ML032100227
| ML032100227 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/16/2003 |
| From: | Operator Licensing and Human Performance Branch |
| To: | Duke Energy Corp |
| References | |
| 50-369/03-301, 50-370/03-301, FOIA/PA-2004-0122 | |
| Download: ML032100227 (79) | |
See also: IR 05000369/2003301
Text
Final Submittal
(Blue Paper)
1. Reactor Operator Written Examination
~
MCGUIRE JUNE 2003 EXAM
50-36912003-301 AND
50-370/2003-301
-
JUNE 16 30,2003
ANSWER KEY REPORT
for RO McGuire 2003 test Test Form: 0
1 ANSWER-KEY 1 1.00 MCS B
2 ANSWER-KEY 2 1.00 MCS D
3 ANSWER-KEY 3 1.00 MCS D
4 ANSWER-KEY 4 1.00 MCS C
5 ANSWER-KEY 5 1.00 MCS A
6 ANSWER-KEY 6 1.00 MCS D
7 ANSWER-KEY 7 1.00 MCS C
8 ANSWER-KEY 8 1.00 MCS D
9 ANSWER-KEY 9 1.00 MCS C
10 ANSWER-KEY 10 1.00 MCS C
11 ANSWER-KEY 11 1.00 MCS B
12 ANSWER-KEY 12 1.00 MCS D
13 ANSWER-KEY 13 1.00 MCS B
14 ANSWER-KEY 14 1.00 MCS A
15 ANSWER-KEY 15 1.00 MCS A
16 ANSWER-KEY 16 1.00 MCS B
17 ANSWER-KEY 17 1.00 MCS D
18 ANSWER-KEY 18 1.00 MCS D
19 ANSWER-KEY 19 1.00 MCS D
20 ANSWER-KEY 20 1.00 MCS A
21 ANSWER-KEY 21 1.00 MCS B
22 ANSWER-KEY 22 1.00 MCS C
23 ANSWER-KEY 23 1.00 MCS C
24 ANSWER-KEY 24 1.00 MCS A
25 ANSWER-KEY 25 1.00 MCS B
26 ANSWER-KEY 26 1.00 MCS A
27 ANSWER-KEY 27 1.00 MCS A
28 ANSWER-KEY 28 1.00 MCS A
29 ANSWER-KEY 29 1.00 MCS C
30 ANSWER-KEY 30 1.00 MCS B
31 ANSWER-KEY 31 1.00 MCS D
32 ANSWER-KEY 32 1.00 MCS D '
33 ANSWER-KEY 33 1.00 MCS C
34 ANSWER-KEY 34 1.00 MCS B
35 ANSWER-KEY 35 1.00 MCS C
36 ANSWER-KEY 36 1.00 MCS A
37 ANSWER-KEY 37 1.00 MCS D
38 ANSWER-KEY 38 1.00 MCS D
39 ANSWER-KEY 39 1.00 MCS A
40 ANSWER-KEY 40 1.00 MCS C
41 ANSWER-KEY 41 1.00 MCS B
42 ANSWER-KEY 42 1.00 MCS D
43 ANSWER-KEY 43 1.00 MCS C
44 ANSWER-KEY 44 1.00 MCS D
45 ANSWER-KEY 45 1.00 MCS B
46 ANSWER-KEY 46 1.00 MCS C
Tuesday, July29,2003 07:40:14 AM 1
ANSWER KEY REPORT
for RO McGuire 2003 test Test Form: 0
47 ANSWER-KEY 47 1.00 MCS B
48 ANSWER-KEY 48 1.00 MCS D
49 ANSWER-KEY 49 1.00 MCS A
50 ANSWER-KEY 50 1.00 MCS A
51 ANSWER-KEY 5 1 1.00 MCS C
52 ANSWER-KEY 52 1.00 MCS B
53 ANSWER-KEY 53 1.00 MCS B
54 ANSWER-KEY 54 1.00 MCS D
55 ANSWER-KEY 55 1.00 MCS B
56 ANSWER-KEY 56 1.00 MCS D
57 ANSWER-KEY 57 1.00 MCS D
58 ANSWER-KEY 58 1.00 MCS B
59 ANSWER-KEY 59 1.00 MCS D
60 ANSWER-KEY 60 1.00 MCS D
61 ANSWER-KEY 61 1.00 MCS A
62 ANSWER-KEY 62 1.00 MCS B
63 ANSWER-KEY 63 1.00 MCS D
64 ANSWER-KEY 64 1.00 MCS A
65 ANSWER-KEY 65 1.00 MCS C
66 ANSWER-KEY 66 1.00 MCS D
67 ANSWER-KEY 67 1.00 MCS B
68 ANSWER-KEY 68 1.00 MCS D
69 ANSWER-KEY 69 1.00 MCS C
70 ANSWER-KEY 70 1.00 MCS A
71 ANSWER-KEY 71 1.00 MCS C
72 ANSWER-KEY 72 1.00 MCS D
73 ANSWER-KEY 73 1.00 MCS B
74 ANSWER-KEY74 1.00 MCS C
75 ANSWER-KEY 75 1.00 MCS D
SECTION 1 ( 75 items) 75.00
Tuesday, July 29,2003 07:40:14 AM 2
ES-401 Site-Specific RO Written Examination Form ES-401-7
Cover Sheet
U.S. Nuclear Regulatory Commission
Site-Specific
RO Written Examination
Applicant Information
Name:
Date: June 30, 2003 Facility/Unit: McGuire
Region: II Reactor Type: Westinghouse
-1 1 - 11 "
Instructions
Use the answer sheets provided to document your answers. Staple this cover sheet on top
of the answer sheets. To pass the examination you must achieve a final grade of at least
80.00 percent. Examination papers will be collected six hours after the examination starts.
Applicant Certification
All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature
Results
Examination Value Points
Applicant's Score Points
1 Applicant's Grade Percen1
31of 34 NUREG-1021, Draft Revision 9
1 Pt After a loss of all AC power (station blackout), ES 0.2 (Natural Circulation
Cooldown) is implemented after AC power has been restored.
Given the following conditions:
1) NC pumps cannot be restarted.
2) Power has been restored to all station AC busses.
3) A natural circulation cooldown is in progress.
Step 18 of ES 0.2 requires that the operators maintain subcooling greater than 50
degrees if ali CRD fans are running and greater than 100 degrees if less than all
CRD fans are running using core exit thermocouples.
What is the EOP basis for these limits?
A. To prevent degradation of reactor coolant pump seals due to steam.
B. To prevent possible void formation in the upper head.
C. To collapse any voids formed in the CRD housings.
D. To ensure adequate subcooling due to possible degradation of core
exit T/Cs accuracy.
Ques-47.1
1 Pt. Which one of the following selections correctly matches the reactor trip
signals to their limiting accident?
Reactor Trip Siunal Limitinu AccidentlProtection
A. OPAT DNB
OTAT Excessive fuel centerline temperature
Pzr High Level DNB
Pzr Low Pressure NC system integrity
B. OPAT Excessive fuel centerline temperature
OTAT DNB
Pzr High Level DNB
Pzr Low Pressure NC system integrity
C. OPAT DNB
OTAT Excessive fuel centerline temperature
Pzr High Level NC system integrity
Pzr Low Pressure DNB
D. OPAT Excessive fuel centerline temperature
OTAT DNB
Pzr High Level NC system integrity
Pzr Low Pressure DNB
Ques-048.l.doc
1 Pt Given the following conditions:
Unit 1 has experienced a large break LOCA
30 minutes have elapsed since the LOCA
FWST Lo Lo level annunciator has just alarmed
Which one (1) of the following describes the operator actions for the alignment of
the containment spray system after a LOCA?
A Reset Containment Spray and Phase B and stop NS pumps within 45
seconds and manually swap the pump alignment to take suction on
the containment sump.
B. Reset Containment Spray and the NS pumps will automatically swap
over to take a suction on the containment sump when FWST level
reaches 33.
C. Reset Containment Spray and Phase B and stop the NS pumps
within 45 seconds when FWST level reaches 33 and initiate
containment spray flow from the ND system.
D. Reset Containment Spray and stop the NS pumps within 45 seconds
when FWST level reaches 33 and manually swap the pump
alignment to take suction on the containment sump.
50.1 doc
1 Pt. A large break LOCA is in progress and the operators are responding in
FR-Z.l (Response to High Containment Pressure). Given the following
conditions:
ND pump 1A is tagged out of service for maintenance.
Containment pressure is 14 psig.
FWST level reaches the swap-over setpoint.
When shifting to cold leg recirc using ES-1.3 (Transfer to Cold Leg Recirc),
valve INI-184B (RB Sump to Train 1B ND & NS) fails to open. The
operators implement ECA-1.I(Loss of Emergency Coolant Recirculation).
FR-Z.l (Response to High Containment Pressure) requires both NS Dumps
to be in operation. ECA-1.1 limits the operators to only one NS Dump in
step 6. Which of these two procedures takes priority under these
conditions and what is the basis for this requirement?
k FR-2.1 takes priority because a total loss of ND causes the NS
system to become relatively more important to reduce
containment pressure.
6. FR-2.1 takes priority because it was implemented in response
to a red path and FRPs always have priority over ECA
procedures.
C. ECA-1.1 takes priority because it conserves FWST water level
as long as possible for injection while providing sufficient NS
flow to mitigate containment pressure.
D. ECA-1.Itakes priority because ECA procedures always have
priority over FRPs.
Ques-05l.l.doc
1 Pt. Unit 2 was operating at 100% power when an electrical fire started inside
the auxiliary building cable spreading room. AP/O/N5500/45 Plant Fire has
been implemented.
Which one of the following describes how the of fire suppression system is
actuated inside the cable spreading area and what are the hazards to
personnel if they enter this room?
A. An NLO is dispatched to open a manual deluge valve. An
electrical shock hazard exists due to the use of water to
combat an electrical fire.
B. An NLO is dispatched to verify automatic sprinkler system
actuation. An electrical shock hazard exists due to the use of
water to combat an electrical fire.
C. An NLO is dispatched to verify automatic Halon system
actuation. An asphyxiation hazard exists due to the presence
of Halon gas.
D. An NLO is dispatched to actuate a manual Cardox system. An
asphyxiation hazard exists due to the presence of carbon
dioxide gas.
__________._________---------.-
Ques-060.2.doc
4
1 Pt Unit 1 is at 12% power with 4 NCPs running during a plant startup when an
electrical transient occurs on the 6.9KV busses.
Given the following transient conditions:
Electrical Bus
Freauencv (Hz) 55 60 55 60
Voltage (C&s AC) 6800 6900 6800 6900
Offsite bus-line 1A is supplying TA and TC
Offsite bus-line 1B is supplying TB and TD
Which one of the following describes the immediate plant response to this
A. No NCP pumps trip and the reactor does NOT trip
B. The 1' A 'and 1 'C' NCPs trip and the reactor trips
C. All four NCPs trip but the reactor does NOT trip
D. All four NCPs trip and the reactor trips
Ques-63.l.doc
7
1 Pt Unit 1 has experienced an ATWS and the operators are performing the immediate
action steps of FR-S.1 (Response to Nuclear Power GenerationIATWS).
Given the following malfunctions:
1) The reactor is manually tripped
2) The turbine fails to trip automaticallyand manually
Which one of the following describes the operator's response in FR-S.1 to respond
to failure of the turbine to trip?
A. Place turbine in EMERGENCY MANUAL and close governor valves in
fast action and close all MSlVs
B. Place turbine in MANUAL and close governor valves in fast action and
close all MSlVs
C. Place turbine in MANUAL and close governor valves in fast action and
if turbine will not runback then close all MSlVs and MSlV bypass
valves
D. Place turbine in EMERGENCY MANUAL and close governor valves in
fast action and if turbine will not runback then close all MSlVs and
MSlV bypass valves
.
107.1 doc 1
1 Pt Given the following plant conditions:
Unit 1 in Mode 6.
Reactor Missile Shield removed.
"Norm-Refuel" Selector Switch in the REFUEL position.
Fan Mode Selector Switch in the 100% position.
1EMF-38 trip 2 alarm.
Which one of the following selections describes the COMPLETE
system response by the Containment Purge System?
A. Supply Fan (IB) will STOP.
Supply Damper will CLOSE.
Exhaust Fan (IB) will STOP.
Exhaust Damper will CLOSE.
Upper Containment Inside Isolation Valves will CLOSE.
Upper Containment Outside Isolation Valves will CLOSE.
Lower Containment Inside Isolation Valves will CLOSE.
Lower Containment Outside Isolation Valves will CLOSE.
B. Supply Fans (1A & IB) will STOP.
Exhaust Fan ( I A & 16) will STOP.
Upper Containment Inside Isolation Valves will CLOSE.
Upper Containment Outside Isolation Valves will CLOSE.
C. Supply Fan (IB) will STOP.
Exhaust Fan (IB) will STOP.
Lower Containment Inside Isolation Valves will CLOSE.
Lower Containment Outside Isolation Valves will CLOSE.
0 . Supply Fans (1A & 1B) will STOP.
Supply Damper will CLOSE.
Exhaust Fan (IA & I B ) will STOP.
Exhaust Damper will CLOSE.
Upper Containment Inside Isolation Valves will CLOSE.
Upper Containment Outside Isolation Valves will CLOSE.
Lower Containment Inside Isolation Valves will CLOSE.
Lower Containment Outside Isolation Valves will CLOSE.
QuesJ3l.l.doc
1 Pt Which ONE (1) of the following Containment Radiation Monitors will initiate
containment ventilation isolation as indicated by the corresponding
sequence of actions?
A. EMF38(H) trip-I will secure VP and VQ, and shutoff
containment sump pumps and incore sump pumps.
B. EMF-39(L) trip-I will sound the containment evacuation alarm,
and secures VP and VQ.
C. EMF40 trip-2 will secure VP and VQ, and shutoff containment
sump pumps and incore sump pumps.
D. EMF41 trip-2 will secure VP and VQ, and shutoff containment
sump pumps and incore sump pumps.
Ques-162.l.doc
I"
1 Pt Unit 1was operating at 100% when a pipe break occurred on the I D S/G
steam header. The operators are responding in E-2(Faulted Steam
Generator lsolation). The following sequence of events occurred:
Isolation of the I D S/G
PZR level dropped to 0% and was restored to 20%
NCS pressure is 1900 psis
Safety Injection has not been reset
What are the correct panel actions for the restoration of power to pressurizer
back-up heater bank D?
A. Reset safety injection on 1MC6.
Ensure AUTO is selected on the heater mode switch on IMC-
10
Select CLOSED on the heater breaker switch on 1MC-5
(vertical board)
6. Ensure AUTO is selected on the heater mode switch on IMC-5
Select CLOSED on the heater breaker switch on IMC-10
Select ON for the heater control switch on IMC-5
C. Select MANUAL on the heater mode switch on IMC-10
Select CLOSED on the heater breaker switch on IMC-5
Select ON for the heater control switch on IMC-10
D. Reset safety injection on IMC-6
Select MANUAL on the heater mode switch on IMC-5
Select CLOSED on the heater breaker switch on IMC-10
Select ON for the heater control switch on IMC-5
_______.___.__._____--.----------
1 Pt Unit 1 was operating at 100% power when a total loss of feedwater
occurred. The operators reached Step 7 of FR-H.l (Response to Loss of
Secondary Heat Sink), which attempts to establish CA flow to at least one
S/G. Sub-step 7.k states:
Maintain feed flow rate less than o r equal to 100
GPM until S/G WR level is greater than 12% (17%
ACC).
Given the following conditions:
Loop A Loop B LOORC Loov D
S/G (WR) [%] @ 15 9 10
NC THO, [F] 150 555 530 545
Containment pressure is 3.4 psig
The TD CA pump is available to feed the SlGs
Which one of the following statements correctly describes the bases for the
restrictions for restoring feedwater flow following feed and bleed in FR-H.1?
k Restore flow to the ASIG because loop A T-hot is the lowest
of the loops and this will reduce the chance of thermal
shocking the SIG. Flow should not be restored to the Band
C SIGs because they will be reserved for use later to provide
a steam supply for the TD CA pump.
B. Restore flow to the B SIG because B SIG level is the highest
and this will reduce the chance of thermal shocking the SIG.
Flow should be preferentially restored to the B or C SIG to
maintain the TD CA pump steam supply.
C. Restore flow to the C SIG because loop C T-hot is less than
loop BT-hot and this will reduce the chance of thermal
shocking the SIG. Flow should be preferentially restored to
the Bor C SIG to maintain the TD CA pump steam supply.
D. Restore flow to the D SIG because the DSIG is higher than
ASIG level, which will reduce the risk of thermal shock. Flow
should not be restored to the B and C SIGs because they
will be reserved for use later to provide a steam supply for the
TD CA pump.
1 Pt Unit 1 was conducting a plant start up. At 1% power, an instrument
malfunction caused an inadvertent reactor trip. Given the following
indications:
Two rod bottom lights are NOT lit
Reactor trip and bypass breakers are open
IR amps = 2x10"
IR SUR = -0.3 DPM
Which one of the following response actions is required?
k Implement AP/14, (Control Rod Misalignment) and respond to
the stuck rods.
B. Implement E-0, (Reactor Trip or Safetylnjection), and
immediately transition to FR-S.2, (Response to Loss of Core
Shutdown).
C. Implement E-0, (Reactor Trip or Safety lnjection) and
immediately transition to FR-S.1, (Response to Nuclear Power
GeneratiodATWS) .
D. Implement E-0, (Reactor Trip or Safety hjection), and then
transition to ES-0.1, (Reactor Trip Response).
1 Pt Unit 1 is in mode 6 and in the process of unlatching control rods. Which
ONE (1) of the following limiting conditions requires immediately
suspending all CORE ALTERATIONS in the Reactor Building?
A. Loss of one channel of SR N l s with both Gamma Metric SDMs
in operation.
B. Loss of direct communications between the control room and
the refueling bridge (refueling station).
C. Loss of the Fuel Handling Ventilation System.
D. Time since entering mode 2 is 102 hours0.00118 days <br />0.0283 hours <br />1.686508e-4 weeks <br />3.8811e-5 months <br />.
Ques-228.l.doc
\4
1 Pt Unit 1 is operating at 50% power. Given the following conditions:
Pressurizer pressure is 2235 p i g
Pressurizer Relief Tank (PRT) pressure is 20 psig
PRT temperature is 125 O F
PRT level is 81%
The PRT is being cooled by spraying from the RMWST
A pressurizer code safety valve is suspected of leaking by its seat
What temperature would be indicated on the associated safety valve
discharge RTD if the code safety were leaking by?
REFERENCES ?ROVIDED
A. 258-262°F
B. 227-231 OF
C. 161-165°F
D. 123-127°F
Ques-3ll.Z.doc
1 Pt In E-3 (Steam Generator Tube Rupture) Enclosure 5 (NC Pressure and
Makeup Control to Minimize Leakage) the operators are directed to
energize pressurizer heaters if the ruptured S/G level is decreasing and
pressurizer level is greater than 25%.
What is the purpose for this action?
A. Maintain pressurizer saturation temperature corresponding to
ruptured SIG pressure to minimize SIG leakage into the NC
system.
B. Maintain pressurizer saturation temperature corresponding to
intact SIG pressure to minimize primarj leakage into the SIO.
C. Maintain pressurizer saturation temperature above the
corresponding ruptured SIG pressure to ensure SIG water
does not flow into the NC system.
D. Maintain pressurizer saturation temperature corresponding to
intact SIG pressure to minimize NC pressure transients.
Ques-32l.l.doc
1 Pt During a cold startup, the NCPs are limited to 3 consecutive starts in any 2-
hour period. There is an additional requirement of a minimum idle period of
60 minutes between restarts. What is the reason for these limitations?
k This restriction assures that the NCP oil temperature will
decrease to design specifications between restart attempts.
6. This restriction prevents overheating the motor windings due
to high starting currents.
C. This restriction allows the NCP seals to fully reseat between
NCP oil lift pump cycles.
D. This restriction ensures adequate Number 1 Seal Leakoff flow.
Ques-330.l.dcc
1 Pt Unit 1 is responding to a small break LOCA using E-I (Loss ofReactoror
Secondary Coolant). Given the following events and conditions:
FWST Level = 340 inches
Containment pressure = 1.5 psig
Containment Sump Level = 1.05 ff
EMF41 (AUXBLDG VENTILATION) = trip 2
Aux Building area radiation monitors are in alarm
EMF-51A and B (CONTAINMENT TRNA & 6) = 25 WHr
Hydrogen Analyzer = 0.7% in containment
NLOs report significant leakage at the seals of the 1A ND pump
Whicn one or' the foilowing procedures should the operator transiliort inlo
from E-I?
A. FR-2.3 (Response to High Containment Radiation Level)
6. ECA-1.I(Loss of Emergency Coolant Recirculation)
C. FR-2.4 (Response to High Containment Hydrogen)
D. ECA-1.2 (LOCA Outside Containment)
______._____________---.--.---.---
1 Pt Unit 2 was at 10% during a plant startup when a loss of condenser vacuum
occurred. Given the following conditions:
The reactor was tripped
The steam dump select switch was in steam pressure mode
Condenser vacuum dropped to 18 inches
No component or instrument failures occurred
No operator action taken
Which one of the following sequences best describes the actuation of the
steam dumps to this event?
Condenser dump valves Atmospheric dump valves
A. open open
B. open shut
C. shut open
D. shut shut
Ques-373. Ldcc
1 Pt Unit 1 has initiated a liquid radioactive waste release from the Ventilation
Unit Condensate Drain Tank (VUCDT) through the RC system. All lineups
and authorizations have been properly made in accordance with
OP/1/A/6500/001 A usingJ
the
J~~ path. Two RC pumps are the
minimum required under the LWR document.
Given the following initial conditions:
3 RC pumps are running
1EMF44 (CONT VENT DRN TANK OUV correctly set for trip 1 and
trip 2 activity limits
No other releases are in progress
If the release automatically terminates 40 seconds after initiation, which
one of the following conditions could have terminated the release?
A. 1WM-46 (LIQUID WASTE DISCH VALVE) closing automatically
if 2 RC pumps trip
8. 1WM-46 closing automatically if 1EMF-44 reached the trip 2
setpoint
C. IWP-35 (WMT & VUCDT TO RC CNTRL) closing automatically
if 1 RC pump tripped
D. IWP-35 closing automatically if 1EMF-44 reached the trip 2
setpoint
__._______._.___._____________
Ques-407.l.doc
1 Pt Unit 1 has just entered Mode 5 in preparation for refueling. Given the
following conditions and events:
A lower containment entry is planned for the next shift.
The SRO directs the RO to purge the containment in preparation for
the containment entry.
Currently the VP system is secured with all fans off and containment
purge and exhaust valves closed
Which one of the following describes the proper alignment of the
containment purge system?
A. The MORMAL-REfUL SELECTOR switch is placed in the
"NORM' position and ratio of supply air is 211 (UppedLower
Containment).
6. The NORMAL-RFUL SELECTOR switch is placed in the
"NORM' position and ratio of supply air is 411 (Upper/Lower
Containment).
C. The NORMAL-REFUEL SELECTOR switch is placed in the
"REFUEL" position and ratio of supply air is 2/1 (UppedLower
Containment).
D. The NORMAL-REFUEL SELECTOR switch is placed in the
"REFUEL" position and ratio of supply air is 4/1 (UppedLower
Containment).
Ques-432.3.doc
1 Pt Unit 1 is shutdown in a refueling outage. Given the following events and
conditions:
The VI system was in a normal lineup.
The VS system was in a normal lineup.
A VI header rupture occurs.
The VI system completely depressurizes.
What effect does a total loss of the VI system have on the VS system?
A. VI-820 will auto-close as VI header pressure decreases below
82 psig and the VS air compressor will start automatically to
maintain VS headei pressuie.
B. VI-820 will auto-close as VI header pressure decreases below
90 psig and the VS air compressor must be manually started to
maintain VS header pressure.
C. -
Check valves in the VI VS cross-connect line will close to
isolate VS system pressure before it drops below 90 psig.
D. VS pressure in the Fire Protection Pressurizer Tank will be lost
until a VS air compressor can be started.
1 Pt Unit 2 is operating at 75% power when a load rejection occurs. Which one
of the following statements correctly describes the response of 2CM-420
(Load Rej Byp) to this transient?
A. 2CM-420closes to prevent condensate water from being
diverted to the suction of the hotwell pumps from the
condensate booster pumps to assure minimum flow to the CF
pumps.
B. 2CM-420closes to prevent diversion of water from the "C"
heater drain tank back to the UST thereby ensuring sufficient
CF pump suction pressure.
C. 2CM-420opens to divert condensate flow directly to the
condensate booster pump suction to ensure that CF pumps
have sufficient suction pressure.
D. 2CM-420opens to divert condensate flow, bypassing around
the condensate booster pumps, directly to the CF pumps to
assure minimum flow requirements.
Ques-531. Ldcc
23
1 Pt Unit 1 was operating at 100% power when main condenser vacuum drops
from 25 inches vacuum to 23 inches vacuum. Given the following events
and conditions:
All 3 condenser steam air ejectors (CSAEs) are in service
Both primary and secondary jets are operating
The system lineup is in the normal configuration
Which one of the following statements correctly describes the cause of this
problem?
A. Loss of YM supply to the condenser boot seals
B. Loss of Main Steam to the CSAEs
C. CM flow to all CSAE intercoolers has been obstructed
D. A CSAE drain was left open
1 Pt Unit 1 was operating in Mode 3 during a plant shut down for a refueling
outage. If a safety injection signal is received, which one of the following
events will occur to protect the vital AC busses from overload?
A. Only non-LOCA loads will be shed. The accelerated sequence
will sequence remaining loads on after checking for adequate
bus voltage.
B. A complete load shed will occur. The accelerated sequence
will sequence LOCA loads on after checking for adequate bus
voltage and DG speed.
C. A complete load shed will occur. The accelerated seqmnce
will sequence LOCA loads on after checking for adequate bus
voltage.
D. Only non-LOCA loads will be shed. The accelerated sequence
will sequence remaining loads on after checking for adequate
bus voltage and DG speed.
________________________
Ques-548.l.doc
25
1 Pt Unit 2 was operating at 99% power when a steamline break occurred.
Given the following events and conditions:
0200 The operators enter AP/OI (Steam Leak)
0200 ,, and Tref
The operators start reducing turbine load to match ,T
0201 The operators start a second NV pump and isolate letdown
0202 NLOs start investigatingfor the location of the steam leak
0203 P/R OVER POWER ROD STOP alarms - the RO reports that
power is now going down.
0204 STA reports pressurizer level is decreasing and cannot be
maintained
0205 The turbine building operator reports that the line to the
atmospheric dump valves has a steam leak and cannot be isolated
If no safety injection has occurred and pressurizer pressure is maintained,
which one of the following operator responses is correct?
A. Manually trip the reactor at 0203
B. Manually trip the reactor at 0204
C. Manually trip the reactor at 0205
D. Commence a rapid down power using AP/04 (Rapid
Downpower) at 0205
___.______.__._____.------------
1 Pt Unit 2 was operating at 90% power after a start-up from a refueling outage.
A pressurizer PORV is found to be leaking and the associated PORV block
valve was shut. The PRT was cooled down to the following PRT
conditions:
PRT Level - 65%
PRT Pressure - 9 psig
PRT Temperature - 1OOF '
Lower Containment Temperature - 118 "F
What actions are required to restore and maintain normal operating
conditions to the PRT for the long term?
k Vent the PRT to the waste gas system.
B. Vent the PRT to containment.
C. Cool the PRT by pressurizing with nitrogen and initiating spray
flow from the NCDT.
Ques-617.2.doc
1 Pt Unit 1 has experienced a rupture of the RN piping inside containment.
Emergency procedures prescribe successful response mechanisms if
containment water level remains between 3.5 and 10.5 feet.
Why is safe plant recovety not assured for a design basis large break
LOCA when containment water level exceeds 10.5 feet?
A. Operation of critical ECCS components needed for safe
recovery is endangered by submersion.
6. Operation of the NS pumps is endangered by excess debris
fouling the containment suction strainers.
C. Operation of the hydrogen purge system is compromised by
loss of direct access to the containment atmosphere.
D. Operation of the ND system is compromised by high suction
pressure
...........................................................................................
1 Pt Unit 1 is operating at 100% power. The battery charger 1EDGA for the 1A
emergency diesel generator battery has failed and will not provide a DC
output.
Which one of the following statements correctly describes the effect on the
1A emergency diesel generator?
A. The 1A emergency diesel generator will start but not continue
to run for its design basis committed time period without the
battery charger in service.
B. The 1A emergency diesel generator will not start without the
battery chaqer in service,
C. The 1A emergency diesel generator will start and run because
the battery charger has a vital DC backup power supply, and
will automatically supply the vital loads after starting.
D. The 1A emergency diesel generator will start and run because
all safety grade auxiliary loads are supplied from the GOOVAC
motor control center supplied from 1 E W
__.______.______.---I____________.._____ _-_.----._____.-
Ques-895. Ldoc
1 Pt The crew has verified natural circulation in ES-0.1 (Reactor Trip Response)
based on decreasing core exit thermocouple readings and subcooling > 0
OF. Ten minutes later, the operator notes that the thermocouple input to
both plasma displays is malfunctioning.
Which one of the following correctly describes a indication that natural
circulation is continuing?
k SIG saturation temperatures are decreasing and REACTOR
VESSEL URLEVELindication is greater than 100 %.
5. SIG pressures are decreasing and Tcold is at SIG saturation
temperature.
C. SIG pressures are decreasing and REACTOR VESSELDIP
indication is greater than 100%.
D. SIG pressures are decreasing and Thot is at SIG saturation
temperature.
___________I___._________________I_
1 Pt Unit 2 was operating at 100% when a complete loss of offsite power
(LOOP) occurred. All systems were operable and in a normal alignment.
Which one of the following containment ventilation systems will have all
operating fanslair handling units stopped after 5 minutes without any offsite
power?
A. VU ventilation units
B. Pressurizer booster fans
C. Pipe tunnel booster fans
D. Steam generator booster fans
1 Pt Unit 2 was at 75% R.T.P. when a loss of condenser vacuum occurred.
Given the following conditions:
Rods are in automatic
The steam dump select switch is selected to 'Tave' mode
Condenser vacuum is slowly decreasing
No component or instrument failures occurred
No operator action taken
Which one of the following sequences best describes the actuation of the
control rods to this event?
A. Control rods move in due to decreased condenser back
pressure
B. Control rods move out due to decreased condenser back
pressure
C. Control rods move in due to increased condenser back
pressure
D. Control rods move out due to increased condenser back
pressure
_._______.______-.__~---.------
Ques-963.l.doc
1 Pt Unit 1 is responding to a LOCA from a trip at full power. Given the following events
and conditions:
A safety injection occurred at 0200.
FWST level reaches 33 in. at 0246.
SA, Sequencers, and Containment Spray have been reset for both
trains.
The 16 NS pump has been successfully swapped to the containment
sump.
INS-18A (A NS Pump Suct From Cont Sump) will not open.
Which one of the following is the reason INS-18A will not open?
A. 1NS-43A ( A ND to NS Containment Outside /sol) is CLOSED
0. NS SYS CPCS TRAIN A INHIBIT light LIT
C. INI-185A (RE Sump to Train A ND 8, NS) is CLOSED
D. 1NS-43A (A ND to NS Containment Outside /sol) is OPEN
1 Pt Unit 2 is in an outage. All the fuel is in the spent fuel pool. A fuel shuffle is
in progress in the spent fuel pool. During the shuffle a fuel assembly is
accidentally damaged and 2EMF-42 (Fuel Building Ventilation Radiation
Monitor) goes into Trip 2.
Which one of the following describes the effect on spent fuel pool
ventilation system as a result of 2EMF-42 in Trip 2?
A. The VF supply and exhaust fans trip and the filter is placed in
the FILTRATION MODE.
B. No effect on VF system alignment.
C. The VF system is automatically placed in BYPASS MODE and
the discharge dampers open ana supply dampers close
D. The VF system is automatically placed in the FUEL HANDLING
MODE OF OPERATION and the supply fans trip.
..............................................................................
1 Pt Unit 1 is at 100% power when indications are received of a "1B' Reactor
Coolant Pump seal malfunction. AP/I/N5500/08 (Malfunction of NC
Pump) is implemented.
Which one of the following conditions describes a number two seal failure?
A. # 1 Seal Leak off flow - GOING DOWN
NC Pump number 2 Seal Standpipe low level alarm LIT -
NCDT input - STABLE, OR GOING DOWN
B. # 1 Seal Leak off flow - GOING UP
NC Pump number 2 Seal Standpipe high level alarm - LIT
NCDT input - STABLE, OR GOING DOWN
C. # 1 Seal Leak off flow - GOING DOWN
NC Pump number 2 Seal Standpipe high level alarm - LIT
NCDT input - GOING UP
D. # 1 Seal Leak off flow - GOING UP
NC Pump number 2 Seal Standpipe low level alarm LIT -
NCDT input - GOING UP
Ques-977.l.doc
1 Pt Which one of the following pre-planned activities that has been evaluated
and approved in advance by Operations can take place during shift
turnover?
A. Dilution to ECB
B. ZPPT
C. Drain to Mid-Loop
D. Reactor Startup
Ques-984. Ldoc
1 Pt. Unit 1 is responding to a small break LOCA inside and outside
containment. Given the following events and conditions:
FWST Level indicates 340 inches
Containment pressure indicates 1.5 psig
Containment Sump Level indicates 1.05 ft
IEMF-41 (AUXBLDG VENTILATION) is in Trip 2 alarm
Aux Building area radiation monitors are in alarm
1EMFdlA and B (CONTAINMENTTRNA & B) indicates 25 WHr
Hydrogen Analyzer indicates 0.7% in containment
NLOs report significant leakage at the seals of the IA ND pump
Which one of the foliowing actions reduces excessive levels of radiation
and guard against personnel exposure?
A. Monitor 1EMF-41 (AUXBLDG VENTILATION)
B. Dispatch NLO to energize Hydrogen Recombiners
C. Secure VA (Aux. Bldg. Ventilation System) to limit airborne
contamination.
Ques-1012.l.doc
1 Pt. Unit 1 is in mode 5 with the operators preparing for a plant startup by drawing a
bubble in the pressurizer.
Given the following conditions:
1) LTOPs is in service
2) Pressurizer pressure is 325 psig
3) Pressurizer level is 25%
4) Tay,= 175 F
If pressure increases to 400 psig, which one of the following describes the correct
inputs for a PORV to actuate in LTOP mode?
A. ID loop Hot iey WR temperature < 320 degrees and WR piessure D
loop >380 psig will actuate PORV NC-34A
B. C loop Cold Leg temperature < 320 degrees and NR pressure A
loop > 380 psig will actuate PORV NC-32B
C. C loop Cold Leg temperature < 320 degrees and WR pressure A
loop > 380 psig will actuate PORV NC32B
D. D loop Hot Leg WR temperature < 320 degrees and NR pressure D
loop 380 psig will actuate PORV NC-34A
1022.doc 1
1 Pt. Initial Conditions:
Unit 1 is at 100% power
A train essential components are in service
OAC alarms indicate an increase in reactor coolant pump motor winding
temperatures.
Which of the following describes the reason for the increase in
temperatures?
A. 1RN-40A (Train A to Non Essential Hdr Isol) has closed
B. 1KC-3388 (NCP Supply)has closed
C. 1RN43A (Train 1B to Non Ess Hdr Isol) has closed
D. 1KC-228B (RB HDR supply) has closed
1 Pt. Unit 2 was operating at 100% power with the Pressurizer Pressure Control
Switch in the '1-2' position and NC pressure in the normal operating band.
Given the following plant conditions and events:
NC pressure increases
PORVs 1NC 328 and NC 368 open at 2335 psig
Pressure modulates between 2315 psig and 2335 psig
Which one of the following instrument failures would cause this plant
response and what is the correct operator action perAPll1 (Pressurizer
Pressure Anomalies)?
k PZR presswe channel I fails high
Immediately swap controlling channels
B. PZR pressure channel II fails low
Place Pressurizer Pressure Master in Manual
C. PZR pressure channel I fails low
Place Pressurizer Pressure Master in Manual
D. PZR pressure channel II fails high
Immediately swap controlling channels.
____________________....-
1 Pt. Unit 1 is operating at 100% power when a small break LOCA occurs.
Given the following
a) Reactor Trip and Safety Injection Actuated
b) E-0 (Reactor Trip or Safety Injection) completed
c) Crew has exited E-0 to E-1 (Lossof Reactor or Secondary Coolant)
d) Both trains of ECCS equipment are functioning normally
e) Subcooling is 0 degrees
f) Pressurizer level is 2%
g) Containment pressure is 2.5 psig
Which one of the fo!lowing should be the status of the reactor coolant
pumps?
A. The reactor coolant pumps should still be running to provide
forced cooling through the core.
B. The reactor coolant pumps should be stopped to prevent
excessive depletion of the NC system water inventory.
C. The reactor coolant pumps should still be running to refill the
pressurizer in order to terminate Safety Injection flow.
D. The reactor coolant pumps should be stopped to prevent
pump damage due to loss of pump support systems.
Ques-lO25.doc
1 Pt. Unit 2 is operating at 100% power when the following occurs:
Loss of offsite power
Neither Diesel Generator starts
ECA-0.0 (Loss ofA//AC Power) is in effect
Standby Makeup pump for unit 2 tagged for maintenance
Reactor Coolant Pump seal injection valves have been closed
Twenty minutes later power is restored to Unit 2 ETA from Unit 1. and the
crew enters ECA-0.1 (Loss ofA//AC Power Recovery Without S//
Required).
Which of the following best describes the proper method for iesioring NCP
seal flows in ECA-O.1?
A. Slowly restore seal injection cooling limiting the cooldown rate to
1 degree per minute
B Do not restore seal injection cooling due to potential damage to
the KC thermal barrier heat exchanger.
C Restore seal injection cooling as rapidly as possible to minimize
the potential for seal degradation.
D. Do not restore seal injection cooling due to potential damage of
thermal shock to the reactor coolant pump seals.
1 Pt. Unit 1 has experienced a large break LOCA.
Given the following conditions:
E-0 (Reactor Trip or Safety Injection) is complete
ES 1.3 (Transfer to Cold Leg Recirc) is complete
Six hours have elapsed since the LOCA and ES 1.4 (Hot Leg
Recirc) is being implemented.
INI-121A (Train A NI to B & C Hot Leg) will not open due to
mechanical binding.
ND Train A has been aligned for Hot Leg Recirc.
ND Train B is aligned for Auxiliary Containment Spray.
Which of the following best describes the effects on the ND system if the
A ND pump trips?
A. Flow is lost to the A and E hot legs
E. Flow is lost to the A, E, C and D hot legs
C. Flow is lost to the E and C hot legs
D. Flow is lost to A and D hot Legs
Ques-1027.doc
1 Pt. Unit 1 is operating at 100% power when the 'A' Main steam line ruptures
outside containment and depressurizes the 'A S/G.
Which of the following describes the logic and coincidence needed to
actuate a Main Steam Isolation signal?
A. 114 on 1/4 steamlines
E. 213 on 214 steamlines
C. 1/4 on 2/4 steamlines
D. 213 cn 1/4 stearnlines
1 Pt. Given the following Unit 1 initial conditions
100% power with Tave = Tref
NC System Boron Concentration 953 ppm
Control Bank ' D rods are at 217 steps
Control Bank 'D' Rod H-8 drops fully into the core
AP/lA/5500/14 Rod Control Malfunction is entered and immediate
actions are completed
Thirty minutes after the rod drops
Load has been reduced to 95% power with Tave = Tref
NC System Boron Concentration 953 ppm
Control Bank ' D rods are at 217 steps
Rod H-8 has not been retrieved
Which one of the following describes the effect of the event on Rod
Insertion Limits and Shutdown Margin?
k Rod insertion limit is unchanged and shutdown margin is
increased.
8. Rod insertion limit is decreased and shutdown margin is
unchanged.
C. Rod insertion limit is unchanged and shutdown margin is
decreased.
D. Rod insertion limit is decreased and shutdown margin is
decreased.
_.___________.______------------
1 Pt. Unit 1 is in Mode 3 at normal operating temperature and pressure. While
performing trouble shooting activities 1NV-94AC (NC Pump Seal Return
Containment Isolation Valve) closes.
Which of the following best describes the effect on the Reactor Coolant
Pumps seal return flow?
A. Seal return flow continues and is routed to the NCDT.
B. Seal return flow continues through INV-95B to VCT.
C. Seal return flow continues and is routed to the PRT.
D. Seal return flow continues to the VCT through a bypass line
around 1NV-94AC.
Ques-1030.doc
1 Pt. Unit 2 was operating at 49% power when the following indications were
observed:
Steam Generator level in the 2A S/G is 84% on 2/3 level indications
Feedwater flows decreasing
Feedwater Isolation Signal actuated
Which of the following describes the plant response to the above condition?
A. Feedwater pump A only has tripped.
B. Both feedwater pumps have tripped, the turbine and ieactor have
tripped.
C. Feedwater pump Aand the turbine only have tripped.
D. Both feedwater pumps and turbine have tripped, the reactor did not
trip.
Ques-103l.doc
1 Pt. Given the following conditions:
Unit 1 isat 100%
No annunciators are in alarm
TD CA pump is being started for post maintenance testing (oil
change)
RO places the #TD I CA Pump to START
The TD CA pump starts but does not achieve rated speed.
Which of the following describes the potential reason the TD CA pump
failed to reach rated speed?
A. The TD CA pump stop valve is not fully open.
B 1SA48ABC ( I C S/G SM Supply to unit I TD CA Pump Turb Isol)
failed to OPEN.
C The Control RoomlLocal switch at local panel is in Local control.
D. The Woodward Governor speed setting was not cycled after the
last PT.
Ques-lO32.doc
1 Pt. During the delivery of chlorine gas cylinders on site, a cylinder fell from the
truck and ruptured. All control room VC intakes closed except IVC-SA (VC
OTSD AIR INTAKE ISOL FROM UNIT 2) and IVC-11B (VC OTSD AIR
INTAKE ISOL FROM UNIT 2) which were mechanically bound and failed to
close completely. Chlorine gas has entered the control room.
AP/l/N5500/17 (Lossof Control Room) has been implemented on both
Units.
Which one of the following describes S/G pressure control for the condition
described above?
A. All SIG PORVs are controlling between 1092 psig and 1125
psig.
8. A and 8 S/G PORVs are contralled manually to maintain
less than 1170 psig.
C. C and D SIG PORVs are controlled manually to maintain
less than 1170 psig
D. Only A and D SIG PORVs are controlling between 1092 psig
and 1125 psig.
._________-_________.-----------
1 Pt. Given the following conditions on Unit 1:
0 Blackout on ETB
0 The 1B D/G started in automatic mode and tripped due to overspeed
An Operator has been dispatched to depress Emergency Stop Reset
Pushbutton.
Which one (1) of the following describes why the diesel generator restarted
once the Emergency Stop Reset Pushbutton was depressed?
A. The engine overspeed trip resets, and the undervoltage
condition was still present.
B. The sequencer was reset to its ground state and the
accelerated sequence relay timed out.
C. The sequencer was reset and placed it in priority mode and the
undervoltage condition was still present.
D. The engine overspeed trip resets, and the accelerated
sequence relay timed out.
1 Pt Given the following conditions:
Unit 1 is operating at 25% power
All electrical systems are in normal alignment
The normal incoming breaker to 1EMXA trips because of a thermal
overload.
Which one of the following describes the effect on 125 VDC Distribution
Center EVDA?
A. No effect; alternate power to Charger Connection box ECB-1
will swap within 8 cycles and maintain power to EVBA.
B. No effect; battery EVCC will continue to power EVDA.
C. No effect; battery EVCA will continue to power EVDA.
D. EVDA will be deenergized until cross tied with EVDD.
Ques-1038.doc
1 Pt Unit 2 was operating at 100% when a Floor Cooling Glycol High
Temperature annunciator is received. A review of the RTD panel reveals
that several ice condenser floor slabs have high temperature indications.
An operator determines that 2NF-848 ( N f Floor Cooling Slab Temp
Control) has failed closed. An inspection of the lower ice condenser
reveals that eight (8) ice condenser bays have experienced buckling.
Which one of the following statements describes the effect on peak
containment pressure and time to reach peak containment pressure?
A. Design containment pressure of 15 psig will not be exceeded.
The time to reach peak containment pressure is 50 minutes.
B. Design containment pressure of 15 psig could be exceeded.
The time to reach peak containment pressure is 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />.
C. Design containment pressure of 60 psig will not be exceeded.
The time to reach peak containment pressure is 50 minutes.
D. Design containment pressure of 60 psig could be exceeded.
The time to reach peak containment pressure is 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />.
1 Pt Which one of the following are the power supplies for the Unit 1 MG sets?
k ILXE and ILXF
B. ILXFandILXG
C. ISLXF and ISLXG
D. ISLXG and ISLXH
Ques-1040.doc
1 Pt Which one of the following is the power supply for the 28 Hydrogen
Recombiner?
A. 2TA
0. ZETA
C. 2EMXC
D. 2EMXD
1 Pt Given the following conditions on Unit 2:
75%power
Annunciator Subcooling Margin Alert comes into alarm
Which one of the following describes the origin of the alarm?
Reference Provided
A. Wide Range Pressure Loop C fails to 0 psig
B. Wide Range Pressure Loop D fails to 0psig
C. One safety related thermocouple fails to 725 degrees
D. Wide Range T hot 6 loop failing high to 650 degrees
1 Pt Unit 1 was at 100% power when the AFWPT trips. Rods fail to insert as
required. The RO places the control rod mode select to manual. The
combined power mismatch signal is +4. The operator drives rod in.
Which one of the following describes the response of the rod control
system?
A. Rods will insert at 72 steps per minute.
B. Rods will insert at 64 steps per minute.
C. Rods will insert at 40 steps per minute.
D. Rods will insert at 48 steps per minute.
__________._________--------.-
Ques-1044.doc
1 Pt A fire on the McGuire site has rendered the control room uninhabitable due
to smoke in the control room. Both units have entered the AP/I/A/5500/17
(Loss of Control Room).
Which one of the following describes the RO actions described in
AP/I/A/5500/17 Loss of Control Room?
A. Go to Aux Shutdown Panel.
B. Go to main turbine front standard.
C. Go to Unit 1 CF pumps.
D. Go to REACTOR PUMP WATER MAKEUP CONTROL PANEL
if dilution in progress.
1 Pt While shifling to cold leg recirc during a LOCA, 1ND 58A (NWNlpump Train A
Isolation) will not open.
Which one of the following is a possible cause of this problem?
A. INI-1158 (A NI Pump Miniflow) must first be closed.
B. lNI-l85A( must first be open.
C. 1 ND-19A (A ND Pump Suction From FWST or NC) must first be open.
D. lNI-144B (B NI Pump Miniflow) must first be closed.
Ques-1046.doc
1 Pt Given the following conditions on Unit 1:
Unit 1 is in Mode 5 after an outage.
B Train of ND is in RHR mode
In the process of swapping to A train ND
An NLO is stationed outside the A ND HX room to listen for
excessive vibration.
After the swap has been completed the following is noticed
b. NC level decreasing and temperature increasing
c. ND flow increasing
Which one (1) of the following is the cause of the above failurc?
A Relief valve IND-56 (Discharge Relief Valve) has failed open to
6. IND-34 ( A 8 B ND Hx Bypass) fails OPEN
C. Relief valve IND-56 (Discharge Relief Valve) has failed open to
NCDT.
D. Flange leak on A RHR heat exchanger.
Ques-1047.doc
_ _ _ ~ ____ ~
1 Pt Given the following conditions on Unit 1:
Unit 1 ETB normal breaker has opened
'IB' Diesel Generator has started and has loaded the bus
Which one (1) of the following will trip the diesel generator?
k Lube Oil Temperature 195 degrees
B. Jacket Water Temperature 205 degrees
C. Turning Gear Engaged
D. Overspeed 113%
1 Pt Diesel generator 16 has been started per OP/I/N6350/002 (Diesel
Generator) from the control room. The diesel has been carrying the load
separated from the grid. It is time in the procedure to transfer load back to
the grid and shutdown the diesel.
Which one (1) of the following describes the actions in proper sequence
necessary to remove load from the diesel?
A. Match DIG voltage with line voltage
Place 1B DIG Sync Switch to ON
Adjust diesel speed to move slowly in the Fast direction using
1B DIG Gov Control pushbutton
Close normal breaker when 3 minutes before 12 oclock
Raise DIG output to 800 to 1000 KW
Adjust Power factor to .90 to .92
B. Place IB Sync Switch to ON
Adjust diesel speed to move slowly in the Fast direction using
Voltage Adjust pushbutton
Transfer load from IB DIG to IATD by obtaining zero amps
on IATD meter
Close normal breaker when 3 minutes before 12 oclock
Raise DIG output to 800 to 1000 KW
Adjust Power factor to .90 to .92
C. Place 1B Sync Switch to ON
Adjust diesel speed to move slowly in the Fast direction using
IB DIG Gov Control pushbutton
Close normal breaker when 3 minutes before 12 oclock
Raise DIG output to 100 to 200 KW
Adjust Power factor to .90 to .92
Match DIG voltage with line voltage
D. Place IB Sync Switch to ON
Adjust diesel speed to move slowly in the Fast direction using
Voltage Adjust pushbutton
Transfer load from IB DIG to IATC by obtaining zero amps
on IATC meter
Close normal breaker when 3 minutes before 12 oclock
Raise DIG output to 100 to 200 KW
Adjust Power factor to .90 to .92
1 Pt Given the following conditions on Unit 1:
Unit 1 heating up in Mode 3 following a refueling outage
An NLO calls the RO and advises that the boric acid filter deltafp is
pegged HIGH
Discharge pressure on 1A Boric Acid Tank pump is pegged HIGH
Which one (1) of the following describes the effect on the boron injection
flowpath from the Boric Acid Tank?
A. No effect after swapping to the 1B BAT pump.
B. Soron injecticiti flowpath from BAT via the boric acid pumps
and charging pump to NC is inoperable.
C. No effect after swapping to standby filter in service.
D. Boron injection flowpath is operable due to availability of
1 Pt Which one of the following describes the operational differences to ESF
systems for a double ended break inside containment versus a LOCA
outside Containment?
k On a LOCA outside containment there will be no containment
isolation signal.
B. There are no operational differences.
C. On a LOCA outside containment the containment sump valves
do not automatically open on low FWST level.
D. As FWST inventory depletes there is no corresponding
increase in containment sump level.
___________._._________I___
Ques-lO5l.doc
1 Pt Which one (1) of the following provides separation between control system
and protection system circuits?
A. Isolation Amplifier
B. Diodes
C. Separate input signal
D. Or/And gate
Ques-1052.doc
1 Pt Given the following conditions on Unit 1:
Loss of Offsite Power coincident with a LOCA
Power has been restored to ETA via '1A D/G while in
EP/I/A/5000/ECA-O.O (Loss ofA//AC Power)
NC Subcooling is -1 degree
Pzr level is 0%
1NI-9A (NC Cold Leg /nj from NV) is closed
INI-1OB (NC Cold Leg Inj from NV) is closed
Which one (1) of the following procedure is required for optimal recovery of
the plant?
A. Go to EP/l/A15000/ECA-0.1(Loss ofA// AC Power Recovery
Without S/I Required)
B. Go to EP/I/A15000/E-l (Loss of Reactor or Secondary Coolant)
C. Go to EP/I/A15000/ECA-0.2(Loss of A// AC Power Recovery
With S// Required
D. Go to EP/I/A/5000/ES-1.2 (Post LOCA Cooldown and
Depressurization)
1 Pt Given the following conditions on Unit 1:
Large break LOCA occurred.
Both trains of NV, NI, ND, NS are running
LOOD A LOOP0 LOOPC LOOPD
S/G (NR) [%I 10 9 10 9
The operators are in E-0 (Reactor Trip or Safefy Injection) step 17. The RO
tells the SRO NC temperature is decreasing. The RO is instructed to
implement Enclosure 3 Uncontrolled NC System Cooldown.
Which one of the fol!owing statements ccrrectly doscribes the method for
controlling feed flow?
REFERENCES PROVIDED
A. When NIR level is greater than 11%in one SIG throttle feed
flow to minimum and maintain NIR level greater than 11%in at
least one SIG.
B. When NIR level is greater than 32% in all SIGs throttle feed
flow to minimum and maintain NIR level greater than 32% in all
SIGs.
C. If NlR level is less than 11%in all SIGs throttle feed flow to
minimize cooldown and maintain total feedwater flow greater
than 450 gpm.
D. If NIR level is less than 32% in all SIGs throttle feed flow to
.
minimize cooldown and maintain total feedwater flow greater
than 450 gpm.
Ques-lO59.doc
1 Pt Given the following conditions on Unit 1:
RTP 100%
A CM system transient has caused both FWPTs to trip.
The turbine and reactor failed to trip automatically.
The Operator at the Controls, per the immediate actions of FR-S.l
(Response to Nuclear Power GeneratiodATWS), will
1. Manually trip the Reactor if it fails to trip, insert control rods.
2. Manually trip the Turbine if it fails to trip, runback the turbine
in fast action.
Which one (1) of the following describes the bases for the immediate
actions in FR-S.l (Response to Nuclear Pcwer Generaticn/ATWS)
A. The safeguards systems are designed assuming that the only
heat being added to the NC system is decay heat and NC pump
heat. If the reactor will not trip, then the rods are manually
inserted to lower reactor power. For an ATWS event with a
loss of normal feedwater, a Turbine trip within 30 seconds will
prevent challenging the PZR PORVs.
6. The safeguards systems are designed assuming that the only
heat being added to the NC system is decay heat and NC pump
heat. If the reactor will not trip, then the rods are manually
insertsd to lower reactor power. For an ATWS event with a
loss of normal feedwater, a Turbine trip within 30 seconds will
maintain SIG inventory.
C. The safeguards systems are designed assuming that the only
heat being added to the NC system is from less than 5%
power. If the reactor will not trip, then the rods are manually
inserted to lower reactor power to less than 5%. For an ATWS
event with a loss of normal feedwater, a Turbine trip within 30
seconds will maintain SIG inventory.
D. The safeguards systems are designed assuming that the only
heat being added to the NC system is from less than 5%
power. If the reactor will not trip, then the rods are manually
inserted to lower reactor power to less than 5%. For an ATWS
event with a loss of normal feedwater, a Turbine trip within 30
seconds will prevent challenging the PZR PORVs
1 Pt One of the functions of the Containment Spray System (NS)is to remove
fission product iodine from the containment atmosphere during a design
basis LOCA.
Which one (1) of the following describes how and when this is
accomplished?
k During the Injection phase by providing a spray of cold and
subcooled borated water from the FWST into the upper
containment volume.
B. During the Injection phase by providing a spray of water with
an alkaline pH from the containment sump into the upper
containment volume.
C. During the Recirculation phase by providing a spray of cold
and subcooled borated water from the FWST into the upper
containment volume.
D. During the Recirculation phase by providing a spray of water
with an alkaline pH from the containment sump into the upper
containment volume.
Ques-lO62.doc
1 Pt Given the following conditions on Unit 1:
RTPis 100%
B train is in operation
CF&E sump HI level alarm is lit.
All NC Pump Motor Bearing LO KC flow annunciators are lit.
All NC Pump upper Motor Bearing temperatures are trending up.
6NC Pump Upper Motor Bearing temperature is 197 degrees.
AP-21(Loss ofKC or KC System Leakage) has been implemented.
Which one (1) of the following describes the operators response to B
NCP Umer Motor Bearing HI temperature?
zefereyl Q 60vi de
A. Close INC-29 (B Loop PZR Spray Control), trip the reactor,
stop B NC Pump and go to EP/l/A/5000/E-0
B. Trip the reactor, stop B NC Pump and go to EP/l/A/5000/E-O
C. Trip the reactor, trip all NC Pumps and go to EP/l/A/5000/E-0
D. Close INC-29, trip the reactor, trip all NC Pumps and go to
EP/l/A/5000/E-O
1 Pt Given the following conditions on Unit 1:
Medium size LOCA has occurred with valid Ss, St and Sp signals
SA termination criteria are satisfied
One NV pump has been secured
Both NI pumps have been secured
Both ND pumps have been secured
Pzr Spray valves are closed
Pressurizer level is 25% and decreasing. Which one of the following
describes the correct operator actions?
REFERENCE PRCV/DED:
A. Restart S/I pumps and realign NV S/I flowpath as necessaryto
restore subcooling and level, GO TO EP/l~5000/E-I(Loss of
Reactor or Secondary Coolant).
B. Go to EP/I/A/5000/ES 1.2 (Post LOCA Cooldown and
Depressurlzalion).
C. Go directly to EP/l/A/5000/ES-0.0(Rediagnosis)
D. Reinitiate Safety Injection and GO TO EP/l/A/5000/E-0 (Reactor
Trip or Safety Injection).
_____________-_-----_____._____
Ques-1064.doc
1 Pt. The SRO instructs the Unit 1 RO to adjust NC Pump seal leak off flow by
cooling the VCT. The potentiometer on 1KC-I32 (Letdown Heat
xcbanger Outlet Temperature Control) was adjusted to lower VCT
temperature 6 degrees.
Which one of the follow is the correct plant response to this adjustment?
A. VCT temperature decreases
KC pump flow decreases
KC pump discharge pressure increases
NC temperature increase
Main Steam prsssure increases.
0. VCT temperature decreases
KC Pump flow increases
KC Pump discharge pressure decreases
NC temperature decrease
Main Steam pressure decreases
C. VCT temperature decreases
KC Pump flow increases
KC Pump discharge pressure decreases
NC temperature increase
Main Steam pressure increases
D. VCT temperature decreases
KC Pump flow decreases
KC Pump discharge pressure increases
NC temperature decreases
Main Steam pressure decreases
1 Pt. Given the following conditions on Unit 1:
ORANGE Path on Core Cooling
RED Path on Heat Sink
Which one of the following describes why Red path on Heat Sink is
addressed prior to the Orange Path on Core Cooling?
A A Red path indicates the CSF is under challenge and
prompt operator action is required.
B. A Red path indicates the CSF is not satisfied and operator
action may be taken.
C. Heat Sink has a hiaher priority than Core Cooling due to
position on status trees.
D. A Red path indicates the CSF is under extreme challenge and
immediate operator action is required.
1 Pt. Unit 1 is in the process of cooling down to Mode 5 to enter refueling
outage.
Steam dumps in Steam Pressure Mode with Steam Dump
Controller in Manual
15 minutes after cooldown has begun from 557 degrees steam
dumps close.
Which one of the following describes the correct reason the steam dumps
closed?
A. Potentiometer set too high on Steam Dump Controller.
B. Cooled down to P-12.
C. C-7A not reset.
D. Tave and Tref deviation is less than 3 degrees.
1 Pt. Given the following conditions on Unit 1:
RN system is in normal alignment
RN pump 8 is running
RV pumps are in normal alignment
Unit 1 experiences a Safety Injection
Which one of the following describes the cooling water supply provided to
lower containment ventilation loads?
A. A RN pump
B. B RN pump
C. RV pump in AUTO that starts on low non-essential header
pressure.
D. RV pump in AUTO that starts on safety injection signal.
Ques-1070.doc
1 Pt(s) Unit 1 is in the process of releasing the Ventilation Unit Condensate Drain
Tank (WCDT) using approved station procedures. Just after the release was
initiated, the 1EMF-44 (Ventilation Unit Condensate Drain Tank) power
supply fails.
Which one of the following statements correctly describes the effect on this
Liquid Waste Release (LWR)?
REFERENCE PROVIDED
A. 1EMF-44 fails in the conservative direction and both Trip 1 and
Trip 2 alarm, terminating the release. The high radiation
alarms can not be reset and the release can not be continued.
B. 1RAD2-F/2, EMF44 LOSS OF CONT VENT DRN TNK
SAMPLE FLOW alarms and the release must be terminated.
C. lEMF-44 will alarm Trip 1 and Trip 2 terminating the release.
The Trip 2 alarm may be reset only one time, if no further
alarms are received. The LWR may proceed provided that
station RP performs an analysis of grab samples for
radioactivity at a lower limit of detection.
D. Nothing, there is no effect on this LWR. The LWR may proceed
provided that station RP performs an analysis of grab samples
for radioactivity at a tower limit of detection.
Ques-1074.doc