ML032370026
| ML032370026 | |
| 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 | |
| Download: ML032370026 (172) | |
See also: IR 05000369/2003301
Text
Fin a IS u bm i tta I
MCGUIRE JUNE 2003 EXAM
50-36912003-301 AND
50-370/2003-301
JUNE 16 - 30,2003
1.
Combined RO/SRO Written Exam with KAs,
Answers, References, and Analysis
Bank Question: 048.1
Answer: D
1 Pt.
Which one of the following selections correctly matches the reactor trip
signals to their limiting accident?
Reactor Trip Siqnal
Limiting AccidentlProtection
A.
B.
C.
D.
OPAT
OTAT
Excessive fuel centerline temperature
Pzr High Level
Pzr Low Pressure
OPAT
Excessive fuel centerline temperature
OTAT
Pzr High Level
Pzr Low Pressure
OPAT
OTAT
Excessive fuel centerline temperature
Pzr High Level
Pzr Low Pressure
NC system integrity
NC system integrity
NC system integrity
OPAT
Excessive fuel centerline temperature
OTAT
Pzr High Level
Pzr Low Pressure
NC system integrity
Distracter Analysis:
A.
B.
Incorrect: All are incorrect.
C.
D.
Correct:
Incorrect: OPAT and OTAT are reversed.
Plausible: PZR low pressure and high level are correct.
Plausible: Provided for psychometric balance.
Incorrect: OPAT and OTAT are reversed.
Plausible: PZR low pressure and high level are correct.
Level: RO
KA: SYS 012 K5.01(3.3/3.8)
Lesson Plan Objective: OP-MC-IC-IPE Obj. 2
Source: Bank
Level of knowledge: Memory
References:
1. OP-MC-IC-IPE pages 19,45 & 81
Ques-048.l.doc
Bank Question: 50.1
Answer: D
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 6
and stop NS pumps within 45
seconds and manually swap the pump alignment to take suction on
the containment sump.
Reset Containment Spray and the NS pumps will automatically swap
over to take a suction on the containment sump when FWST level
reaches 33.
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.
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.
6.
C.
D.
MISCINFO:
SOURCE:
BANK
LEVEL OF KNOWLDEGE: Memory
REFERENCES:
OP-MC-ECC-NS 3.2 page 31
EP1lN5000lFR-2.1 4,d,2 page 5
EP/1/N5OQO/ES-1.3
LESSON:
OP-MC-ECC-NS
OBJECTIVE: 6 , 8
WA:
026000 K401 (3.113.6)
G 2.4.50 (3.3/3.3)
50.1 doc
Bank Question: 51.1
Answer: C
A large break LOCA is in progress and the operators are responding in
FR-Z.l (Response to Higb Containment Pressure). Given the following
conditions:
1 Pt.
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 pumps
to be in operation. ECA-1 .I
limits the operators to only one NS Dum@ in
step 6. Which of these two procedures takes priority under these
conditions and what is the basis for this requirement?
A.
FR-Z.l takes priority because a total loss of ND causes the NS
system to become relatively more important to reduce
containment pressure.
FR-Z.l takes priority because it was implemented in response
to a red path and FRPs always have priority over ECA
procedures.
ECA-1 .I
takes priority because it conserves FWST water level
as long as possible for injection while providing sufficient NS
flow to mitigate containment pressure.
ECA-1.1 takes priority because ECA procedures always have
priority over FRPs.
B.
C.
D.
________________..____.______
Distracter Analysis:
A.
Incorrect: ECA-1 .I
takes priority over FR-Z.l
Plausible: Although a loss of ND and containment sump recirc
causes a loss of the containment heat sink, the supply for N S
comes from the FWST which will be drawn down until containment
sump recirculation can be established.
Incorrect: ECA-1.1 takes priority over FR-Z.l
Plausible: FRPs normally take priority over most EOPs
Incorrect: ECAs do not always have priority over FRPs.
Plausible: Some ECAs take priority e.g. ECA-0.0 has priority over
FRPs in that F-0 is not applicable until transition out of ECA-0.0.
B.
C.
Correct answer
D.
Ques-05l.l.doc
Bank Question: 60.1
Answer: A
Unit 2 was operating at 100% power when an electrical fire started inside
the auxiliary building cable spreading room. AP/O/A/5500/45 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.
1 Pt.
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.
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.
An NLO is dispatched to verify automatic Halon system
actuation. An asphyxiation hazard exists due to the presence
of Halon gas.
An NLO is dispatched to actuate a manual Cardox system. An
asphyxiation hazard exists due to the presence of carbon
dioxide gas.
B.
C.
D.
Distracter Analysis:
A.
Correct Answer:
B.
Incorrect A manual deluge Mulsifyre system is installed
Plausible: an electrical shock hazard exists
C.
Incorrect: A manual deluge Mulsifyre system is installed
Plausible: Halon gas is generally used in areas in which electrical
fires are the predominant risk because it does not create a shock
hazard
Incorrect: A manual deluge Mulsifyre system is installed
Plausible: Cardox gas is a personnel hazard - although all the
CARDOX systems have been replaced with HALON, the pull
switches still say CARDOX in some areas (like the diesel
generators)
D.
LEVEL: RO
LEVEL OF KNOWLEDGE: Memory
SOURCE: BANK
KA: 000067 AK3.02 (2.U3.3)
Ques-060.2.doc
Lesson Plan: OP-MC-SS-RFY
OBJECTIVE: OP-MC-SS-RFY Obj. 11
REFERENCE: OP-MC-SS-RFY pages 37,49,51,53
Ques-060.2.doc
Bank Question: 63.1
Answer: D
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
Parameter
TA
Ti3
TD
Frequency (Hz)
55
60
55
60
Voltage (Volts AC)
6800 6900 6800 6900
Offsite bus-line 1A is supplying TA and TC
Offsite bus-line 1B is supplying Ti3 and TD
Which one of the following describes the immediate plant response to this
A.
B.
C.
D.
No NCP pumps trip and the reactor does NOT trip
The 1' A 'and 1 'C' NCPs trip and the reactor trips
All four NCPs trip but the reactor does NOT trip
All four NCPs trip and the reactor trips
Level: RO
SOURCE:
BANK
Level of Knowledge: Analysis
REFERENCES:
OP-MC-PS-NCP pages 29 & 31
OP-MC-IC-IPE pages 47 & 81
OP-MC-EL-EP pages 41 & 43
LESSON:
OP-MC-PS-NCP
OP-MC-IC-IPE
OP-MC-EL-EP
OBJECTIVE: OP-MC-PS-NCP Obj. 15
OP-MC-IC-IPE Obj. 10
OP-MC-EL-EP Objs. 23 & 24
W A EPE 007 EA1.04 (4.2/4.1)
Ques-63.l.doc
Bank Question: 107.1
Answer: C
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 Generation/ATWS).
Given the following malfunctions:
1)
2)
Which one of the following describes the operator's response in FR-S.l to respond
to failure of the turbine to trip?
The reactor is manually tripped
The turbine fails to trip automatically and manually.
A.
B.
,.
CI.
D.
MISCINFO:
SOURCE:
REFERENCES:
Place turbine in EMERGENCY MANUAL and close governor valves in
fast action and close all MSlVs
Place turbine in MANUAL and close governor valves in fast action and
close all MSlVs
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
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
BANK - Modified
EP/1/N5000/FR-S.1 page 2
OP-MC-EP-FRS page 25
OBJECTIVE: 1) OP-MC-EO-FRS.Obj 4
KIA
00012 K3.02 (3.2*/3.3)
LEVEL OF KNOWLEDGE:: COMPRHENSION
107.1 doc
1
Bank Question: 131.1
Answer: D
1 Pt
Given the following plant conditions:
Reactor Missile Shield removed.
IEMF-38 trip 2 alarm.
Which one of the following selections describes the COMPLETE
system response by the Containment Purge System?
A. Supply Fan (16) will STOP.
Supply Damper will CLOSE.
Exhaust Fan (16) 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.
Unit 1 in Mode 6.
"Norm-Refuel" Selector Switch in the REFUEL position.
Fan Mode Selector Switch in the 100% position.
6. Supply Fans (IA & 16) will STOP.
Exhaust Fan (1A& IB) will STOP.
Upper Containment Inside Isolation Valves will CLOSE.
Upper Containment Outside Isolation Valves will CLOSE.
C. Supply Fan (IB) will STOP.
Exhaust Fan (16) will STOP.
Lower Containment Inside Isolation Valves will CLOSE.
Lower Containment Outside Isolation Valves will CLOSE.
D. Supply Fans (In& 16) will STOP.
Supply Damper will CLOSE.
Exhaust Fan (IA & 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.
_______________.___________
Distracter Analysis:
A.
Incorrect:
Plausible:
B.
Incorrect:
Plausible:
C.
Incorrect:
Ques-13l.l.doc
Plausible:
D.
Correct answer
Plausible:
Level: RO
Source: BANK
Level of Knowledge: Memory
Lesson: OP-MC-CNT-VP
Objective: OP-MC-CNT VP Obj. 3
KA: 029 K4.03 (3.2/3.5)
Bank Qoesfion: l62.1
Answer: C
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.
EMF-38(H) trip-I will secure VP and VQ,
and shutoff
containment sump pumps and incore sump pumps.
EMF-39(L) trip-1 will sound the containment evacuation alarm,
and secures VP and VQ.
EMF40 trip-2 will secure VP and VQ, and shutoff containment
sump pumps and incore sump pumps.
EMF41 trip-2 will secure VP and VQ, and shutoff containment
sump pumps and incore sump pumps.
B.
C.
D.
LEVEL:
SOURCE:
BANK
REFERENCES:
OP-MC-WE-EMF page 25
LESSON:
OP-MC-WE-EMF
OBJECTIVE: OP-MC-WE-EMF Obj. 3
KA: SYS 103 A301 (3.914.2)
Bank Question: 164.2
Answer: C
1 Pt
Unit 1 was 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 Isolation). The following sequence of events occurred:
What are the correct panel actions for the restoration of power to pressurizer
back-up heater bank D?
A.
Isolation of the I D S/G
PZR level dropped to 0% and was restored to 20%
NCS pressure is 1900 psig
Safety Injection has not been reset
Reset safety injection on 1 MC-6.
Ensure AUTO is selected on the heater mode switch on 1 MC-
10
Select CLOSED on the heater breaker switch on IMC-5
(vertical board)
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
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
Reset safety injection on IMC-6
Select MANUAL on the heater mode switch on IMC-5
Select CLOSED on the heater breaker switch on 1 MC-10
Select ON for the heater control switch on 1 MC-5
B.
C.
D.
_________.______.___--..------.--
Distracter Analysis: The B N heater breakers will not close unless the
mode selector switch is in MANUAL.
Incorrect: insufficient action, SI reset is unnecessary, and mode
switch to MANUAL.
Plausible: if the candidate is not familiar with the interlocks on the
PZR heater circuit, the locations are correct.
Incorrect: must turn the heater mode switch to MANUAL, and the
locations are incorrect.
Plausible: if the candidate reverses the panel locations and knows
that SI reset is unnecessary, it would appear that this is the best
answer.
Correct answer: Bank D does not require SI reset
Incorrect: Not necessary to reset safety injection and wrong
locations for SI reset and heater controls.
A.
B.
C.
D.
Ques-164.2.doc
Plausible: If the candidate does not know the panel locations, this
is the right method for Banks A&B (and would work for D) and was
correct in the prior version of the question.
Level: RO
KA: SYS 010 G2.1.31 (4.2/3.9)
Lesson Plan Objective: OP-MC-PS-ILE Obj. 11
Source: BANK
Level of knowledge: comprehension
References:
1, OP-MC-PS-IPE page 19
Ques-164.2.doc
Bank Question: 47. I
Answer: B
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)
2)
3)
Step 18 of ES 0.2 requires that the operators maintain subcooling greater than 50
degrees if all 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.
B.
C.
D.
NC pumps cannot be restarted.
Power has been restored to all station AC busses
A natural circulation cooldown is in progress.
To prevent degradation of reactor coolant pump seals due to steam.
To prevent possible void formation in the upper head.
To collapse any voids formed in the CRD housings.
To ensure adequate subcooling due to possible degradation of core
exit TlCs accuracy.
LEVEL:
SOURCE:
BANK
LEVEL OF KNOWLEDGE: Comprehension
REFERENCES:
EP/l/N5000/ES0.2 step 18
OP-MC-EP-EO 6.4.18 page 147
LESSON:
OP-MC-EP-EO
OBJECTIVE: OP-MC-EP-EO Obj. 6
KIA:
W/E09 EK2.1 (3.2/3.4)
Ques-47.1
Bank Question: 191.3
Answer: B
1 Pt
Unit 1 was operating at 100% power when a total loss of feedwater
occurred. The operators reached Step 7 of FR-H.1 (Response to Loss of
Secondary Heaf Sink), which attempts to establish CA flow to at least one
S/G. Sub-step 7.k states:
Maintain feed flow rate less than or equal to I00
GPM until S/G WR level is greater than 12% (17%
ACC).
Given the following conditions:
LOOP A
LOOP B
LOOP D
SIG(WR)~%I
o
15
9
10
I . .
NCTnot [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?
A.
Restore flow to the A
SIG 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 6
and
C S/Gs because they will be reserved for use later to provide
a steam supply for the TD CA pump.
Restore flow to the B SIG because B SIG level is the highest
and this will reduce the chance of thermal shocking the S/G.
Flow should be preferentially restored to the B or C S/G to
maintain the TD CA pump steam supply.
Restore flow to the IC S/G because loop C T-hot is less than
loop B T-hot 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.
Restore flow to the D
SIG because the DSIG is higher than
A S/G 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.
B.
C.
D.
__________________-.---.------.---
Distracter Analysis: The guidance is to select the S/G that has the
highest apparent level and to preferentially select the B or C SIG.
A.
Incorrect: T-hot should not be used to determine which S/G
should receive flow. It is not a reliable means of determining S/G
shell temp in a dry stagnant loop.
Plausible: The apparent temp of the A loop is the lowest and it
may appear that the chance of thermal shock is lessened.
Correct answer: feed the S/G that has the highest level and
preferentially feed B & C S/Gs to maintain steam supply to the TD
CA pump.
Incorrect: C S/G has a lower S/G level than B S/G
Plausible: C S/G has a lower T-hot than B S/G
Incorrect: No basis for reserving the B & C S/Gs for restoring flow
Plausible: There is a high probability that restoring feed to a dry
S/G could rupture the tube sheet due to thermal stress. It makes
sense to select a S/G that is NOT used to supply steam to the TD
CA pump for the initial restoration of the heat sink.
Level: RO
KA: W/EO5 2.4.18 (2.713.6)
Level of Knowledge: Analysis
Lesson Plan Objective: OP-MC-EP-FRH, Obj.4
Source: BANK
References:
1. EP/FR-H.l, Step 7.k (NOTE prior)
B.
C.
D.
Ques-191.3.doc
Bank Question: 195.5
Answer: D
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"
Which one of the following response actions is required?
A.
IR SUR = -0.3 DPM
Implement AP114, (Control Rod Misalignment) and respond to
the stuck rods.
Implement E-0, (Reactor Trip or Safety hjecfion), and
immediately transition to FR-S.2, (Response to Loss of Core
B.
Shufdown).
C.
Implement E-0, (Reactor Trip or Safety Injection) and
immediately transition to FR-S.1, (Response to Nuclear Power
Genera tion/A 7WS).
Implement E-0, (Reactor Trip or Safety Injection), and then
transition to ES-0.1, (Reactor Trip Response).
D.
_________.____.___.__________
Distracter Analysis: The RNO will evaluate the need to transition to FR-S.l
based on indications of reactor criticality. Transition is not appropriate
unless reactor power is > 5% and not decreasing.
Incorrect: If above P-I 1 (1955 psig) must use E-0.
Plausible: This would be the correct answer for a reactor trip below
P-I 1.
Incorrect: There is no yellow path because SUR < -0.2dpm. In
addition, F-0 is not in effect at this point in the procedure
Plausible: This would be the correct response if SUR > -0.2 dpm.
Incorrect: inappropriate to enter FR-S.1 because the reactor is
subcritical and F-0 is not in effect
Plausible: If the candidate makes a literal reading of E-0 without
knowledge of the ERG background positions on what constitutes a
tripped reactor. Some plants enter FR-S.1 for two rods stuck out.
A.
B.
C.
D.
Correct:
Level: RO
KA: W/E 01 EK1.2 (3.4/4.0)
Ques-195.5.doc
Lesson Plan Objective: EP-EO Obj. 10
Source: BANK
Level of knowledge: Memory
References:
1. OP-MC-IC-IRE page 35
2. OP-MC-EP-FRS page 15, 17
3. OP-MC-EP-EO pages 19,27
4. F-0 page 1
5. E-0 page 3
6. AP-14 page 2
Ques-195.5.doc
Bank Question: 228.1
Answer: B
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 Nls with both Gamma Metric SDMs
in operation.
Loss of direct communications between the control room and
the refueling bridge (refueling station).
Loss of the Fuel Handling Ventilation System.
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 />.
B.
C.
D.
LEVEL:
SOURCE:
BANK
LEVEL OF KNOWLEDGE: Memory
REFERENCES:
SLC 16.9.18
OP-MC-FH-FC pages 11,27,33
LESSON:
OP-MC-FH-FC
OBJECTIVE: OP-MC-FH-FC Objs. 1 & 7
KA: G 2.2.27 (2.6/3.5)
Ques - 228.l.doc
Bank Question: 311.2
Answer: A
Unit 1 is operating at 50% power. Given the following conditions:
Pressurizer pressure is 2235 psig
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
0
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?
1 Pt
REFERENCES PROVIDED: Steam Tables
A.
258-262°F
8.
227-231
O F
C.
1 61 -1 65 "F
D.
123 -127°F
Distracter Analysis:
A.
Correct answer
B.
Incorrect: Temp is too low - the correct temp is 260 O F
Plausible: If the candidate makes the mistake of not correcting for
atmospheric pressure by failing to adding 14.6 psi to the PRT
pressure and uses 20 psia.
Incorrect: Temp is too low - the correct temp is 260 "F
Plausible: If the candidate reverses the correction for atmospheric
pressure by subtracting 14.6 psi from PRT pressure of 20 psig to
get 5 psia.
Incorrect: Temp is too low - the correct temp is 260 "F
Plausible: If the candidate thinks that the discharge temperature
will be at the same temperature as the PRT fluid.
Level: RO
tW SYS 010 K5.02 (2.6/3.0*)
Source: BANK
Level of Knowledge: Analysis
Objective: OP-MC-THF-EB Obj. 8
C.
D.
Ques-311.2.doc
Reference: OP-MC-THF-EB pages 23-26
Ques-3ll.Z.doc
c
Bank Question: 321.1
Answer: A
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.
Maintain pressurizer saturation temperature corresponding to
intact SIG pressure to minimize primary leakage into the SIG.
Maintain pressurizer saturation temperature above the
corresponding ruptured SIG pressure to ensure S/G water
does not flow into the NC system.
Maintain pressurizer saturation temperature corresponding to
intact SIG pressure to minimize NC pressure transients.
6.
C.
D.
Distracter Analysis: The purpose of this question is to determine if the
candidate understands that thermal hydraulic equilibrium
(templpresslleak rate) needs to be established between the NCS
and the ruptured S/G. No references are provided because the
candidate should be able to answer the question by simply
comprehending the pressures and reasons for this equilibrium.
A.
Correct Answer:
B.
Incorrect: required to maintain NCS pressure equal to ruptured
SIG pressure, not the intact SIG - Intact S/G pressure c ruptured
SIG pressure would not reduce NCS to SIG leakage
Plausible: if the candidate is confused over the thermal hydraulics
Incorrect required to maintain NCS pressure equal to ruptured
S/G pressure
Plausible: partially correct - do not want leakage from SIG to NCS
or NCS to SIG
Incorrect: required to maintain NCS pressure equal to ruptured
S/G pressure, not the intact S/G
Plausible: this would be a reasonable basis for monitoring intact
S/G pressure if that were the correct answer.
Level: RO
KA: EPE 038 EK1.02(3.2/3.5)
C.
D.
Ques-32l.l.doc
Lesson Plan Objective: OP-MC-EP-EP3 Obj 4
Source: Bank
Level of knowledge: comprehension
References:
1,OP-MC-EP-EP3 pages 19,101,119
2. EP/I/A/5000lE-3 pages 56,57
Ques-321. Ldoc
Bank Question: 330. I
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?
A.
Answer: B
1 Pt
This restriction assures that the NCP oil temperature will
decrease to design specifications between restart attempts.
This restriction prevents overheating the motor windings due
to high starting currents.
This restriction allows the NCP seals to fully reseat between
NCP oil lift pump cycles.
This restriction ensures adequate Number 1 Seal Leakoff flow.
B.
C.
D.
Distracter Analysis:
A.
Incorrect: The reason is stator-winding temperatures
Plausible: if the candidate remembers this as a high temperature
concern - another adverse consequence of multiple starts on
motors
Incorrect: The reason is stator-winding temperatures
Plausible: NCP seal seating is the basis for a different cold start
precaution - seal leakoff limit after seal replacement
Incorrect: The reason is stator-winding temperatures
Plausible: if the candidate is confused regarding the basis for the
precaution.
B.
Correct Answer:
C.
D.
Level: RO
Source: BANK
Level of Knowledge: Memory
KA: G2.1.32 (3.4/3.8)
References:
1. OP-MC-PS-NCP page 35
Ques-330.l.doc
Bank Question: 359.3
Answer: D
Unit 1 is responding to a small break LOCA using E-I (Loss of Reactor or
Secondary Coolant). Given the following events and conditions:
1 Pt
FWST Level = 340 inches
Containment pressure = 1.5 psig
Containment Sump Level = 1.05 ft
EMF41 (AUXBLDG VENTILATION) = trip 2
Aux Building area radiation monitors are in alarm
EMF-51A and B (CONTAINMENT TRNA & B) = 25 WHr
Hydrogen Analyzer = 0.7% in containment
NLOs report significant leakage at the seals of the 1A ND pump
Which one of the following procedures should the operator transition into
from E-I?
A.
B.
C.
D.
ECA-1.2 (LOCA Outside Containment)
FR-2.3 (Response to High Containment Radiation Level)
ECA-1 .I (Loss of Emergency Coolant Recirculation)
FR-2.4 (Response fo High Containment Hydrogen)
Distracter Analysis: The initial conditions provide a LOCA into
containment and a leakage path outside of containment. The question is
which of the problems take priority? The purpose is not to memorize
procedure steps but to answer this from a broader perspective.
A.
Incorrect: Cont RAD levels < 35 Whr and this would be a YELLOW
path that does NOT require priority action.
Plausible: If the candidate thinks that the abnormal radiation level
requires priority action.
Incorrect: Still in injection phase of SI - have failed to isolate leak
outside containment.
Plausible: if candidate is not familiar with the entry conditions for
ECA 1.1 (after failure to isolate leak outside containment).
Incorrect: Cont H2 > 0.5 %, but this is a YELLOW path not
requiring priority action.
Plausible: If the candidate fails to recognize the leak in the auxiliary
bldg and/or the fact that E-I takes care of the cont H2 problem.
B.
C.
D.
Correct:
Level: RO
KA: WE 04EK3.2 (3.4 /4.0)
Ques-359.3.doc
Lesson Plan Objective: OP-MC-EP-E1 Obi 2
Source: BANK
Level of knowledge: comprehension
References:
1,OP-MC-EP-E1 page 45
2. EP/l/A/5000/E-1 pages 12-14
3. EP/I/A/5000/F-O page 9
Ques-359.3.doc
Bank Question: 373.1
Answer: D
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
No operator action taken
Which one of the following sequences best describes the actuation of the
steam dumps to this event?
The steam dump select switch was in steam pressure mode
Condenser vacuum dropped to 18 inches
No component or instrument failures occurred
Condenser dump valves
Atmospheric dump valves
A.
open
open
0.
open
shut
C.
shut
open
D.
shut
shut
A.
6.
C.
D.
Distracter Analysis:
Incorrect: -the condenser dumtx will not oDen due to the C9
arming signal not present caused by a low vacuum condition (20 in)
The atmospheric dumps will not open because they do not actuate
when the steam dump selector switch is in steam pressure mode
Plausible: - this would occur if the transition had not yet been
made to steam pressure mode and C9 had actuated - a normal
plant response during a startup < 10% power.
Incorrect: - the condenser dumps will not open due to the C9
arming signal not present caused by a low vacuum condition
Plausible: -this sequence would occur if there was not a loss of
condenser vacuum or if the candidate does not recognize the
interaction between condenser pressure and the C9 arming signal.
Incorrect: - the atmospheric dumps will not open because they do
not actuate when the steam dump selector switch is in steam
pressure mode
Plausible: - this sequence would occur if the plant was in Tave
mode above -55% -the transition from Tave to steam pressure
mode occurs by procedure at 10% power
Correct answer
Level: RO
KA: APE 051 AK.3.01 (2.8*/3.1*)
Ques-373. Ldoc
Lesson Plan Objective: STM-IDE LPSO 5, 6, 9
Source: Bank
Level of Knowledge: comprehension
References:
1 .OP-MC-STM-IDE pages 17-35 (odd only)
Ques-373. Ldoc
Bank Quesfion: 407.1
Answer: D
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 using the norma[ path. Two RC pumps are the
minimum required under the LWR document.
Given the following initial conditions:
0
If the release automatically terminates 40 seconds after initiation, which
one of the following conditions could have terminated the release?
A.
1 Pt
3 RC pumps are running
1 EMF-44 (COW VENTDRN TANK OUT) correctly set for trip 1 and
trip 2 activity limits
No other releases are in progress
1WM-46 (LIQUID WASTE DISCH VALVE) closing automatically
if 2 RC pumps trip
1WM-46 closing automatically if 1EMF-44 reached the trip 2
setpoint
IWP-35 (WMT & VUCDT TO RC CNTRL) closing automatically
if 1 RC pump tripped
IWP-35 closing automatically if 1EMF-44 reached the trip 2
setpoint
B.
C.
D.
Distracter Analysis:
A.
Incorrect: - RC pump interlock will not actuate - set at 2 pumps
(minimum required on LWR document). WM-46 is isolated and not
used anymore as a release path.
Plausible: - this was formerly the normal release path
Incorrect: - WM-46 receives a closing signal from EMF-44 but this
is not the normal path for a release. WM-46 is isolated and not
used anymore.
Plausible: - this was formerly the normal release path
Incorrect: - RC pump interlock will not actuate - set at 2 pumps
(minimum required on LWR document).
Plausible: - if the candidate misunderstands the RC pump
interlock--this was the correct answer on a prior NRC exam -
B.
C.
D.
Correct answer
Level: RO
Ques-407.l.doc
KA: G 2.3.1 1 (2.7/3.2)
Lesson Plan Objective: OP-MC-WE-WL Obj. 3
Source: Bank
Level of knowledge: Comprehension
References:
1, OP-MC-WE-WL pages 21,23,27,59
2. OP-MC-WE-EMF page 31
3. OP-MC-WE-RLR page 11 and 13
Ques-407.l.doc
Bank Question: 432.3
Answer: A
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 NORMAL-REFUEL SELECTOR switch is placed in the
"NORM' position and ratio of supply air is 211 (UppedLower
Containment).
The NORMAL-REFUEL SELECTOR switch is placed in the
"NORM' position and ratio of supply air is 4/1 (UppedLower
Containment).
The NORMALAEFUEL SELECTOR switch is placed in the
"REFUEL" position and ratio of supply air is 2/1 (Upper/Lower
Containment).
The NORMAL-REFUEL SELECTOR switch is placed in the
"REFUEL" position and ratio of supply air is 4/1 (UppedLower
Containment).
B.
C.
D.
Distracter Analysis:
A.
B.
C.
D.
Correct: - this is the proper position for this operation.
Incorrect: Air ratio is 2/1 not 411
Plausible: -
Incorrect : -this will over-pressurize the upper containment
Incorrect: - this will over-pressurize the upper containment.
Plausible: .
Level: RO
KA: G 2.3.9 (2.5/3.4)
Lesson Plan Objective: CNT-VP Obj. 2
Source: BANK
Level of knowledge: Comprehension
Ques-432.3.doc
References:
1. OP-MC-CNT-VP pages 19,21,23
Ques-432.3.doc
Bank Question: 451.1
Answer: B
1 Pt
Unit 1 is shutdown in a refueling outage. Given the following events and
conditions:
What effect does a total loss of the VI system have on the VS system?
A.
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.
VI-820 will auto-close as VI header pressure decreases below
82 psig and the VS air compressor will start automatically to
maintain VS header pressure.
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.
Check valves in the VI - VS cross-connect line will close to
isolate VS system pressure before it drops below 90 psig.
VS pressure in the Fire Protection Pressurizer Tank will be lost
until a VS air compressor can be started.
B.
C.
D.
___________________.----------
Distracter Analysis:
A.
B.
C.
D.
Incorrect: -the VS air compressor does not automatically start to
maintain pressure
Plausible: -The VI system is safety significant, VI-820 used to
close 82 psig but the setpoint was recently changed from 82 psig to
90 psig. There is a separate VS air compressor, which has an
automatic startup feature -but is normally in off and requires
operator action to start.
Correct answer
Incorrect: - there are no check valves in this line
Plausible: -this is another possible method to prevent
depressurizing the VS header at some plants.
Incorrect: -the RF system tank is pressurized with VS air - but is
maintained isolated from the VI header
Plausible: - if the candidate does not know that the RF system air
tank is isolated from the VS header.
Level: RO
KA: SYS 078 K4.01 (2.7/2.9)
Lesson Plan Objective: SS-MC-SS-VI Obj. 7
Ques-451.l.doc
Source: Bank
Level of Knowledge: comprehension
References:
1. OP-MC-SS-VI page 1 15
Ques-45l.l.doc
Bank Question: 531.1
Answer: C
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-420 closes 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.
2CM-420 closes to prevent diversion of water from the "C"
heater drain tank back to the UST thereby ensuring sufficient
CF pump suction pressure.
2CM-420 opens to divert condensate flow directly to the
condensate booster pump suction to ensure that CF pumps
have sufficient suction pressure.
2CM-420 opens to divert condensate flow, bypassing around
the condensate booster pumps, directly to the CF pumps to
assure minimum flow requirements.
6.
C.
D.
Distracter Analysis:
A.
Incorrect: CM-420 opens - does not close. Does not prevent
water from being recirculated around the hotwell pumps.
Plausible: this function is performed by CM-407 - which opens to
assure minimum flow around the hotwell pumps to prevent water
hammer on the CM system during startup.
Incorrect: CM-420 opens - does not close. Does not prevent a
loss of water to the condensate booster pump suction.
Plausible: CM-227 opens to recirc condensate from the C
feedwater heater to the USTs to assure minimum recirc flow on the
Incorrect: CM-420 does not provide a flow path around the
condensate booster pumps directly to the CF pumps to meet
minimum flow requirements
Plausible: CM-420 opens to provide bypass flow - but directly to
B.
C.
Correct answer
D.
Level: RO
Level of Knowledge: Memory
Source: BANK
Ques-531.1 .doc
K&A: 056 A2.04 (2.6/2.8*)
Lesson Plan: OP-MC-CF-CM Obj. 11
References: OP-MC-CF-CM page 33 & 67
Ques-531.l.doc
Bank Question: 547.2
Answer: C
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:
Which one of the following statements correctly describes the cause of this
problem?
A.
B.
C.
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
Loss of YM supply to the condenser boot seals
Loss of Main Steam to the CSAEs
CM flow to all CSAE inter-coolers has been obstructed
D.
A CSAE drain was left open
Distracter Analysis:
A.
Incorrect: A recent change no longer runs seals water to the
condenser boot seals.
Plausible: Seal water to the boot seals was originally designed to
prevent condenser leakage
Incorrect: Main steam does not supply the CSAEs
Plausible: There are physical connections for main steam to be
the back up supply for aux steam - but these connections are not
used.
Correct answer - reduces effectiveness of steam jets and causes
vacuum to decrease.
Incorrect: CSAE drains are normally open to allow condensate to
drain out of the air ejectors.
Plausible: If the drain is lefl closed, the condensate will build up
and flood out the CSAE, which could cause a loss of vacuum. This
is the reverse of the distracter.
Level: RO
KA: SYS 055K3.01 (2.5 / 2.7)
Lesson Plan Objective: MT-ZM SEQ 4,5,9
Source: Bank
Level of knowledge: comprehension
B.
C.
D.
Ques-547.2.doc
References:
1. OP-MC-MT-ZM pages 11, 13, 15,23,27
Ques-547.2.doc
Bank Question: 548.1
Answer: A
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.
A complete load shed will occur. The accelerated sequence
will sequence LOCA loads on after checking for adequate bus
voltage and DG speed.
A complete load shed will occur. The accelerated sequence
will sequence LOCA loads on after checking for adequate bus
voltage.
Only non-LOCA loads will be shed. The accelerated sequence
will sequence remaining loads on after checking for adequate
bus voltage and DG speed.
B.
C.
D.
__________-____--___--.---.-----
Distracter Analysis:
A.
Correct answer
B.
Incorrect: only non-LOCA loads are shed, the accelerated
sequence does not check for DG speed during a LOCA
Plausible: DG speed is checked when the sequencer is actuated
during a blackout signal
Incorrect: only non-LOCA loads are shed
Plausible: the remaining part of the answer is correct
Incorrect: the accelerated sequence does not check for DG speed
during a LOCA
Plausible: DG speed is checked when the sequencer is actuated
during a blackout signal
C.
D.
Level: RO
KA: SYS 013 K4.11(3.2/3.8)
Lesson Plan Objective: DG-EQB Obj 6
Source: Bank;
Level of knowledge: Memory
References:
Ques-548. Ldoc
1. OP-MC-DG-EQB page 25
Ques-548.l.doc
Bank Question: 593.1
Answer: 8
1 Pt
Unit 2 was operating at 99% power when a steamline break occurred.
Given the following events and conditions:
0200 The operators enter APlOl (Steam Leak)
0200 The operators start reducing turbine load to match Tave and T,ef
0201 ' The operators start a second NV pump and isolate letdown
0202 NLOs start investigating for 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.
B.
C.
D.
Manually trip the reactor at 0203
Manually trip the reactor at 0204
Manually trip the reactor at 0205
Commence a rapid down power using AP104 (Rapid
Downpower) at 0205
________.____.____-_----.--.-.-----
Distracter Analysis:
A.
Incorrect: no requirement to trip the reactor because reactor power
has turned and is decreasing. Not approaching the overpower
automatic reactor trip at 109% in 2 of 4 channels.
Plausible: shows a power mismatch - reactor power reaches
103% on 1 of 4 PR channels to cause C-2. OMP 4-3 (Use of
Abnormal and Emergency Procedures) requires the operator to trip
when an automatic safeguards action setpoint is approached to
avoid challenging the automatic safeguards function.
Correct answer required to trip under AP/OI (and many other
procedures) if you cannot maintain pressurizer level with 2 NV
Incorrect: required to trip when PZR level cannot be maintained
Plausible: if the candidate thinks that a reactor trip is required
because the steam leak was not isolated.
Incorrect: required to trip when PZR level cannot be maintained
Plausible: this would be the correct answer if not required to trip at
0204.
B.
pumps
C.
D.
Ques-593.1 .doc
Level: RO
KA: W/E12 EA1.03(3.4/3.9)
Lesson Plan Objective: AP-1 Obj. 4
Source: Bank;
Level of knowledge: comprehension
References:
1, AP/l/N5500/01 page 3
2. OP-MC-IC-IPE page 45
3. OMP 4-3, page 8
Ques-593.l.doc
Bank Question: 617.2
Answer: A
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 - 100°F
Lower Containment Temperature - 118 "F
What actions are required to restore and maintain normal operating
conditions to the PRT for the long term?
A.
B.
C.
Vent the PRT to the waste gas system.
Vent the PRT to containment.
Cool the PRT by pressurizing with nitrogen and initiating spray
flow from the NCDT.
Cool the PRT by initiating spray flow through the sparger line
from the RWST
D.
Distracter Analysis: With PRT pressure > 8 psig and temperature
containment temp, cooling the PRT will only result in the PRT heating back
up again.
A.
Correct:
B.
Incorrect: cannot be performed at power as the vent valve is inside
containment and is inaccessible at power
Plausible: venting to containment would accomplish the required
action
Incorrect: Lower Containment temp is 118 OF. Cooling the tank
further would only delay the time when it would heat back up again
and require further cooling. The PRT can be cooled by pressurizing
the PRT with nitrogen - but then spray flow must be initiated from
the RMWST not the NCDT.
Plausible: Cooling will reduce pressure temporarily but will not
allow the PRT to reheat to its normal limit of 114'F without getting a
high-pressure condition (containment temp is 11 8°F). In addition,
recirculating through the NCDT using the NCDT pumps cools the
PRT and pressure would be reduced -temporarily.
Incorrect: Cannot cool the PRT through the sparger line
Plausible: can cool the PRT by recircing through the RWST - must
pressurize with N2 and recirculate RWST water through the spray
and drain connections.
C.
D.
Ques-617.2.doc
Level: RO
KA: SYS 007 A2.02 (2.6/3.2)
Lesson Plan Objective: PS-NC Obj. 20
Source: BANK
Level of knowledge: memory
References:
1. OP-MC-PS-NC pages 41,43
Ques-617.2.doc
.. ,
.-
Bank Question: 891.2
Answer: A
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 recovery not assured for a design basis large break
LOCA when containment water level exceeds 10.5 feet?
A.
1 Pt
Operation of critical ECCS components needed for safe
recovery is endangered by submersion.
Operation of the NS pumps is endangered by excess debris
fouling the containment suction strainers.
Operation of the hydrogen purge system is compromised by
loss of direct access to the containment atmosphere.
Operation of the ND system is compromised by high suction
pressure
B.
C.
D.
Distracter Analysis:
A.
Correct: The containment flood plane reference is at 10.5 ft.
Submersion beyond this level will expose unqualified components
to a hostile environment that they are not qualified for.
B.
Incorrect: Submergence beyond the referenc flood plane will not
cause excess debris nor will it transport debris to the suction
strainers, which are at the very bottom of the containment sump.
Debris is generated by impingement of high energy releases
against containment SSCs - the design basis will prevent excess
debris if containment is maintained free of foreign material.
Plausible: Clogged suction strainers could occur if submergence
of components was a mechanism, which could lift debris. This is a
reason to keep foreign material out of containment.
Incorrect: The hydrogen purge system is far above the 10.5 ft flood
plane and would not be compromised.
Plausible: If the hydrogen purge system was submerged, it would
fail to operate.
Incorrect: 10.5 feet of water will not lift the ND suction relief, or if it
did the relief returns to the PRT.
Plausible: High containment level increases ND suction pressure.
Level: RO
KA: EPE W E 15 G2.1.7 (3.714.4)
Lesson Plan Objective: EP-MC-EP-
C.
D.
Ques-891.2.doc
FRZ Obj. 4
Source: BANK
Level of knowledge: Memory
References:
1. OP-MC-EP-FRZ page 47
Ques-891.2.doc
Bank Question: 895.1
Answer: A
1 Pt
Unit 1 is operating at 100% power. The battery charger IEDGA 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 I A emergency diesel generator will start but not continue
to run for its design basis committed time period without the
battery charger in service.
The 1A emergency diesel generator will not start without the
battery charger in service.
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.
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 IELXA.
6.
C.
D.
.__._____._________.-----------.---.
Distracter Analysis:
A.
Correct: The D/G will start because the D/G battery will supply all
starting loads. However, without the charger, the battery will expire
and power will be lost to the governor, voltage regulator and other
vital DC loads.
Incorrect: The D/G will start without the charger - power will be
supplied from the D/G battery.
Plausible: if the candidate does not know that removing the
inverter does not remove the battery from service. This would be
true if the DIG control power breaker was opened.
Incorrect: DG is inoperable without the battery charger.
Plausible: Some batteries have this feature.
Incorrect: DG is inoperable without the battery charger.
Plausible: The battery will provide power to DG auxiliaries for some
period of time - some vital D/G auxiliaries are supplied from the 600
VAC control center.
Level: RO
KA: APE 058 AK1.O1 (2.8/3.1*)
Lesson Plan Objective: OP-MC-DG-EPQ Objs. 3,4, 5,6,7
Source: BANfVModified
6.
C.
D.
Ques-895.l.doc
Level of knowledge: comprehension
References:
1. OP-MC-DG-EPQ pages 15-19 & 25 odd pages only
Ques-895. Ldoc
Bank Question: 906.1
Answer: C
1 Pt
A station emergency battery is supplying DC bus loads without a battery
charger online. If the load on the DC bus does not change, which one of
the following statements correctly describes a vital batterys discharge rate
(amps) as the battery is expended?
A.
The discharge rate will be fairly constant until the design
battery capacity (amp-hours) is exhausted and then will rapidly
decrease.
The discharge rate will decrease at a faster rate until the
design battery capacity is exhausted.
The discharge rate will increase at a faster rate until the design
battery capacity is exhausted.
The discharge rate will initially decrease until approximately
50% design capacity had been expended and then increase
until the battery has been exhausted.
B.
C.
D.
Distracter Analysis:
A.
Incorrect: The discharge rate increases.
Plausible: This is a typical response for many design systems - If
the candidate does not recall that V= IxR.
Incorrect: The discharge rate increases.
Plausible: If the candidate reverses the effect of decreasing
voltage on discharge rate.
Incorrect: The discharge rate increases.
Plausible: If the candidate does not understand battery theory.
B.
C.
Correct:
D.
Level: RO
KA: SYS 063 AI .01 (2.513.3)
Lesson Plan Objective: EL-EPL SEQ 12/20
Source: Bank
Level of knowledge: memory
References:
1. OP-MC-EP-EPL pages 65-67
Ques-906.l.doc
Bank Quesfion: 911.2
Answer: B
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
circulation is continuing?
A.
indication that natural
SIG saturation temperatures are decreasing and REACTOR
VESSEL URLEVEL indication is greater than 100 %.
SIG pressures are decreasing and Tcald is at SIG saturation
temperature.
SIG pressures are decreasing and REACTOR VESSEL D/P
indication is greater than 100%.
SIG pressures are decreasing and Thot is at SIG saturation
temperature.
Distracter Analysis:
A.
B.
C.
D.
_._____..___._____._----------.-----
Incorrect: There is no indication of coupling between primary and
secondary.
Plausible: These are important indications during natural
circulation.
Incorrect: dp range is unavailable during natural circulation.
Plausible: S/G pressure decreases during natural circulation and
RVLlS is one of the other plasma display indications.
Incorrect: dp range is unavailable during natural circulation.
Plausible: SIG pressure will remain close to saturation for Tcold
during natural circulation and RVLlS is one of the other plasma
display indications.
Level: RO
KA: 0017 A3.01 (3.6*/3.8*)
Lesson Plan Objective: EP-EO Obj. 6
Source: BANK
Level of knowledge: Memory
References:
B.
Correct:
C.
D.
Ques-911.2.doc
1. OP-MC-EP-EO pages 1 17, 123
2. ES-0.1 page 15
3. ES-0.1 Enclosure 2 page 31
Ques-911.2.doc
Bank Question: 957.1
Answer: D
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 fans/air handling units stopped after 5 minutes without any offsite
power?
A.
VU ventilation units
6. Pressurizer booster fans
C. Pipe tunnel booster fans
D.
Steam generator booster fans
Distracter Analysis:
A.
6.
C.
D.
Incorrect: VU AHUs and return air fans will start on a
LOOP/blackout -they have an emergency power supply.
Plausible: They will not start in a safety injection signal
Incorrect: Pressurizer booster fans will start on a LOOP from the
B/O sequencer - they have an emergency power supply.
Plausible: If the candidate confuses the emergency power supply
for the pressurizer booster fans with the steam generator booster
fans
Incorrect: Pipe tunnel booster fans will start on a LOOP from the
B/O sequencer - they have an emergency power supply.
Plausible: They will not start in a safety injection signal
Correct: Steam generator booster fans do not restart on a LOOP -
B/O signal -they do not have an emergency power supply
Level: RO
KA: SYS 022 K2.01 (3.0*/3.1)
Lesson Plan Objective: CNT-VUL LPRO 5
Source: Bank
Level of Knowledge: memory
References:
1. OP-MC-CNT-VUL pages 35,39
Ques-957.l.doc
Bank Question: 963.1
Answer: D
Unit 2 was at 75% R.T.P. when a loss of condenser vacuum occurred.
Given the following conditions:
Rods are in automatic
No operator action taken
Which one of the following sequences best describes the actuation of the
control rods to this event?
1 Pt
The steam dump select switch is selected to Tave mode
Condenser vacuum is slowly decreasing
No component or instrument failures occurred
A.
Control rods move in due to decreased condenser back
pressure
Control rods move out due to decreased condenser back
pressure
Control rods move in due to increased condenser back
pressure
Control rods move out due to increased condenser back
pressure
B.
C.
D.
___._____________._____._____
Distracter Analysis:
A.
Incorrect:
Plausible:
B.
Incorrect: -
Plausible:.
C.
Incorrect:
Plausible: -
D.
Correct
Level: RO
KA: APE 000051 MI .04 (2.5*/2.5*)
Lesson Plan Objective: OP-MC-STM-ID Obj. 9
Source: Bank
Level of Knowledge: Comprehension
References:
1 .OP-MC-STM-IDE pages 17-33 (odd only)
Bank Question: 975.1
Answer: C
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 1 B NS pump has been successfully swapped to the containment
sump.
1 NS-18A (A NS Pump Suct From Cont Sump) will not open.
Which one of the following is the reason 1 NS-18A will not open?
A.
B.
C.
D.
1NS-43A (A ND to NS Containment Outside /sol) is CLOSED
INS SYS CPCS TRAIN A INHIBIT light LIT
INI-185A (RB Sump to Train A ND & NS) is CLOSED
1NS-43A (A ND to NS Containment Outside /sol) is OPEN
Distracter Analysis:
A.
Incorrect:.
B.
Incorrect
Plausible:
C.
Correct:.
Plausible:.
D.
Incorrect:.
Plausible:.
Level: RO
Source: BANK
KA: SYS 026 K4.07(3.8*/4.1*)
Lesson Plan Objective: OP-MC-ECC-NI Obj. 8 ,
Source: BANK
Level of knowledge: comprehension
References:
1. OP-MC-ECC-NS page 17
Ques-975.l.doc
r
2. EP/lN5000/ES-1.3 page 8
3. OP-MC-ECC-NI page 21
Ques-975.l.doc
Bank Question: 976.1
Answer: B
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.
B.
C.
D.
The VF supply and exhaust fans trip and the filter is placed in
the FILTRATION MODE.
No effect on VF system alignment.
The VF system is automatically placed in BYPASS MODE and
the discharge dampers open and supply dampers close
The VF system is automatically placed in the FUEL HANDLING
MODE OF OPERATION and the supply fans trip.
________.____.______~-----------
Distracter Analysis: When fuel handling is in progress the VF system
is placed in Filter Mode as a result no system changes will
occur.
A.
Incorrect:.
Plausible:.
B.
Correct:
C.
Incorrect:
Plausible:
D.
Incorrect:
Plausible:.
Level: RO
KA: SYS 072 A3.01 (2.9*/3.1)
Lesson Plan Objective: OP-MC-FH-VF Obj 8 & 9
Source: BANK
Level of knowledge: Comprehension
References:
1. OP-MC-FH-VF page 17
Ques-976. Ldoc
Bank Question: 977. I
Answer: C
1 Pt
Unit 1 is at 100% power when indications are received of a 1 B Reactor
Coolant Pump seal malfunction. AP/l/A/5500/08 (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
- 1 Seal Leak off flow - GOING U P
NC Pump number 2 Seal Standpipe high level alarm - LIT
NCDT input - STABLE, OR GOING DOWN
- 1 Seal Leak off flow - GOING DOWN
NC Pump number 2 Seal Standpipe high level alarm - LIT
NCDT input - GOING UP
- 1 Seal Leak off flow -GOING UP
NC Pump number 2 Seal Standpipe low level alarm - LIT
NCDT input - GOING UP
B.
C.
D.
_.___________________.______
Distracter Analysis:
A.
Incorrect:
B.
Incorrect:
C.
Correct:
D.
Incorrect:
Plausible: #I
Seal UO WILL go down
Plausible: High Standpipe level alarm WILL lite.
Plausible: NCDT input WILL go up
Level: RO
KA: SYS 003 A3.03 (3.2/3.1)
Lesson Plan Objective: OP-MC-PS-NCP, Obj. 12
Source: Bank
Level of knowledge: Comprehension
Ques-977.l.doc
References:
1. OP-MC-PS-NCP pages 25-29
2. AP/l/A/5500/08 Malfunction of NC Pump
Ques-977.l.doc
Bank Question: 984.1
Answer: A
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
Distracter Analysis:
A.
Correct:
B.
C.
D.
_________.____._____-----.----.--
Incorrect: Should not be scheduled during turnover
Plausible:
1ncorrect:Should not be scheduled during turnover
Plausible
Incorrect: Should not be scheduled during turnover
Plausible:.
Level: RO
KA: G2.1.3 (3.W3.4)
Lesson Plan Objective:
Source: Bank
Level of knowledge: memory
References:
1. OMP 2-2 page 31
Ques-984.l.doc
Bank Question: 1012.1
Answer: D
Unit 1 is responding to a small break LOCA inside and outside
containment. Given the following events and conditions:
1 Pt.
FWST Level indicates 340 inches
Containment pressure indicates 1.5 psig
Containment Sump Level indicates 1.05 A
IEMF-41 (AUXBLDG VENTILATION) is in Trip 2 alarm
Aux Building area radiation monitors are in alarm
1EMFdlA and B (CONTAINMENT TRNA 8.6) indicates 25 FUHr
Hydrogen Analyzer indicates 0.7% in containment
NLOs report significant leakage at the seals of the 1A ND pump
Which one of the following actions reduces excessive levels of radiation
and guard against personnel exposure?
A.
Monitor 1EMF-41 (AUXBLDG VENTILATION)
B.
C.
Dispatch NLO to energize Hydrogen Recombiners
Secure VA (Aux. Bldg. Ventilation System) to limit airborne
contamination.
Identify and isolate the break
D.
Distracter Analysis: The initial conditions provide a LOCA into
containment and a leakage path outside of containment. The question is
which of the problems take priority? The purpose is not to memorize
procedure steps but to answer this from a broader perspective.
A.
__.____.____________-.---.-.--.-.-
Incorrect: Monitoring of rad levels does not minimize exposure.
Plausible: If the candidate thinks that the abnormal radiation level
requires priority action.
Incorrect: Energizing the Hydrogen Recombiners does not limit rad
exposure in the Aux. Bldg.
Plausible: Small Hydrogen Concentration inside containment
exists).
Incorrect: This is needed to limit personnel exposure..
Plausible: If the candidate thinks there is an airborne problem.
B.
C.
D.
Correct:
Level: RO
KA: G3.10 (2.W3.3)
Lesson Plan Objective: EP-E1 OBJ 3
Ques-lOl2.l.doc
Source: BANK
Level of knowledge: comprehension
References:
1.OP-MC-EP-E1
page 231,233,235
2. EP/I/A/5000/ECA-1.2
Ques-lOl2.l.doc
Bank Question: 1022
Answer: D
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)
3)
Pressurizer level is 25%
4)
T
,
= 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?
Pressurizer pressure is 325 psig
A.
B.
C.
D.
MISCINFO:
SOURCE:
ID loop Hot leg WR temperature < 320 degrees and WR pressure D
loop >380 psig will actuate PORV NC-34A
C loop Cold Leg temperature < 320 degrees and NR pressure A
loop > 380 psig will actuate PORV NC-32B
IC loop Cold Leg temperature < 320 degrees and WR pressure A
loop > 380 psig will actuate PORV NC-32B
D
loop Hot Leg WR temperature < 320 degrees and NR pressure D
loop > 380 psig will actuate PORV NC-34A
NEW
Level of Knowledge: Memory
Author:
cws
REFERENCES:
OP-MC-PS-NC pages 45 & 49
LESSON:
OP-MC-PS-NC
OBJECTIVE: OP-MC-PS-NC Obj. 21
KIA:
APE 008 AA206 (3.313.6)
1022.doc
1
Bank Question: 1023
Answer: A
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. 1KC338B (NCP Supply)has closed
C. 1RN43A (Train 1B to Non Ess Hdr Isol) has closed
D. IKC-228B (RB HDR supply) has closed
Distracter Analysis:
A.
Correct
B.
C.
D.
KC system has no effect on motor stator temperatures
Closure of this valve will have no effect on stator temperatures
KC system has no effect on motor stator temperatures
Level: RO
KA: APE 015 AA2.01 (3.0/3.5)
Lesson Plan Objective: OP-MC-PS-NCP Obj 7
OPO-MC-PSS-RN Obj 10
Source: New
Author: CWS
Level of knowledge: memory
References:
1. OP-MC-PS-NCP page 5, 13 & 17
2. OP-MC-PSS-RN page 31 & 75
Ques-lO23.doc
Date: 3/06/2003
Ques-1023.doc
Bank Question: 1024
Answer: C
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
Which one of the following instrument failures would cause this plant
response and what is the correct operator action perAP/11 (Pressurizer
Pressure Anomalies)?
A.
PORVs 1 NC 32B and NC 368 open at 2335 psig
Pressure modulates between 2315 psig and 2335 psig.
PZR pressure channel I fails high
Immediately swap controlling channels
PZR pressure channel II fails low
Place Pressurizer Pressure Master in Manual
PZR pressure channel I fails low
Place Pressurizer Pressure Master in Manual
B.
C.
D.
PZR pressure channel II fails high
Immediately swap controlling channels.
.__.___._______..___~---.------
Distracter Analysis:
R
B.
C.
Correct:
D.
Incorrect: -
Incorrect: - channel I failing high causes pressure to decrease
Plausible: -
Incorrect answer - If a channel II fails low you immediately swap
controlling channels.
Plausible: -
Level: RO Only
KA: APE 027 AK3.03 (3.7/4.1)
Lesson Plan Objective: PS-IPE Obj. 12
Source: NEW
Author: CWS
Level of knowledge: comprehension
References:
1. OP-MC-PS-IPE page 35
Ques-1024.doc
Bank Question: 1025
Answer: B
1 Pt.
Unit 1 is operating at 100% power when a small break LOCA occurs.
Given the following
a)
b)
c)
d)
e)
Subcooling is 0 degrees
f)
Pressurizer level is 2%
g)
Which one of the following should be the status of the reactor coolant
pumps?
A.
Reactor Trip and Safety Injection Actuated
E-0 (Reactor Trip or Safety Injection) completed
Crew has exited E-0 to E-I (Loss of Reactor or Seeonday Coolant)
Both trains of ECCS equipment are functioning normally
Containment pressure is 2.5 psig
The reactor coolant pumps should still be running to provide
forced cooling through the core.
The reactor coolant pumps should be stopped to prevent
excessive depletion of the NC system water inventory.
The reactor coolant pumps should still be running to refill the
pressurizer in order to terminate Safety Injection flow.
The reactor coolant pumps should be stopped to prevent
pump damage due to loss of pump support systems.
B.
C.
D.
________.____.____._------------.-
Distracter Analysis:
A.
B.
Correct.
C.
Incorrect
D.
containment.
Incorrect - NCP should be stopped on loss of subcooling
Incorrect: Do not lose support systems on 2.5 # in
Level: RO
KA: APE 009 EK3.13 (3.4/3.7)
Lesson Plan Objective: OP-MC-EP-ECA-0 Obj. 4
Source: New
Ques-lO25.doc
Level of knowledge: Comprehensive
Author:CWS
References:
1,OP-MC-EP-E1 page 53
Ques-1025.doc
Bank Quesfion: 1026
Answer: D
Unit 2 is operating at 100% power when the following occurs:
1 Pt.
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 restoring NCP
seal flows in ECA-O.1?
A. Slowly restore seal injection cooling limiting the cooldown rate to
1 degree per minute
8 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.
_________-___-.____.~----.--------
Distracter Analysis:
A.
B.
closed.
C.
closed
D.
Correct
Incorrect - old procedure guidance
Incorrect do not restore seal cooling after needle valves
Incorrect do not restore seal cooling after need le vavles
Level: RO
KA: APE 022 AKI .01 (2.8/3.2)
Lesson Plan Objective: OP-MC-EP-ECA-0 Obj. 3
Ques-lO26.doc
Source: New
Level of knowledge: Comprehension
Author: CWS
References:
1.OP-MC-EP-ECA-0 page 79
Ques-1026.doc
Bank Question: 1027
Answer: C
Unit 1 has experienced a large break LOCA.
Given the following conditions:
1 Pt.
E-0 (Reactor Trip or Safefy 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 6
hot legs
6. Flow is lost to the A, E, C and D hot legs
C. Flow is lost to the 6
and C hot legs
D. Flow is lost to A and D hot Legs
_.______________._._.-.--.----.--.--
Distracter Analysis:
A.
6.
C.
Correct
D.
Incorrect -This is alignment for CLR
Incorrect all legs are not aligned for hot leg recirc
Incorrect flow is not go aligned to A and D
hot legs
Level: RO
KA: APE 025 AK2.02 (3.2*/3.2)
Lesson Plan Objective: OP-MC-PS-ND Obj. 8
Source: New
Level of knowledge: memory
Ques-1027.doc
Author: CWS
References:
1. OP-MC-PS-ND
pages 51 & 73
Ques-1027.doc
Bank Question: 1028
Answer: D
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. 1/4 on 1/4 steamlines
B. 2/3 on 214 steamlines
C. 1/4 on 2/4 steamlines
D. 2/3 on 1/4 steamlines
____________________----------
Distracter Analysis:
A.
Incorrect -
B.
Incorrect
C.
Incorrect
D.
Correct
Level: RO
KA: APE 040 AK3.01 (4.2/4.5)
Lesson Plan Objective: OP-MC-ECC-ISE Obj. 13
Source: New
Level of knowledge: memory
Author: CWS
References:
1. OP-MC-ECC-ISE page 65
Ques-1028.doc
Bank Question: 1029
Answer: D
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/1,4/5500/14 Rod ConfrolMalfunction 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?
A.
B.
C.
D.
Rod insertion limit is unchanged and shutdown margin is
increased.
Rod insertion limit is decreased and shutdown margin is
unchanged.
Rod insertion limit is unchanged and shutdown margin is
decreased.
Rod insertion limit is decreased and shutdown margin is
decreased.
Analysis:
A.
Incorrect:
Plausible:.
B.
Incorrect:.
Plausible:.
C.
Incorrect:
D.
Correct:
______._________._________._
-Distracter
Plausible:.
Level: RO
KA: 000003.AK1.07 (3.U3.9)
Ques-lO29.doc
..,
Lesson Plan Objective:
Source: New
Author: CWS
Level of knowledge: comprehensive
References:
1, McGuire 1 Cycle 16 COLR pages 9,11 & 12
2. REACT (Reactor Engineering Analysis & Computer Tools)
Shutdown Margin-Unit at Power, Modes 1 & 2 Calculations
Ques-1029.doc
Bank Question: 1030
Answer: C
Unit 1 is in Mode 3 at normal operating temperature and pressure. While
performing trouble shooting activities 1 NV-MAC (NC Pump Seal Return
Containment Isolation Valve) closes.
1 Pt.
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-956 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 1NV84AC.
Distracter Analysis:
A.
B.
Incorrect - seal return flow goes to PRT
Incorrect INV-94 and INV-95 are in series Student may think
the valves are in parallel.
C.
Correct
D.
Incorrect - check valve prevents this flow path
Level: RO
KA: SYS 003 K6.04 (2.8/3.1)
Lesson Plan Objective: OP-MC-PS-NV Obj. 5
Source: New
Level of knowledge: Memory
Author: CWS
References:
1. OP-MC-PS-NV pages 39,41 B 115
Ques-1030.doc
Bank Question: 1031
Answer: B
1 Pt.
Unit 2 was operating at 49% power when the following indications were
observed:
0
e
Feedwater flows decreasing
Feedwater Isolation Signal actuated
Steam Generator level in the 2A S/G is 84% on 213 level indications
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 reactor have
tripped.
C. Feedwater pump A and the turbine only have tripped.
D. Both feedwater pumps and turbine have tripped, the reactor did not
trip.
B.
Correct
C.
D.
Incorrect: - see A above
Incorrect: reactor trips above P-8 48%
Level: RO
KA: SYS 059 K4.01 (3.3/3/5)
Lesson Plan Objective: OP-MC-CF-CF Obj. 14
Source: New
Level of knowledge: Comprehensive
Author: CWS
References:
OP-MC-IC-IPE Obj. 10 & I 1
Ques-lO3l.doc
1. OP-MC-CF-CF page 35
2. OP-MC-IC-IPE pages 79,81 & 83
Ques-lO3l.doc
Bank Question: 1032
Answer: D
1 Pt.
Given the following conditions:
Unit 1 is at 100%
No annunciators are in alarm
TD CA pump is being started for post maintenance testing (oil
change)
RO places the #I
TD 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 lSA-48ABC (IC S/G SM Supply to unit 1 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.
Distracter Analysis:
A.
Incorrect - would have an annunciator if the valve is not fully
open.
Incorrect SA 48 and SA 49 are in parallel no effect.
Incorrect TD CA pump would not start if in local. There is a
B.
C.
status light that would be lit if this switch were in local.
D.
Correct
Level: RO
Source: NEW
KA: SYS 039 A4.04 (3.8/3.9)
Lesson Plan: OP-MC-CF-CA
Lesson Plan Objective: OP-MC-CF-CA Obj. 7
Level of knowledge: Memory
Ques-lO32.doc
Author: CWS
References:
OP-MC-CF-CA pages 15,23,25 & 27
Ques-lO32.doc
Bank Question: 1034
Answer: A
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-11 B (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/Af5500/17 (Loss of Control Room) has been implemented on both
Units.
Which one of the following describes S/G pressure control for the condition
described above?
1 Pt.
A.
B.
C.
D.
All S/G PORVs are controlling between 1092 psig and 1125
psig.
A and B
S/G PORVs are controlled manually to maintain
less than 1170 psig.
C and D
S/G PORVs are controlled manually to maintain
less than 1170 psig
Only A and D S/G PORVs are controlling between 1092 psig
and 1125 psig.
______.____.____.___-.---..---..--.-
Distracter Analysis: Manual control of SIG pressure if only taken if
S/G pressure is greater than 1170 psig and the SIG safeties are
lifting. Only the A and ID S/G have local manual control
available.
A.
Correct:.
B.
C.
D.
Plausible:
Incorrect: Can not control B S/G manually
Plausible:
Incorrect: Can not control C S/G manually.
Incorrect:. All S/Gs would be functioning normally
Level: RO
KA: APE 000068 (3.7/4.0)
Lesson Plan Objective: OP-MC-AP-17 Obj. 2
Source: New
Level of Knowledge: Comprehension
References:
1. OP-MC-AP-17 Obj. 2
2. AP/l/~5500/17
page 10 and Enclosure 7
Ques-lO34.doc
3. AP/l/N5500/17 Background document page 14
Ques-1034.doc
Bank Question: 1036
Answer: A
1 Pt.
Given the following conditions on Unit 1:
Blackout on ETB
The 1 B DIG 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.
The sequencer was reset to its ground state and the
accelerated sequence relay timed out.
The sequencer was reset and placed it in priority mode and the
undervoltage condition was still present.
The engine overspeed trip resets, and the accelerated
sequence relay timed out.
B.
C.
D.
Distracter Analysis: The actions needed to retart the diesel after an
automatic start are listed in A above.
A.
Correct:
Plausible:
B.
Incorrect:
Plausible:
C.
Incorrect:
Plausible:
D.
Incorrect
Plausible:
LEVEL RO
KA: 00051 EA1.02 (4.314.4)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Analysis
AUTHOR CWS
Ques-1036.doc
LESSON: OP-MC-DG-DG
OBJECTIVES: OP-MC-DG-DG Obj 10
REFERENCES: OP-MC-DG-DG pages 23
Ques-1036.doc
Bank Question: 1038
Answer: C
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 IEMXA 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 EVDA.
No effect; battery EVCC will continue to power EVDA.
No effect; battery EVCAwill continue to power EVDA.
EVDAwill be de-energized until cross tied with EVDD.
B.
C.
D.
Distracter Analysis:.
A.
B.
C.
Correct:
D.
Incorrect: Charger connection box is Kirk-keyed
Plausible:
Incorrect: No automatic function for EVCC to power EVCA
Plausible:
Plausible:
Incorrect Cant crosstie EVDA and EVDD
Plausible:
LEVEL: RO
KA: 00062 K1.03 (3.514.0)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Memory
AUTHOR CWS
LESSON: OP-MC-EP-EPL
OBJECTIVES: OP-MC-EP-EPL Obj 9
Ques-1038.doc
REFERENCES: OP-MC-EP-EPL pages 21 & 69
Ques-lO38.doc
Bank Quesfion: 1039
Answer: B
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 (NF 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.
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 />.
Design containment pressure of 60 psig will not be exceeded.
The time to reach peak containment pressure is 50 minutes.
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 />.
B.
C.
D.
Distracter Analysis: There are 24 ice condenser bays in containment.
With 8 bays having experienced buckling and the doors
incapable of opening 1/3 of the total flowpath into the ice
condenser is now blocked.
Incorrect: peak containment pressure is reached in 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />
Plausible: peak containment pressure is correct.
Plausible:
Incorrect Answer: peak pressure to high, time to reach is too
short
Incorrect: peak pressure to high.
Plausible: 20 psig is appropriate for some non-ice condenser
plants..
Level: RO
KA: SYS 025K3.01(3.8*/3.8*)
Lesson Plan Objective: OP-MC-CNT-NF Obj. 20
Source: NEW
Level of knowledge: Comprehension
A.
B.
Correct.
C.
D.
Ques-1039.doc
References:
1. OP-MC-CNT-NF pages 69 & 17
2. OP-MC-CNT-CNT pages 17 & 21
Ques-1039.doc
Bank Question: 1040
Answer: B
~~
1 Pt
Which one of the following are the power supplies for the Unit 1 MG sets?
A.
1 LXE and 1 LXF
B.
ILXF and ILXG
C.
ISLXF and ISLXG
D.
ISLXG and ISLXH
Distracter Analysis:.
A.
Incorrect: ILXE is not correct
B.
Correct
C.
D.
Plausible:
Plausible:
Incorrect: Power does not come from shared load centers
Plausible:
Incorrect Power does not come from shared load centers
Plausible:
LEVEL RO
KA: 00001 K2.05 (3.1*13.5)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Memory
AUTHOR: CWS
LESSON: OP-MC-IC-RTB
OBJECTIVES: OP-MC-IC-RTB Obj 11
REFERENCES: OP-MC-IC-RTB page 19
Ques-1040.doc
Bank Question: 1041
Answer: D
Which one of the following is the power supply for the 28 Hydrogen
Recombiner?
A.
2TA
6.
2ETA
1 Pt
C.
ZEMXC
D.
2EMXD
__._______________________
Distracter Analysis:.
A.
Incorrect:
Plausible:
6.
Incorrect:
Plausible:
C.
Incorrect:
Plausible:
D.
Correct
Plausible:
LEVEL: RO
KA: 0028 K2.01 (2.5*/2.8*)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Memory
AUTHOR CWS
LESSON: OP-MC-CNT-VX
OBJECTIVES:
REFERENCES: OP-MC-CNT-VX page 49
Ques-104l.doc
Bank Question: 1043
Answer 6:
Given the following conditions on Unit 2:
1 Pt
75%power
Annunciator Subcooling Margin Alert comes into alarm
Which one of the following describes the origin of the alarm?
Reference Provided
Steam Tables
A.
B.
C.
D.
Wide Range Pressure Loop C fails to 0 psig
Wide Range Pressure Loop D fails to 0 psig
One safety related thermocouple fails to 725 degrees
Wide Range T hot B
loop failing high to 650 degrees
__.___.______.______________
Distracter Analysis:. The alarm Subcooling Margin Alert is actuated
due to A train inputs only
Incorrect: Input to 6
train
Plausible:
Plausible:
Incorrect: 625 x 4 + 750 = 3225 / 5 =645 degrees which is not
witin 2 degrees of 650 where the alarm would come in
Plausible: Average CETC temp at 100% is 624 degrees
Incorrect Input to B train
Plausible:
A.
B.
Correct:
C.
D.
LEVEL: RO
SOURCE: NEW
LEVEL OF KNOWLEDGE: Comphrension
KA: SYS 002 K6.06 (232.8)
AUTHOR CWS
LESSON: OP-MC-IC-ICM
Ques-1043.doc
OBJECTIVES: OP-MC-IC-ICM Obj 9
REFERENCES: OP-MC-IC-ICM page 33
Ques-1043.doc
Bank Question: 1044
Answer: D
Unit 1 was at 100% power when the A
FWPT 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.
B.
C.
D.
1 Pt
Rods will insert at 72 steps per minute.
Rods will insert at 64 steps per minute.
Rods will insert at 40 steps per minute.
Rods will insert at 48 steps per minute.
Distracter Analysis:.
A.
B.
C.
Incorrect: this speed is for auto mode only at a 5 degree mismatch
Plausible:
Incorrect: this speed is for shutdown banks only
Plausible:
Incorrect: this speed is correct for auto rod movement at a 4
degree error
Plausible:
Plausible:
D.
Correct
LEVEL: RO
KA: 014 A4.02 (3.4/3.3)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Memory
AUTHOR CWS
LESSON: OP-MC-IC-IRX
OBJECTIVES: OP-MC-IC-IRX Obj 8
REFERENCES: OP-MC-IC-IRX pages 21,23,25
Ques-1044.doc
Bank Question: 1045
Answer: D
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/l/N5500/17
(Loss of Control Room).
Which one of the following describes the RO actions described in
AP/I/N5500/17 Loss of Control Room?
A.
B.
Go to Aux Shutdown Panel.
Go to main turbine front standard.
C.
D.
Go to Unit 1 CF pumps.
Go to REACTOR PUMP WATER MAKEUP CONTROL PANEL
if dilution in progress.
Distracter Analysis:.
A.
Incorrect: this is an SRO function
Plausible:
B.
Incorrect: this is an NLO function
Plausible:
C.
Incorrect: this is an NLO function
Plausible:
D.
Correct
Plausible:
LEVEL: RO
KA: G 2.4.34 (3.8/3.6)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Memory
AUTHOR: CWS
LESSON: OP-MC-AP-17
OBJECTIVES: OP-MC-AP-17 Obj. 2
REFERENCES: AP 17 Background document pages 4-6
APll/Al5500/17 page 3
Ques-1045.doc
Bank Question: 1046
Answer: B
1 Pt
While shifting to cold leg recirc during a LOCA, 1 ND 58A (NV/N/ pump Train A
Isolation) will not open.
Which one of the following is a possible cause of this problem?
A.
1 NI-I 15B (A NI Pump Miniflow) must first be closed.
8.
INI-185A (TRAINA ND TO NV& NI PUMPS) must first be open.
C.
IND-19A (A ND Pump Suction From FWST or NC) must first be open.
D.
INI-144B (6
NI Pump Miniflow) must first be closed.
.........................................................................................................................
LEVEL: RO
SOURCE: NEW
LEVEL OF KNOWLEDGE MEMORY
LESSON: OP-MC-ECC-NI
OBJECTIVE: OP-MC-ECC-NI Obj. 8
REFERENCES:
OP-MC-ECC-NI page 21
KIA: 006 K3.01 (4.1/4.2)
AUTHOR: CWS
Ques-1046.doc
Bank Question: 1047
Answer: D
1 Pt
Given the following conditions on Unit 1:
0
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 failure?
A.
Relief valve IND-56 (Discharge Relief Valve) has failed open to
IND-34 (A 8, B ND Hx Bypass) fails OPEN
Relief valve IND-56 (Discharge Relief Valve) has failed open to
NCDT.
Flange leak on 'A' RHR heat exchanger.
B.
C.
D.
Distracter Analysis:. The procedure for swapping ND trains has an
operator sent to the HX room to listen for excessive vibration.
McGuire has experienced an event where a leak developed on
the flange of the RHR HX as a result of a water hammer.
Incorrect: would not have auxiliary building EMFs in alarm
Plausible:
Incorrect: This would account for the temperature increasing
Plausible:
Plausible:
Plausible:
A.
B.
C.
Incorrect: Relief goes to PRT
D.
Correct
LEVEL: RO
KA: 005 K6.03 (2.W2.6)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Memory
Ques-1047.doc
AUTHOR: CWS
LESSON: OP-MC-PS-ND
OBJECTIVES: OP-MC-PS-ND Obj. 6
REFERENCES: OP-MC-PS-ND pages 21 and 61
Ques-1047.doc
Bank Question: 1048
AnswecD
Given the following conditions on Unit 1:
1 Pt
Unit 1 ET6 normal breaker has opened
1 B Diesel Generator has started and has loaded the bus
Which one (1) of the following will trip the diesel generator?
A.
B.
C.
Turning Gear Engaged
D.
Overspeed 113%
Lube Oil Temperature 195 degrees
Jacket Water Temperature 205 degrees
Distracter Analysis:.
A.
Incorrect: Manual mode only
B.
Incorrect: Manual mode only
C.
Incorrect: Manual mode only
D.
Correct
Plausible:
Plausible:
Plausible:
Plausible:
LEVEL RO
KA: 064 K4.02 (3.9/4.2)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Memory
AUTHOR: CWS
LESSON: OP-MC-DG-DG
OBJECTIVES: OP-MC-DG-DG Obj. 5 & 6
REFERENCES OP-MC-DG-DG pages 39-43 odd pages only
1 Pt
Diesel generator 1 B has been started per OP/l/A/6350/002 (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 16 DIG Sync Switch to ON
Adjust diesel speed to move slowly in the Fast direction using
16 DIG Gov Control pushbutton
Close normal breaker when 3 minutes before 12 oclock
Raise D/G output to 800 to 1000 KW
Adjust Power factor to .90 to .92
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 D/G output to 800 to 1000 KW
Adjust Power factor to .90 to .92
Place 16 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
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
B.
C.
D.
Ques-1049.doc
Bank Question: 1049
Answer: A
Diesel generator 1 B has been started per OP/l/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.
1 Pt
Match DIG voltage with line voltage
Place IB DIG 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 800 to 1000 KW
Adjust Power factor to .90 to .92
Place 1 B Sync Switch to ON
Adjust diesel speed to move slowly in the Fast direction using
Voltage Adjust pushbutton
Transfer load from 1 B 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
Place IB Sync Switch to ON
Adjust diesel speed to move slowly in the Fast direction using
18 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
Place 1 B 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
B.
C.
D.
Distracter Analysis:.
A.
Correct:
Ques-1049.doc
Plausible:
B.
Incorrect:
Plausible:
C.
Incorrect:
Plausible:
D.
Incorrect
Plausible:
LEVEL: RO
KA: 064 A4.07 (3.4/3.4)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Comprehension
AUTHOR: CWS
LESSON:
OBJECTIVES:
REFERENCES: OP/l/N6350/002 Enclosure 4.4 page 2
Ques-1049.doc
Bank Question: 1050
Answer: B
~~~~~
~
~
~
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 delta/p 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.
B.
No effect after swapping to the I B BAT pump.
Boron injection flowpath from BAT via the boric acid pumps
and charging pump to NC is inoperable.
No effect after swapping to standby filter in service.
Boron injection flowpath is operable due to availability of
C.
D.
1 NV-265B.
LEVEL: RO
KA: 004 K1.16 (3.3/3.5)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Analysis
AUTHOR CWS
LESSON: OP-MC-PS-NV
OBJECTIVES: OP-MC-PS-NV Objs. 5 & 15
Ques-1050.doc
REFERENCES: OP-MC-PS-NV pages 43,51, & 133
SLC 16.9.9 Boration Systems - Flow Paths
Ques-1050.doc
Bank Question: 1051
Answer: D
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?
A.
On a LOCA outside containment there will be no containment
isolation signal.
There are no operational differences.
On a LOCA outside containment the containment sump valves
do not automatically open on low FWST level.
As FWST inventory depletes there is no corresponding
increase in containment sump level.
B.
C.
D.
__.____.__._________----.--.----.
Distracter Analysis:.
A.
Incorrect: A manual SA will be generated on low pressurizer level
and charging flow as a result a containment isolation signal will
actuate.
Plausible:
Incorrect: Phase 'B components will not actuate on LOCA outside
containment
Plausible:
Incorrect: Not correct they will open on 180 FWST level whethe6
there is water in the sump or not.
Plausible:
Plausible:
B.
C.
D.
Correct
LEVEL: RO
KA: W E 0 4 EK2.1 (3.U3.9)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Comprehension
AUTHOR: CWS
LESSON: OP-MC-ECC-ISE
OP-MC-PS-ND
OBJECTIVES: OP-MC-PS-ND Obj. 7
REFERENCES:
OP-MC-PS-ND page 29
OP-MC-ECC-ISE Objs. 5 and 13
OP-MC-ECC-ISE pages 15 & 29
Ques-105l.doc
Bank Question: 1052
Answer: A
Which one (1) of the following provides separation between control system
and protection system circuits?
A.
Isolation Amplifier
B.
Diodes
1 Pt
C.
Separate input signal
D.
Or/And gate
__________._________----------
Distracter Analysis:.
A.
Correct:
Plausible:
B.
Incorrect:
Plausible:
C.
Incorrect:
Plausible:
D.
Incorrect
Plausible:
LEVEL: RO
KA: SYS 016 K5.01 (2.7*/2.8*)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Memory
AUTHOR. CWS
LESSON: OP-MC-IC-IPE
OBJECTIVES:
REFERENCES: OP-MC-IC-IPE page 17
Ques-lO52.doc
Bank Question: 1056
Answer: C
Given the following conditions on Unit 1 :
1 Pt
Pzr level is 0%
Loss of Offsite Power coincident with a LOCA
Power has been restored to ETA via '1A D/G while in
EP/l/A/5000/ECA-0.0 (Loss of All AC Power)
NC Subcooling is -1 degree
1 NI-9A (NC Cold Leg lnj from NV) is closed
INI-1OB (NC Cold Leg lnj from NV) is closed
Which one (1) of the following procedure is required for optimal recovery of
the plant?
A.
Go to EPll/N5000/ECA-0.1 (Loss ofAll AC Power Recovery
Without S/I Required)
Go to EP/I/N5000/E-l (Loss of Reactor or Secondary Coolant)
Go to EP/l/N5000/ECA-0.2 (Loss of All AC Power Recovery
With S/I Required
Go to EP/1/A/5000/ES-1 .2 (Posf LOCA Cooldown and
Depressurization)
B.
C.
D.
~~~
Distracter Analysis:.
A.
Incorrect:
Plausible:
B.
Incorrect:
Plausible:
C.
Correct:
Plausible:
D.
Incorrect
Plausible:
LEVEL: RO
KA: 000056 AK1.04 (3.1*/3.2*)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Comprehension
AUTHOR CWS
Ques-1056.doc
LESSON: OP-MC-EP-ECA-0
OBJECTIVES: OP-MC-EP-ECA-0 Obj 2
REFERENCES: OP-MC-EP-ECA-0 Page 61
EP/IA/5500/ECA 0.0 page 30
Ques-1056.doc
Bank Question: 1059
Answer: D
Given the following conditions on Unit 1:
Large break LOCA occurred.
1 Pt
Both trains of NV, NI, ND, NS are running
LOOD A
Loop B
Loo0 c
LOOP D
SIG (NR) [%]
10
9
10
9
The operators are in E-0 (Reactor Trip or Safety 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 following statements correctly describes the method for
controlling feed flow?
REFERENCES PROVIDED:
E-0 Enclosure3
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.
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.
If NIR level is less than 11% in all SIGs throttle feed flow to
minimize cooldown and maintain total feedwater flow greater
than 450 gpm.
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.
B.
C.
D.
_________._____.___________
Distracter Analysis:
A.
Incorrect:
Plausible:
B.
Incorrect:
Plausible:
C.
Incorrect
D.
Correct:
Plausible:
Level: RO
Ques-lO59.doc
KA: SYS 061 K5.01 (3.6/3.9)
Lesson Plan Objective: OP-MC-EP-EO Obj. 6
Source: NEW
AUTHOR: CWS
Level of knowledge: Analysis
References:
1. OP-MC-EP-E-0 page 75
2. EP/I/N5000/E-O Enclosure 3 - PROVIDED
Ques-1059.doc
i
Bank Question: 1061
Answer: B
Given the following conditions on Unit 1:
1 Pt
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.1
(Response to Nuclear Power Generation/ATWS), 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 Power Generation/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.
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
maintain S/G inventory.
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 S/G inventory.
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
B.
C.
D.
Distracter Analysis:.
A.
Incorrect:
Plausible:
Ques-lO6l.doc
B.
Correct:
Plausible:
C.
Incorrect:
Plausible:
D.
Incorrect
Plausible:
LEVEL: RO
KA: 000029 EK1.O1 (2.8/3.1)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Analysis
AUTHOR CDC
LESSON: OP-MC-EP-FRS
OBJECTIVES: OP-MC-EP-FRS Obj 4
REFERENCES: OP-MC-EP-FRS pages 23 &25
EP/1/N5000/FR-S.1 page 2
Ques-106l.doc
Bank Question: 1062
Answer: D
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?
A.
During the Injection phase by providing a spray of cold and
subcooled borated water from the FWST into the upper
containment volume.
During the Injection phase by providing a spray of water with
an alkaline pH from the containment sump into the upper
containment volume.
During the Recirculation phase by providing a spray of cold
and subcooled borated water from the FWST into the upper
containment volume.
During the Recirculation phase by providing a spray of water
with an alkaline pH from the containment sump into the upper
containment volume.
B.
C.
D.
*------
______________-______________.________I---------------
Distracter Analysis:.
A.
Incorrect:
Plausible:
B.
Incorrect:
Plausible:
C.
Incorrect:
Plausible:
D.
Correct
Plausible:
LEVEL: RO
KA: 027 K1.01 (3.4/3.7)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Memory
AUTHOR CDC
Ques-lO62.doc
LESSON: OP-MC-ECC-NS
OBJECTIVES: OP-MC-ECC-NS Obj 1
REFERENCES: OP-MC-ECC-NS page 11
MNS Technical Specifications Bases for T.S. 3.6.6
Containment Spray System
Ques-lO62.doc
Bank Question: 1063
Answer: C
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.
0
All NC Pump upper Motor Bearing temperatures are trending up.
" B NC Pump Upper Motor Bearing temperature is 197 degrees.
AP-21 (Loss of KC or KC System Leakage) has been implemented.
Which one (1) of the following describes the operator's response to " 6
NCP Upper Motor Bearing HI temperature?
AP/I/N5500/21 Loss KC
A.
Close INC-29 (B Loop PZR Spray Confrol), trip the reactor,
stop "B" NC Pump and go to EP/l/A/5000/E-O
Trip the reactor, stop "B" NC Pump and go to EP/l/A15000/E-O
Trip the reactor, trip all NC Pumps and go to EP/l/N5000/E-0
Close INC-29, trip the reactor, trip all NC Pumps and go to
B.
C.
D.
EP/I/N5000/E-O
...........................................................................................
Distracter Analysis:.
A.
Incorrect:
Plausible:
B.
Incorrect:
Plausible:
C.
Correct:
Plausible:
D.
Incorrect
Plausible:
LEVEL: RO
KA: 000026 G2.4.47 (3.4/3.7)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Analysis
AUTHOR CWS
Ques-1063.doc
LESSON: OP-MC-AP-21
OBJECTIVES: OP-MC-AP-21 Obj 4
REFERENCES: OP-MC-AP-21 page 4
Bank Question: 1064
Answer: A
1 Pt
Given the following conditions on Unit 1:
Medium size LOCA has occurred with valid Ss, St and Sp signals
SI1 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 PROV/DED:
ES 1.f
A.
Restart S/I pumps and realign NV S/I flowpath as necessary to
restore subcooling and level, GO TO EP/lA/5000/E-I (Loss of
Reactor or Secondary Coolant).
Go to EP/l/A/5000/ES 1.2 (Post LOCA Cooldown and
Depressurization).
Go directly to EP/l/A/5000/ES-0.0 (Rediagnosis)
Reinitiate Safety Injection and GO TO EP/l/A/5000/E-O (Reactor
Trip or Safety Injection).
B.
C.
D.
____.________...____---------.----
Distracter Analysis:.
A.
Correct:
Plausible:
B.
Incorrect:
Plausible:
C.
Incorrect:
Plausible:
D.
Incorrect
Plausible:
LEVEL: RO
KA: WIE-2 EK2.2 (3513.9)
SOURCE: NEW
LEVEL OF KNOWLEDGE: ANALYSIS
Ques-1064.doc
AUTHOR: CWS
LESSON: OP-MC- EP-E-1
OBJECTIVES: OP-MC-EP-E-1 Obj. 4
REFERENCES: OP-MC-EP-E-1 pages 65 & 67
EP/1/N5000/ES-1 .I
Ques-1064.doc
Bank Question: 1066
Answer: C
1 Pt.
The SRO instructs the Unit 1 RO to adjust NC Pump seal leak off flow by
cooling the VCT. The potentiometer on 1 KC-I32 (Letdown Heat
Exchanger 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 pressure increases.
B.
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
Distracter Analysis:.
A.
Incorrect:
Plausible:
B.
Incorrect:
Plausible:
C.
Correct:
Plausible:
D.
Incorrect
Plausible:
LEVEL: RO
KA: SYS 008 A4.06 (2.5*/2.5)
Ques-1066.doc
SOURCE: NEW
LEVEL OF KNOWLEDGE: ANALYSIS
AUTHOR CWS
LESSON: -
OBJECTIVES:
REFERENCES: OP/1A/6200/001
B page 1 & 2
QuesJ066.doc
Bank Question: 1068
Answer: D
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
prompt operator action is required.
A Red path indicates the CSF is not satisfied and operator
action may be taken.
Heat Sink has a hiqher priority than Core Cooling due to
position on status trees.
A Red path indicates the CSF is under extreme challenge and
immediate operator action is required.
challenge and
B.
C.
D.
Distracter Analysis:.
A.
Incorrect:
Plausible:
B.
Incorrect:
Plausible:
C.
Incorrect:
Plausible:
D.
Correct Answer
Plausible:
LEVEL: RO
KA: G2.4.22 (3.0/4/0)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Memory
AUTHOR: CWS
LESSON: OP-MC- EP-INTRO
OBJECTIVES: OP-MC-EP-E-1 Objs. 1 & 3
Ques-lO68.doc
REFERENCES: OP-MC-EP-INTRO pages 21,27,29
Ques-1068.doc
Bank Question: 1069
Answer: B
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.
B.
Cooled down to P-12.
C.
C-7A not reset.
D.
Distracter Analysis:.
A.
B.
Correct:
C.
Incorrect: No effect
Potentiometer set too high on Steam Dump Controller.
Tave and Tref deviation is less than 3 degrees.
.______._______.____---------.-----
Incorrect: POT has no effect in manual steam dump control
Plausible:
Plausible:
Plausible: condition required to arm steam dumps when in Tave
mode
Plausible: On a load rejection must have greater than 3 degrees
for banks to start modulating
D.
Incorrect No effect
LEVEL: RO
KA: G 2.2.2 (3.5/3.9)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Memory
AUTHOR CWS
LESSON: OP-MC-STM-IDE
OBJECTIVES: OP-MC- STM-IDE Obj. 10
Ques-1069.doc
REFERENCES: OP-MC-STM-IDE pages 35-49 odd only
Ques-1069.doc
Bank Question: 1070
Answer: C
Given the following conditions on Unit 1:
1 Pt.
RN system is in normal alignment
RN pump 'B 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
6.
'B' RN pump
C.
RV pump in AUTO that starts on low non-essential header
pressure.
RV pump in AUTO that starts on safety injection signal.
D.
Distracter Analysis:. 1RN-42A closed on SII. Lose RN flow to non
essential headers. RV pump in AUTO will start on low non
essential header pressure. Operator needs to know SI1
alignment for RN and when RV pumps start to answer
question.
-_______I___________.___________._______-
A.
Incorrect:
Plausible:
6.
Incorrect:
Plausible:
C.
Correct:
Plausible:
D.
Incorrect
Plausible:
LEVEL: RO
KA: SYS 076 AI .02 (2.6*/2/6*)
SOURCE: NEW
LEVEL OF KNOWLEDGE:
Memory
AUTHOR CWS
Ques-1070.doc
LESSON: OP-MC- CNT-RV
OBJECTIVES: OP-MC-CNT-RV Obj. 10
REFERENCES: OP-MC-CNT-RV pages 13 & 25
OP/O/A/6400/009 Enclosure 4.1
OP-MC-PSS-RN page 75
Ques-1070.doc
Bank Question: 1074
Answer: D
1 Pt(s)
Unit 1 is in the process of releasing the Ventilation Unit Condensate Drain
Tank W C D T ) 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
SLC 16.11.2
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.
1EMF-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.
C.
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 lower limit of detection.
Distracter Analysis:
A.
Incorrect The hi rad alarms will not be received upon loss of
power supply.
Plausible: Some bistables and alarms fail on when power is lost or
detectors fail.
Incorrect The LOSS OF SAMPLE FLOW will alarm.
Plausible: There is an alarm for loss of sample flow, but there is not
an alarm for loss of power.
Incorrect: The hi rad alarms will not be received.
Plausible: Some hi rad alarms may be reset one time to reinitiate
the LWR without additional sampling or LWR paperwork.
B.
C.
D.
Correct:
Ques-lO74.doc
Level: RO
KA: SYS 073 A2.02 (2.7/3.2)
Lesson Plan Objective:
Source: New
Level of knowledge: comprehension
References:
1. lFUD2-F/2 Annunciator Response Procedure
2. SLC 16.11.2
Ques-1074.doc
Bank Question: 33. I
Answer: C
1 Pt.
Given the following conditions:
Unit 1 is in a refueling outage.
Fuel movement is in progress.
The Spent Fuel Pool Level Low computer alarm has actuated.
Initially IEMF 17 (SPENT FUEL BLDG. REFUEL. BRDG) was
reading radiation 7 mrem/hr.
After 20 minutes IEMF-17 is 18 mremlhr.
Which one (1) of the following describes the operator response to the
current conditions?
A.
Begin makeup to the pool from the Boric Acid Tank to restore
level.
Move the fuel transfer cart to the reactor side and close IKF-
122 (Fuel Transfer Tube Block Valve).
Move the fuel transfer cart to the spent fuel (pit) side and close
IKF-122 (Fuel Transfer Tube Block Valve).
Place the weir gate in position and inflate the seals.
B.
C.
D.
LEVEL:
SOURCE:
BANK
LEVEL OF KNOWLEDGE: Memory
REFERENCES:
OP-MC-FH-FC pages 19-25 odd only
LESSON:
OP-MC-FH-FC
OBJECTIVE:
OP-MC-FH-FC Obj. 6
W A 036 AA2.02 (3.4/4/1)
33.1 doc
Bank Question: 40.1
Answer: D
1 Pt.
Unit 1 is in mode 4.
Given the following conditions:
(1)
(2)
Which one (1) of the following situations meets the requirements for a one hour
Tech Spec LCO?
A.
Surveillance testing has been recently completed on the ice condenser
The surveillance test was not satisfactory as described below
The ice condenser door position monitoring system was declared
inoperable when one door did not indicate in the open position during
a surveillance test. The door was left in the open position.
The ice bed was declared inoperable when it was determined that it
failed a surveillance test based on total ice weight less than 2,099,790
pounds at a 95% level of confidence.
The Ice Bed Temperature Monitoring System was declared inoperable
when it failed a Tech Spec surveillance test - channel check failure.
The ice condenser intermediate deck door was declared inoperable
when it was discovered to be obstructed from opening by ice and
debris.
B.
C.
D.
LEVEL:
SOURCE:
BANK
REFERENCES:
LESSON:
OP-MC-CNT-NF
OBJECTIVE: OP-MC-CNT-NF Obj. 21
K/A
SYS 025 G2.2.22 (3.414.1)
LEVEL OF KNOWLEDGE: Memory
40.1 doc
Bank Question: 207.1
Answer: C
1 Pt.
Unit 1 is preparing for a reactor start up following a refueling outage. Given
the following conditions:
Tavg = 515°F
At 0200, a Station Engineer reports that a mistake had been made in
analyzing the containment Appendix J Leak Rate Test results that were
conducted prior to exceeding 200 "F in mode 5. Reanalysis indicated that
the combined containment leak rate (Type A) had exceeded 1 .O La.
Which one of the following actions are required by Tech Specs in response
to this situation?
Plant heatup in progress using NCPs
REFERENCES PROVIDED
Tech Spec 3.6.land Bases
A.
B.
C.
D.
Commence a plant cooldown to reach mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Commence a plant cooldown to reach mode 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
Commence a plant cooldown to reach mode 5 within 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />.
Commence a plant cooldown to reach mode 5 within 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />.
Distracter Analysis:
A.
Incorrect:
Plausible:
B.
Incorrect:
Plausible:
C.
Correct:
Plausible:
D.
Incorrect
Plausible:
SOURCE:
BANK
LEVEL:
LEVEL OF KNOWLEDGE: ANALYSIS
KA:
SYS 103 A2.01 (2.0*/2.6)
Ques-207.l.doc
OBJECTIVES: OP-MC-ADM-TS Obj. 2
REFERENCES: Tech Spec 3.6.1 and Bases
OP-MC-ADM-TS pages 29,3 1
Ques-207.1 .doc
Bank Question: 338.1
Answer: C
1 Pt
Which one of the following statements complies with the requirements of
OMP 4-3 (P/AP lmplemenfafion Guidelines) regarding the rules of usage
for abnormal procedures (APs) when the emergency procedures (EPs)
have been implemented?
A.
B.
APs may not be implemented when EPs have been entered.
Only one AP at a time may be implemented when EPs have
been implemented. Concurrent implementation of APs when
EPs are in use is not allowed.
APs may be implemented concurrently with EPs. However, the
APs were written assuming that SI has not actuated and
operators must be careful when using APs if SI has occurred.
APs may be implemented concurrently with EPs with the
exception of events where SI has actuated. APs were written
assuming the SI had not occurred and cannot be used if SI has
actuated.
C.
D.
Distracter Analysis:
A.
Incorrect: APs may be entered after EOPs have been started
Plausible: Many plants have this provision - symptomatic EOPs
should address all significant safety challenges without requiring
A P S
Incorrect: No limitation on the number of APs
Plausible: Makes sense to limit the number of concurrent
procedures in use
C.
Correct answer
D.
Incorrect: No explicit prohibition against use of APs when SI has
actuated BUT there is a caution and the APs were written for the
situation where SI has NOT occurred.
Plausible: APs were written for the situation where SI has NOT
occurred.
B.
LEVEL: SRO
SOURCE: BANK
LEVEL OF KNOWLEDGE: Memory
KA: G2.4.5 (2.913.6)
Ques-338.l.doc
REFERENCE: OMP 4-3 pages 21 & 22
Ques-338.l.doc
Bank Question: 697.3
Answer: C
1 Pt.
Unit 2 is operating at 100% power. 21\\11-59 (Cold Leg Accumulator Check
Valve) begins to leak at 0200. Given the following accumulator indications:
-
Time
Level (%)
-
0200
-
0300
-
0400
-
0500
21 %
31 %
41 %
51%
Pressure (psig)
586
61 1
636
661
Boron (ppm)
2500
2490
2480
2470
When does the accumulator first exceed a limiting condition for operation?
REFERENCES PROVIDED:
Unit I Data Book curve 7.4
Unit 1 Cycle 16 COLR - page 24
A.
0200
B.
0300
C.
0400
D.
0500
Distracter Analysis: Tech Spec values for CLA parameters are:
Volume 2 6870 (12.3%) but I7342 gal (38.7%) -exceeded at 0400 (high)
Pressure 2 585 but I 639 psig - exceeded at 0400
Boron concentration 2 2475 ppm but 12875 ppm - exceeded at 0300
A.
B.
C.
D.
Incorrect Answer: nothing out of spec.
Incorrect: nothing out of spec
Plausible:
Correct: the LCO is first exceeded at 0400 on accumulator level
Plausible:
Incorrect: the LCO is first exceeded at 0400 on accumulator level
Plausible:
Level: SRO
KA: G2.1.25 (2.W3.1)
Lesson Plan Objective: ECC-CLA Obj. 7
Source: Bank
Ques-697.3.doc
Level of knowledge: comprehension
References:
1. OP-MC-ECC-CLA page 23
2. Tech Spec 3.5.1 -PROVIDED
3. Unit 1 Data Book Curve 7.4 - PROVIDED
4. Unit 1 Cycle 15 COLR - PROVIDED
Ques-697.3.doc
Bank Quesfion: 776. I
Answer: B
1 Pt.
Unit 1 was operating at 100% when a large break LOCA with loss of offsite
power occurs. One diesel generator fails to start. The operators are
entering E-I (Loss of Reactor or Secondary Coolant).
Given the following critical safety function status indications:
Core Cooling - RED
Subcriticality - GREEN
Containment - RED
Inventory - GREEN
Heat Sink - RED
Integrity - RED
Which one of the following describes the highest priority problem, and the
appropriate operator action?
A.
Integrity; Transition to FR-P.l, (Response to Imminent
Pressurized Thermal Shock).
Core cooling; Transition to FR-(2.1, (Response to Inadequate
Core Cooling).
Heat Sink; Transition to FR-H.l, (Response to Loss of
Secondary Heat Sink).
Containment; Transition to FR-Z.l, (Response to High
Containment Pressure).
B.
C.
D.
____._______________---.-------
Distracter Analysis:
A.
B.
Correct:
C.
D.
Incorrect: Core Cooling is the highest priority RED
Plausible:
Plausible:
Incorrect core cooling is the highest priority RED
Incorrect: core cooling is the highest priority RED
Plausible:.
Level: SRO
Lesson Plan Objective: EP-FO SEQ 2,3
Ques-776.l.doc
Source: Bank
Level of knowledge: Memory
References:
1. OP-MC-EP-FO pages 13,15
2. OMP 4-3 pages 15-16
Ques-776.l.doc
Bank Quesfion: 892.3
Answer: A
Unit 1 is operating at 100% power when the OAC registers a low spent fuel
pool level alarm. Given the following events and conditions:
Which one of the following statements correctly describes the corrective
action for this event?
A.
1 Pt.
The operators read -2.1 ft SFP level and stable on the main control
board.
The operating KF pump has tripped.
An NLO reports a large leak in the auxiliary building has stopped.
Normal SFP makeup is not available.
Implement AP/l/A/5500/41 (Loss of Spent Fuel Cooling or
Level), find and isolate the leak on the KF discharge piping.
Implement AP/l/A/5500/41 (Loss of Spent Fuel Cooling or
Level), find and isolate the leak on the KF suction piping.
Implement AFVl/A/5500/21 (Loss of KC or KC System Leakage),
and initiate assured makeup due a leak on the discharge
piping.
Implement AP/I/A/5500/21 (Loss of KC or KC System Leakage),
and initiate assured makeup due to a leak on the suction
piping.
6.
C.
D.
Distracter Analysis:
A.
Correct
B.
Incorrect: The leak is on the discharge piping.
Plausible: If the candidate confuses the piping immersion depth with
the suction pipes, which are at 4 feet.
Incorrect: KF leak not a KC leak
Plausible:.
Incorrect: Do not use the assured source, and the leak is on the
discharge piping.
Plausible:.
C.
D.
Level: SRO
KA: SYS 033 A2.02(2.7/3.0)
Lesson Plan Objective: OP-MC-FH-KF Obj. 4/5/14
Ques-892.3.doc
Source: BANK
Level of knowledge: Comprehension
References:
1. OP-MC-FH-KF pages 19,23,49
Ques-892.3.doc
Bank Question: 894.2
Answer: A
1 Pt.
Unit 2 is operating at 100 YO power. Given the following events and
conditions:
The Test Group Supervisor comes to you the Control Room SRO and
wants to perform valve stoke testing.
Which one of the following valves would you NOTallow testing?
B essential train components are in service.
A.
ORN-1 (LLl Supply fO RN)
B.
C.
D.
2RN-40A (Train A to Non- Ess Hdr /sol)
ORN-7A (Train 7A &2A SNSWP Supply)
2RN-64A (AB Non-Ess Return /sol)
_.______..____..____---.-.---------
Distracter Analysis:
A.
Correct:.
B.
Incorrect:.
Plausible:
C.
Incorrect: .
Plausible:.
D.
Incorrect:
Plausible:.
Level: SRO
KA: APE 062 AA2.0(2.9/3.6)
Lesson Plan Objective: PSS-RN Obj 7
Source: Bank
Level of knowledge: comprehension
References:
1.OP-MC-PSS-FWpages 23,41,73,85
2. OP-MC-PSS-KC page 39
Bank Question: 991.1
Answer: A
Which one of the following is a correct list of SAFETY LIMITS?
A.
B.
C.
D.
Distracter Analysis:
A.
Correct:.
Plausible:
B.
Incorrect:
Plausible:
C.
Incorrect:
D.
Incorrect:.
Plausible:
Level: SRO Only
KA: G2.1.10 (2.7/3.9)
Lesson Plan Objective: (None)
Source: New
1 Pt.
Thermal Power, RCS Highest Loop Tave and Pressurizer
Pressure.
Thermal Power, AFD, Pressurizer Pressure.
AFD, QPTR and Reactor Power.
Linear Heat Generation Rate, Thermal Power and QPTR.
...........................................................................................
Level of knowledge: memory
References:
l.TechSpec2.1.1
Ques-99l.l.doc
Bank Question: 1004.7
Answer: B
1 Pt.
Unit 1 has experienced a 50% load rejection which resulted in Control Bank
D Group 1 being greater than 12 steps misaligned from its associated
step counter. Tech Spec 3.1.4 Rod Control Group Alignment Limits states:
XI1 shutdown and control rods shall be OPERABLE; with all individual
indicated rod positions within12 steps of their group step counter demand
position!
Which one of the following is the bases for this Tech Spec?
A.
6.
C.
D.
Distracter Analysis:
A.
Incorrect:.
Plausible:
8.
Correct:
C.
Incorrect:
Plausible:
D.
Incorrect:.
Plausible:
Ensure SDM limits are maintained and QPTR is maintained
within limits.
Ensure power distribution and SDM limits are preserved.
Ensure QPTR is maintained within limits and rod alignments
are correct.
Ensure AFD is maintained and limit power distribution.
____________________-------
Level: SRO
KA: G2.2.25 (2.5/3.7)
Lesson Plan 0bjective:OP-MC-IC-IRX Obj. 14
Source: BANK
Level of knowledge: Memory
References:
1.T.S. 3.1.4 Bases
Ques-1004.l.doc
Bank Question: 1033
Answer: A
Unit 1 is operating at 100% power when the following occurs:
1 Pt.
LOCA outside containment
The leak can
be isolated
0
FWST level is 178
FWST has mruptured
Containment Sump Level is Normal
Which of the following procedures would be used to MITIGATE the event?
A. ECA-1 .I (Loss of Emergency Coolant Recirc)
B. ECA-1.2 (LOCA Outside Containment)
C. ES-I .2 (Post LOCA Cooldown and Depressurization)
D. ES-I .3 (Transfer to Cold Leg Recirc)
Distracter Analysis:
A.
Correct -
B.
Incorrect.
C.
Incorrect
D.
Incorrect
Level: SRO
KA: EPE WlEl1 EA2.1 (3.414.2)
Lesson Plan Objective: OP-MC-EP-E1 Obj. 6
Source: New
Level of knowledge: Analysis
Author: CWS
References:
1.OP-MC-EP-E1 page 157
2. ES 1.3 Transfer to Cold Leg Recirc.
Ques-1033.doc
Bank Question: 1035
Answer: D
1 Pt.
Given the following conditions:
Pressurizer Level Channel 1 is at 28% level
Pressurizer Level Channel 2 associated bistables are in the tripped
condition due to surveillance testing
Pressurizer Level Channel 3 fails high.
N-41 is 8%
N-42 is 10%
N-43 is 9%
N-44 is 9%
Impulse pressure channel 1 is 11 %
Impulse pressure channel 2 is 9%
No reactor trip has occurred
Which of the following describes the proper operator response?
A. Trip the reactor and enter E-0 (Reactor Trip or Safety hection)
B. Trip the reactor and enter FR-S.l (Response Nuclear Power
Generation/A TWS)
C. Do not trip the reactor because thermal power is less than P-7
D. Do not trip the reactor. Initiate unit shutdown.
_._____________._____II_____
Distracter Analysis:
A.
Incorrect: -This example is not a valid ATWS event. This is a
loss of reactor protection. Therefore you do not trip the
reactor.
Incorrect: This example is not a valid ATWS event. This is a
loss of reactor protection. Therefore you do not trip the
reactor.
Incorrect: Greater than P-7. Pzr Hi level trip is in effect
B.
C.
D.
Correct
Level: SRO
KA: APE 029 EA2.02 (4.214.4)
Lesson Plan Objective: OP-MC-IC-IPE Obj. 10 & 11
QuesJ035.doc
Source: New
Level of knowledge: Analysis
Author: CWS
References:
1. OP-MC-IC-IPE pages 47,79 & 81
2. OMP 4-3 page 9
Ques-1035.doc
Bank Question: 1037
Answer: D
Given the following conditions on Unit 1:
A steam leak has occurred on the main steam header
Unit 1 reactor has been tripped and safety injection has actuated
The MSlVs will not close
20 minutes into the event lowest loop NC Tcold is 305 degrees
Based on the above conditions which one of the following is the correct
procedure flowpath?
A.
1 Pt.
From E-0 Reactor Trip or Safety Injection GO TO FR-P.2
(Response to Anticipated Pressurized Thermal Shock)
From E-0 go directly to ECA 2.1, (Uncontrolled
Depressurization of all Steam Generators)
From E-0 GO TO FR-P.l, (Response to Imminent Pressurized
Thermal Shock)
From E-0 GO TO E-2, (Faulted Steam Generator Isolafion) and
then to ECA 2.1
B.
C.
D.
__.____.__.__.____..-----.----..-.---.
Distracter Analysis:
A.
Incorrect:
Plausible:
B.
Incorrect:
Plausible:
C.
Incorrect:
Plausible:
D.
Correct
Plausible:
LEVEL: SRO
KA: WIE12 EA2.1 (3.2/4.0)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Comprehension
AUTHOR: CWS
LESSON: OP-MC-EP-E2
Ques-1037.doc
OBJECTIVES: OP-MC-EP-E2 Obj 2,6
REFERENCES: OP-MC-EP-E2 pages 9,15 & 23
EP/I/N5000/F-O page 7
EP/I/A/5000/E.2 page 2
Ques-1037.doc
Bank Question: 1042
Answer: D
Given the following conditions on Unit 1 :
1 Pt.
Chemistry had confirmed two leaking fuel rods
A large break LOCA occurs
E-0 Reactor Trip or Safety lnjecfion is complete
ES-1.3 Transfer to Cold Leg Recirc is complete
E-I Loss of Reactor or Secondary Coolant is complete
ES-1.2 Post LOCA Cooldown and Depressurization is in effect.
All Red and Orange Paths have been addressed
IEMF 51A is reading 39FVHR
Pressurizer level is 0%
The SRO is currently considering implementing Yellow Path
procedures. Which one of the following describes proper procedure
implementation?
A.
Go to FR-1.3, (Response to Voids in the Reactor Vessel) and
exit ES-1.2
Stay in ES-1.2 and implement FR-1.3 concurrently
Go to FR-Z.3, (Response to High Containment Radiation Level)
and exit ES-1.2
Stay in ES-1.2 and implement FR-Z.3 concurrently
B.
C.
D.
.____._____.____..___________
Distracter Analysis:.
A.
B.
C.
Incorrect: ESI .2 is controlling procedure
D.
Correct
Incorrect: ESI .2 is the controlling procedure and not to be exited
Plausible:
Incorrect: FR-1-3 is a lower priority than FR-Z-3
Plausible:
Plausible:
Plausible:
LEVEL: SRO
KA: WIE16 EA2.1 (4.3/4.4)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Analysis
Ques-lO42.doc
AUTHOR CWS
LESSON: OP-MC-EP-FO
OBJECTIVES: OP-MC-EP-FO Obj 3
REFERENCES: OP-MC-EP-FO page 17
OMP 4-3 page 19
Ques-lO42.doc
Bank Question: 1053
Answer: A
~~~~
~
~
1 Pt(s)
Given the following conditions on Unit 1:
Mode3
Safety Injection has occurred
NC System is at 1700 psig and 450 degrees
In process of cooling down and depressurizing the NC System
NC Pressure going down in an uncontrolled manner
Containment pressure going up in uncontrolled manner
Which one of the following describes the proper procedures to mitigate the
above?
A.
Enter AP/35 (ECCS Actuation During Plant Shutdown) and then
go to E-0 (Reactor Trip or Safety Injection).
Enter E-0 and then go to AP/35
Enter AP/35 and then go to AP134 (Shutdown LOCA)
Enter E-0 and then go to E-I (Loss of Reactor or Secondary
Coolant).
B.
C.
. D.
Distracter Analysis:.
A.
Correct:
Plausible:
B.
Incorrect:
Plausible:
C.
Incorrect:
Plausible:
. D.
Incorrect
Plausible:
LEVEL: SRO
KA: 006 G 2.4.4 (4.014.3)
SOURCE: NEW
LEVEL OF KNOWLEDGE: ANALYSIS
AUTHOR: CWS
LESSON: - AP/1/5500/35 Background Document
Ques-1053.doc
OBJECTIVES: OP-MC-AP-35 Obj. 1
MC-AP-34 Obj. 1
AP/I/N5500/35 page 3
AP/34 Backdground Document page 2
REFERENCES: AP/1/5500/35 Background Document pages 2-4
Ques-1053.doc
Bank Question: 1054
Answer: C
1 Pt
Given the following conditions on Unit 1:
Unit 1 is at 100% power.
A,
B, and C VL AHU are running
A
and C VL AHUs have tripped and will not restart
Attempts to start D
VL AHU were unsuccessful
Average temperature in lower containment for past 365 days has
been 105 degrees.
Maintenance indicated it will take two days to repair the VL AHUs.
Containment lower compartment temperature is 126 degrees and
steady.
Which one (1) of the following describes the required Technical
Specification actions to address the high containment temperature?
Reference Provided Tech Spec 3.6.5
A.
B.
Reduce temperature to <I25 degrees in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
C.
Restore temperature to within limits in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
No action is required to address high containment
temperature.
Be in Mode 3 in 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />.
D.
_______________.____________
Distracter Analysis:.
A.
Incorrect:
Plausible:
B.
Incorrect:
Plausible:
C.
Correct:
Plausible:
D.
Incorrect
Plausible:
LEVEL: SRO
KA: SYS 022 G2.1.12 (2.9/4.0)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Analysis
AUTHOR CWS
LESSON: OP-MC-CNT-VUL
OBJECTIVES: OP-MC-CNT-VUL Obj. 11
REFERENCES: OP-MC-CNT-VUL pages 15 & 17
Ques-1054.doc
Bank Question: 1055
Answer: D
1 Pt.
Given the following conditions on Unit 1:
0
In Mode 5 cooling down for a refueling outage.
The '1 B ND pump tripped due to an electrical fault.
The '1A ND pump has been started per AP/I/A/5500/19 (Loss of
ND or ND System Leakage) Encl. 14 (Startup of ND Pumps)
NC temperature before the pump trip was 150 degrees
NC temperature has increased to 207 degrees.
AP/l/A/5500/19 (Loss of ND) is in effect
The SRO instructs the RO to cooldown to the pre-event temperature.
Which one (1) of the following describes the maximum cooldown rate and
minimum flow rate allowed to cooldown?
REFERENCES PROVlDED
AP/I/N5500/19 Encl 14
DATA BOOKEncl. 4.3, curve 1.6b
A.
Maximum cooldown rate of 50 degreeslhr and minimum flow
rate of 1500 gpm.
Maximum cooldown rate of 75 degreeslhr and minimum flow
rate of 1000 gpm
Maximum cooldown rate of 50 degreeslhr and minimum flow
rate of 2000 gpm.
Maximum cooldown rate of 75 degreeslhr and minimum flow
rate of 1500 gpm.
B.
C.
D.
Distracter Analysis:.
A.
Incorrect:
Plausible:
B.
Incorrect:
Plausible:
C.
Incorrect:
Plausible:
D.
Correct
Plausible:
LEVEL: SRO
KA: 000025 AA2.05 (3.1*/3.5*)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Analysis
AUTHOR: CWS
LESSON: OP-MC-AP-19
OBJECTIVES: OP-MC-AP-19 Obj 2
REFERENCES: AP-19 Background Document Enclosure 14
AP/IA/5500019 Enclosure 14 Provided
DATA Book Enclosure 4.3 Provided
Ques-1055.doc
SUMMARY FOR ENCLOSURE 14, STARTUP OF ND PUMPS
This enclosure attempts to get a ND Pump started under various potential plant conditions.
If a loss of VI has occurred, then numerous compensatory actions are needed and rather
than complicate this enclosure, a kickout is provided to a separate enclosure for that plant
condition.
A couple of system checks are performed prior to starting an ND train. ND-35 is check
closed to prevent an inadvertent inventory loss (may have been opened as a makeup
option). If open, an operator is dispatched to stand by so it can be closed prior to pump
start.
A step is provided to leave ND UD in service if the NC System is solid. The setpoint for
checking if NC solid is 96% Pzr level, which includes 4% instrument error. Note there still
may be some volume above just full indicated level (dome of Pzr), but that amount can't
be assumed to be available.
If SI has occurred then control of RN modulating valves is reestablished. Then direction is
provided to go the section of the enclosure to start the desired ND Pump.
In preparation for starting a ND Pump, the local pump discharge is setup 2 turns open to
prevent water hammer concerns. Pump support conditions are established (RN & KC)
and ND-35 is closed at this time, if required. ND suction from the loop is aligned, and ND
flow bypassing the ND Hx is aligned. The ND recirc valve is de-energized prior to starting
pump to prevent any air that may be in the ND Hx from returning to the pump suction.
Several precautions are taken on ND Pump startup addressing voiding concerns. If air
entrainment or voiding has occurred, a cue is provided to continue makeup as required,
considering void collapse may occur after pump start. Also, a check is made for
subcooling. If subcooling can't be restored, FW-27A is aligned open in conjunction with
the loop suction valves until after pump start. Once NC System subcooling restored
(should happen quickly with the cool FWST water mixed in), FW-27A is closed.
After the ND Pump is started, ND flow is carefully established using ND Pump discharge
valve and ND-34, and then flow through the ND Hx is carefully established to maintain NC
temperature (considering NC System cooldown limits). A cue is also provided to secure
"feed & bleed" when less than 2OO0F, if it had been established. Finally, a cue is provided
to flush the idle ND train if air entrainment may have occurred on it.
Ques-1055.doc
Bank Question: 1057
Answer: C
1 Pt.
As a result of thunderstorms Unit 2 has experienced a Loss of Offsite
Power and Reactor trip. E-0 (Reactor Trip or Safety injection) was
implemented and the crew has transitioned to ES-0.1 (Reactor Trip
Response).
The SRO asks the RO to check NC temperatures.
Which one (1) of the following would the RO use to describe the response
of the NC system?
A.
E.
C.
D.
NC Tave STABLE or trending to 557 degrees
NC T hots STABLE or trending to 553 degrees
NC T colds STABLE or trending to 557 degrees
NC Tave STABLE or trending to 553 degrees.
Distracter Analysis:. The reactor coolant pumps have tripped in this
scenario. Tave is only checked if the NC pumps are on. T hot
should be increasing initially on the establishment of natural
circulation. T colds will go to 557. 553 degrees is a common)$i
used number for steam dump P-12.
A.
Incorrect:
Plausible:
B.
Incorrect:
Plausible:
C.
Correct:
Plausible:
D.
Incorrect
Plausible:
LEVEL: SRO
KA: 00056 AA2.32 (4.3/4.3)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Comprehension
AUTHOR: CWS
LESSON: AP/O9 Background Document
Ques-1057.doc
OBJECTIVES:
REFERENCES: AP109 Background Document pages 3 & 4
EP/I/A/5000/ES-O. 1 page 3
Bank Question: 1058
Answer: B
~~
~
1 Pt.
Radwaste is in the process of releasing WGDT A.
1 EMF -36 L is
inoperable due to PM. Trip 2 is received on OEMF-50 (Waste Gas
Discharge). The gaseous waste release is secured as a result of IWG-160
closing. Radwaste calls the control room SRO and reports OEMF-50 has
been purged and is ready to reinitiate the release.
Which one (1) of the following describes the actions of the control room
SRO?
A.
The SRO can authorize up to two (2) restarts without
re-sampling.
The SRO has Radwaste terminate the release and existing
GWR paperwork, and generate new paperwork.
The SRO can authorize one (1) restart without re-sampling.
The SRO can authorize Radwaste to jumper control actions of
OEMFdO, restart release and take grab samples once per four
(4) hours during release.
B.
C.
D.
__.___________-_____-.---.-------
Distracter Analysis:.
A.
Incorrect: Would be correct if both EMF 36 and 50 were operable
Plausible:
B.
Correct:
Plausible:
C.
Incorrect:
Plausible:
D.
Incorrect
Plausible:
LEVEL: SRO
KA: 00060 G 2.3.8 (2.3/3.2)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Comprehension
AUTHOR CWS
LESSON: OP-MC-WE-RGR
OBJECTIVES: OP-MC-WE-RGR Obj 5
Ques-1058.doc
REFERENCES: OP-MC-WE-RGR page 13
Ques-1058.doc
Bank Question: 1060
Answer: C
1 Pt.
Given the following conditions on Unit 1:
0
SGTR in the 1A S/G
E-0 (Reactor Trip or Safety Injection) complete
E-3 (Steam Generator Tube Rupture) implemented.
Cooldown is secured due to operator exceeding Main Steam
Isolation set point.
Which one (1) of the following describes how the operator continues to
cooldown?
A.
Go to Bypass Interlock on steam dumps and continue
cooldown with steam dumps.
Reset Main Steam Isolation, open MSlVs and continue
cooldown with steam dumps.
Reset Main Steam Isolation and PORVs and continue
cooldown using PORVs in manual.
Reset Main Steam Isolation and PORVs and continue
cooldown using PORVs in automatic.
B.
C.
D.
_______.____________________
Distracter Analysis:.
A.
Incorrect:
Plausible:
B.
Incorrect:
Plausible:
C.
Correct:
Plausible:
D.
Incorrect
Plausible:
LEVEL: SRO
KA: 0041 G2.4.20 (3.3/4.0)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Memory
Ques-1060.doc
AUTHOR CWS
LESSON: OP-MC-EP-E3
OBJECTIVES: OP-MC-EP-E3 Obj 4
REFERENCES: OP-MC-EP-E3 pages 75,77,79
EP/IA/5500/E-3 page 19-21
Bank Question: 1065
Answer: B
1 Pt.
Given the following:
Both Units operating at 100% power.
A train RN is operating on both units.
Operations Test Group is performing 6
train RN valve stroke
timing.
SRO is instructed to evaluate the consequences of stroking ORN-
2840 (Train I B and 2B Discharge to RC)
Which one of the following describes the consequences of allowing the
technician to test this valve?
A.
B.
No consequences due to A Train RN running on both units.
Closing ORN-284B will isolate the RN non-essential header
return from Unit 2.
Closing ORN-284B will isolate the RN non-essential header
return from Unit 1.
Closing ORN-284B will isolate RV pump discharge.
C.
D.
Distracter Analysis:.
A.
Incorrect:
Plausible:
8.
Correct:
Plausible:
C.
Incorrect:
Plausible:
D.
Incorrect
Plausible:
__.___________.__________I__
LEVEL: SRO
KA: G 2.2.3 (3.113.3)
SOURCE: NEW
LEVEL OF KNOWLEDGE: comprehension
AUTHOR: CWS
LESSON: OP-MC- PSS-RN
OBJECTIVES: OP-MC-PSS.RN Obj. 8
REFERENCES: OP-MC-PSS-RN page 67
Ques-1065.doc
Bank Question: 1067
Answer: A
Which one of the following describes the bases for prioritizing Critical
Safety Functions (CSF)?
1 Pt.
A.
The CSFs are prioritized to address challenges to the
boundaries that protect the general public from exposure to
radiation.
The CSFs are prioritized to address design bases accidents
that are described in the USFAR.
The CSFs are prioritized to ensure the proper optimal
response procedure is implemented.
The CSFs are prioritized to address challenges to parameters
that would affect operation of Engineered Safeguard Features
equipment.
B.
C.
D.
__._._____._____._._-----.--.----..--
Distracter Analysis:.
A.
Correct:
Plausible:
B.
Incorrect:
Plausible:
C.
Incorrect:
Plausible:
D.
Incorrect
Plausible:
LEVEL: SRO
KA: G 2.4.22 (3/0/4.0)
SOURCE: NEW
LEVEL OF KNOWLEDGE: Memory
AUTHOR: CWS
LESSON: OP-MC- EP-INTRO
OBJECTIVES: OP-MC-EP-E-1 Obj. 1 & 3
REFERENCES: OP-MC-EP-INTRO pages 21,27,29
Ques-1067.doc
Bank Question: 1071
Answer: C
After Channel 1 7300 Process Control Cabinet Channel Operability Test
was completed the Unit 1 Pressurizer level master malhctions causing it to
demand full output while in automatic.
Which one of the following statements correctly describes the basis for the
McGuire limit on flow?
1 Pt(s)
A.
Letdown flow rates in excess of 135 gpm are limited to ensure
proper demineralizer operation and adhere to the design limits
of the letdown piping.
Letdown flow rates in excess of 120 gpm exceed the design limits
of the letdown orifice valves and induce resonance vibration.
Charging flow rates in excess of 100 gpm during normal
operation can induce vibration in the regenerative heat
exchanger tubes.
Charging flow rates between 65 gpm and 100 gpm total charging
flow will cause flashing in the regenerative heat exchanger.
B.
C.
D.
Distracter Analysis:
A.
Inorrect:
B.
Incorrect
Plausible
C.
Correct:
Plausible
D.
Incorrect
Plausible:
Level: SRO
KA: APE 028 AA2.09 (2.9/3.2)
Lesson Plan Objective: OP-MC-PS-IW Obj. 13
Source: New
Level of knowledge: comprehension
References:
1. OP-MC-PS-NV pages 81 & 83
Ques-lO7l.doc
Bank Question: 7072
Answer: A
As an SRO working on a Complex Maintenance Plan you are asked to
evaluate four possible work teams who must repair filter housing in a
1500 d e & radiation field.
Which one of the following work teams would maintain station ALARA?
A.
1 Pt(s)
A qualified male worker who has previously performed this
task. He can complete this job in 20 minutes. This worker has
exceeded his Alert level for exposure and will require a dose
extension.
Two male workers who are qualified to perform the task.
Together they can perform the task in 15 minutes. Both
workers have already accumulated 325 mRem this year.
A team of a female worker who is qualified to perform the task
and a male worker who needs to qualify to this task. The female
is a declared pregnant worker. The team will need 15 minutes to
complete the task. The female has no dose and the male worker
has 200 mRem for the year.
A team of a male and female both are qualified to the task but
will take 20 minutes to complete the task. Each has less than 100
mRem this year.
B.
C.
D.
____I_____________________________I_____--------_----------------------------------
Distracter Analysis:
5 A.
Correct 500mRtotal.
B.
Incorrect: 750 per mrem total
Plausible
C.
Incorrect: Declared pregnant worker.
Plausible:
D.
Incorrect: 1000 mrem total
Level: SRO
KA. G2.3.2 (2.5/2.9)
Lesson Plan Objective: RAD Rp Ojb. 135
Source: New
Level of knowledge: comprehension
Ques-lO72.doc
References:
1. OP-MC-RAD-RF' page 73
Ques-lO72.doc
Bank Question: 1073
Answer: A
1 Pt(s)
The following conditions exist on Unit 1:
Reactor power is 100%
1A CA Pump is running with 1CA-60A (1A CA Pump Disch to 1A S/G
Control) and 1CA-56 (1A CA Pump Disch to 1B S/G Control) closed
for post maintenance testing.
N R
level in IB S/G increases to 84% due to 1CF-23 (1B S/G Control
Valve) failing open.
Which one of the following statements correctly describes the response of
the CA system to the above conditions?
A.
1A CA Pump remains running
1B CA pump auto starts
ICA-60A and 1CA-56A fail open
ICA-44B (1B CA Pump Disch to 1C S/G Control) and 1CA-40B
(1B CA Pump to Disch to 1D S/G Control) do not reposition.
Depressing the MD CA Modulating Valve Reset Train A
pushbutton will cause 1CA-60A and 1CA-56A to close.
1A CA Pump remains running
1B CA pump auto starts
1CA-60A and 1CA-56A remain closed.
1CA-44B and ICA-40B fail closed.
Depressing the MD CA Modulating Valve Reset Train A
pushbutton will cause 1CA-60A and 1CA-56A to open
B.
C.
1A CA Pump trips
1B CA pump remains off
ICA-60A and 1CA-56A remain closed.
1CA-44B and 1CA-40B do not change position.
Depressing the MD CA Modulating Valve Reset Train A
pushbutton will cause 1CA-60A and 1CA-56A to open.
D.
1A CA Pump trips
1B CA Pump remains off
1CA-44B and 1CA-40B fail open.
Depressing the MD CA Modulating Valve Reset Train A
pushbutton will cause 1CA-60A and 1CA-56A to close.
Distracter Analysis:
A.
Correct: .
B.
Incorrect:
Plausible:.
C.
Incorrect:
Plausible
D.
Incorrect:
Plausible:.
Level: SRO
KA. APE 054 AA204 (4.2/4.3)
Lesson Plan Objective: CF-CA Obj. # 4,
OP-MC-ECC-ISE Obj. # 13)
Source: New
Level of knowledge: comprehension
References:
1. OP-MC-CF-CA page 13,
2. OP-MC-ECC-ISE page 33
Ques-1073.doc