A. Place containment auxiliary charcoal filter units (CACFUs) in
service.
B. Place containment purge (VP) system in service.
C. Place the containment spray (NS) system in operation.
D. Place the containment air return fans ( a s ) in service.
Ques-97 1 For Official Use Only Page 56
Question #57 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 was operating at 100% power when a loss of vital power occurs.
Given the following events and conditions:
1AD-11, HI2 "125 VDC ESS PWR CHANNEL B TROUBLE" Alarm -
is lit
The operators dispatch an NLO to investigate the cause of the alarm
The control room supervisor implements AP-29 (Loss of Vital or A m
Control Power).
Which one of the following actions shall be performed immediately?
A. Close the breaker to 1EBB
B. Open the tie breaker to lEDB
C. -
Verify ND ALIGNED IN RHR MODE
D. Verify TURB IMP PRESS CH 1 - NORMAL
Ques-974 For Official Use Only Page 57
Question #58 Catawba Nuclear Station RO Exam
~~
1 Pt(s) Unit 1 was operating at 100% power.
Which one of the following conditions requires a reactor trip and turbine
trip?
A. Exhaust hood temperature channel = 226 O F
B. Turbine bearing oil pressure = 13 psig
C. Condenser vacuum = 21.5 inches Hg Vacuum
D. Generator frequency = 65 Hz
Ques-977 For Official Use Only Page 58
Question #59 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 is preparing to conduct a vacuum fill of the NC system at the end of a
refueling outage. The NC system is in a mid loop condition.
Which one of the following reactor vessel level instruments will provide the
greatest accuracy for this condition?
A. NC level loop indication
B. Sight glass loop indication f
C. Ultrasonic level indication
D. RVLIS lower range indication
Ques-978 For Official Use Only Page 59
Question #60 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 was shutdown in mode 6, in mid loop operations when a loss of ND
cooling occurred. Given the following events and conditions:
0 The operators implemented CASE IV of AP- 19 (Loss of Residual Heat
Removal System) and have reached step 23.
0 The ND system has been refilled and properly vented
0 Step 23 requires restart of one ND pump to restore cooling.
0 A caution warns the operator that restarting an ND pump can cause NC
system level to decrease rapidly.
What is reason for this caution?
A. NC system level will drop due to the contraction of the water
from the cooldown.
B. NC system level will drop due to the suction of water from the
NC system into the ND pump.
C. NC system level will drop due to the collapse of system voids.
D. NC system level will drop due to increased system pressure.
Ques-980 For Official Use Only Page 60
Question #61 Catawba Nuclear Station RO Exam
1 Pt(s) What sub-group of pressurizer heaters can be powered from SLXG?
A. Backup heater Group A
B. Backup heater Group B
C. Control Group C
D. Backup heater Group D
Qu es-9 81 For Official Use Only Page 61
Question #62 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is at 100% power following a refbeling. Given the following events
and conditions:
Reviews of surveillances reveals that all 3 channels on the flow
instruments for NC loops IC and ID were not calibrated properly and are
out of specification.
Repairs cannot be made for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> due to parts availability.
" hat is the maximum power level allowed by Tech Specs at the time of
repair?
REFERENCES PRO WDED:
A. Reduce power to less than 69%
B. Reduce power to less than 48%
C. Reduce power to less than 10%
D. Reduce power to mode 3
Ques-98 2 For Official Use Only Page 62
Question #63 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 was operating at 100% power when a LOCA occurred.
Which one of the following statements correctly describes the operation of
the N S N X reset during the LOCA and what is the reason for this operation?
A. NSNX is reset to allow the operator to take manual control of NS
pumps.
B. NSNX is reset to terminate spray flow after pressure is reduced to
prevent a vacuum in containment.
C. NSNX is NOT reset to prevent excessive cycling of NS spray pumps
and VX fans.
D. NSNX is NOT reset to allow NS components to continue to operate
when transferring to recirculation.
Ques-985 For Official Use Only Page 63
Question #64 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is operating at 100% power. Given the following events and
conditions:
The plant operator reports the following annunciator is received on D/G
panel 2A: LOW VG AIR TANK PRESS
0 VG receivers starting air pressure is 149 psig.
Which one of the following statements correctly describes the 2A D/G?
A. The D/G cannot be manually or automatically started until the
VG receiver is repressurized.
B. The D/G can be manually started and is capable of one or two
starts.
C. The D/G can be automatically started and is capable of one or
two starts.
D. The D/G can be automatically started and is capable of five
starts.
Ques-986 For Official Use Only Page 64
Question #65 Catawba Nuclear Station RO Exam
1 Pt(s) Which one of the following statements explains the reason for E-0,
Reactor Trip or Safety Injection, step 8. Verify all Feedwater Isolation
status lights (1 SI-5) - LIT.?
A. Prevent water from entering the steam lines due to
uncontrolled CA flow.
B. Prevent water from entering the steam lines due to
uncontrolled CF flow.
C. Prevent excessive NC system cooldown due to
uncontrolled CA flow.
D. Prevent excessive NC system cooldown due to
uncontrolled CF flow.
Ques-9 87 For Official Use Only Page 65
Question #66 Catawba Nuclear Station RO Exam
1 Pt(s) Which one of the following statements correctly describes the analog and
digital portions of the Engineered Safety Features Actuation System?
A. There are 2 analog input channels.
There are 3 to 4 digital output logic trains.
B. There are 3 to 4 analog input channels.
There are 2 digital output logic trains.
C. There are 3 to 4 analog input channels.
There are 4 digital output logic trains.
D. There are 4 analog input channels.
There are 4 digital output logic trains.
Ques-990 For Official Use Only Page 66
Question #67 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 was operating at 50% power. Instrument air pressure is reading 80
psig in the control room.
Which one of the following actions should have just occurred?
A. Quick start of the standby air compressor
B. VI-670 'VI Dryer Auto Bypass' opened
C. CF control valves failed closed
D. VS-78 'VS supply to VI' opened
Ques-991 For Official Use Only Page 67
Question #68 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 was operating at 100% power. Given the following events and
conditions:
3 control rod drive mechanism (CRDM) vent fans are running.
CRDM vent fan 1D is out of service.
Lower containment temperature is 105 F and steady.
1B pipe tunnel booster fan (PTBF) is running in LOW.
Lower containment ventilation units (LCVUs) 1B, 1C and ID are
running in LOW speed and NORM cooling.
C1A1 08 1 (Reactor Vessel Head Area Temp) is 1 10 F
C 1A 1087 (Reactor Vessel Head Area Temp) is 1 10 F
ClA1093 (Digital Rod Pos Ind Cabinet Area Temp) is 97 F.
If one of the running CRDM fans trips on over-current, what is the first
action (if any) that needs to be taken by the crew?
REFERENCES PRO WDED:
A. Start a second PTBF.
B. Place all LCVUs to MAX cooling and shift LCVUs to high speed.
C. Place LCVU 1D and 1B only in MAX cooling and secure LCVU
1c.
D. Generate a work request to determine CRDM shroud leaving air
temperature.
Ques-99 2 For Official Use Only Page 68
Question #69 Catawba Nuclear Station RO Exam
1 Pt(s) When does the CPCS shutdown signal actuate and what is the purpose of this
automatic protection?
A. CPCS actuates at 0.3 psig to prevent drawing a negative pressure
in containment.
B. CPCS actuates at 0.3 psig to prevent NS pump runout caused by
decreasing backpressure.
C. CPCS actuates at 0.5 psig to conserve FWST inventory.
D. CPCS actuates at 0.5 psig to reduce RN heat load.
Ques-993 For Official Use Only Page 69
Question #70 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 1 is operating at 100% power when a main steam line break occurs on
the 1B steam generator. Given the following plant events and conditions:
The operators have entered EP/l/A/SOOO/E-O (Reactor Trip 01' Safety
Injection)
Maximum containment pressure was 1.5 psig
1A and 2A RN pumps are RUNNING
1RN36A (Rh' PUMP INJ FILT INLT X-OVER) OPEN
1RN37B (Rh' PUMP IIdJ FILT OTLT X-OVER) OPEN
1RN232A (D/G 1A HX INLET ISOL) OPEN
1RN292B (D/G 1B HX INLET ISOL) OPEN
1RN47A (RN SUPPLY X-OVER ISOL) CLOSED
1RN48B (RN SUPPLY X-OVER ISOL) CLOSED
All other ECCS systems operate properly
Which one of the following actions is required to place the RN system in the
correct configuration for the given conditions?
A. Close 1RN36A and open 1RN47A, 1B and 2B RN pumps are not
operating.
B. Close 1RN37B and OPEN 1RN48B, 1B and 2B RN pumps are
not operating.
C. Start 1B and 2B RN pumps, open 1RN47A & 1RN48B and close
1RN232A & 1RN292B.
D. Start 1B and 2B RN pumps, close 1RN36A & 1RN37B and open
1RN47A & 1RN48B.
Ques-994 For Official Use Only Page 70
Question #71 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is operating at 100% power. Given the following events and conditions:
a Normal letdown alignment exists
a Controlling pressurizer pressure channel fails low.
a Operator immediately transfers control to an alternate operable channel.
Assuming no additional operator action, which one of the following statements
correctly describes how letdown flow responds?
A. Letdown will isolate.
B. Letdown flow will indicate approximately 45 gpm.
C. Letdown flow will indicate approximately 75 gpm.
D. Letdown flow will indicate approximately 120 gpm
Ques-995 For Official Use Only Page 71
Question #72 Catawba Nuclear Station RO Exam
1 Pt(s) AP-2 1 (Loss Of Component Cooling) Foldout Page directs the operators to align
alternate cooling to the 1A NV pump. Enclosure 4, Step 7 directs the operators to
reduce motor cooler and oil cooler flow.
Why is YD flow to the 1A NV pump motor cooler and oil cooler flow reduced?
A. To preserve the YD storage tank inventory and to minimize chloride
contamination of the KC system.
B. To maintain motor bearing temperature less than 160°F and stator
temperature less than 240°F.
C. To minimize chloride contamination of the KC system only.
Ques-99 7 For Official Use Only Page 72
Question #73 Catawba Nuclear Station RO Exam
_ _ _ _ _ _ _ ~
I Pts Unit 1 was operating at 100% power.
Which one of the following malfunctions could occur and still have KC train
A remain operable?
REFERENCES PROVIDED:
A. 1A2 KC pump has failed
B. 1A KC surge tank has been drained
C. 1A KC heat exchanger is being cleaned
Ques-998 For Official Use Only Page 73
Question #74 Catawba Nuclear Station RO Exam
1 Pt(s) Unit 2 is operating at 23% power. Given the following events and conditions:
120VAC panel 2ERPA fails
Which of the following statements is correct?
REFERENCES PROVIDED:
A. D/G 2A cannot be run in manual and it will run in auto due to an
emergency start signal.
B. D/G 2A cannot be run in manual and it will not run in auto due to an
emergency start signal.
C. D/G 2A can be run in manual and it will not run in auto due to an
emergency start signal.
D. D/G 2A can be run in manual and it will run in auto due to an
emergency start signal.
Ques-999 For Official Use Only Page 74
___5_ -
Question #75 Catawba Nuclear Station RO Exam
1 Pt(s) IAE technicians are performing IP/O/B/3260/001 (Maintenance and
Troubleshooting Procedure for Making changes to 1.47 Bypass System) at
the local panel in the cable spreading room. They need the BOP to verify
plant process information in the control room.
Which one of the following statements correctly describes how these
communications should be conducted from the control room?
A. Communication should be over hand-held radios. Three-way
communication procedures are required.
B. Communication should be over hand-held radios. Three-way
communication procedures are NOT required.
C. Communication should be over plant telephones. Three-way
communication procedures are required.
D. Communication should be over plant telephones. Three-way
communication procedures are NOT required.
Ques-1024 For Official Use Only Page 75