ML030650584
| ML030650584 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/09/2002 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Keenan J Carolina Power & Light Co |
| References | |
| 50-324/03-301, 50-325/03-301 | |
| Download: ML030650584 (106) | |
See also: IR 05000325/2003301
Text
Final Submittal
BRUNSWICK EXAM
50-2003-301
50-325 & 50-324
FEBRUARY 10 - 14 & 19, 2003
Senior Operator Written Examination
ANSWER KEY REPORT
for FINAL SRO Test Brunswick 2003-301 Test Form: 0
iD Answers
201002A3.03 1 A
201002K402 1 A
202001A1.07 I C
202002K4.06 1 D
203000A 1.04 1 A
204000K1.06 1 A
204000K5.04 1 A
206000K5.08 1 A
209001K2.03 1 C
211000A3.08 1 D
212000K6.04 1 C
214000K4.01 1 D
215004 G2.2.1 1 C
215005A4.06 I D
216000K2.01 1 A
217000G2.1.28 1 A
217000K1.01 1 A
218000A4.02 I A
219000A2.03 1 A
223001A2.01 I A
223001G2.1.7 1 A
223002A3.02 1 C
223002K1.07 1 C 'fiji>
239001K3.16 1
239002A1.01 I
C
-B. ea
C
' + t'5
4-;
241000K6.05 1
245000A4.10 1 D
256000K2.01 1 C
259001A2.07 I B
261000K3.04 I B
262001A2.03 1 C
262001A4.05 1 A
263000K2.01 1 D
264000K4.05 1 D
264000K5.06 1 B
268000A1.01 1 -B-,J 9wýw
272000K1.02 1 D
288000A2.02 1 A
295001AK2.02 1 D
295002AK2.08 1 D
295002AK3.02 1 B
295003AK1.02 I B
295003G2.1.10 1 A
295004AA2.02 I A
295005AA1.05 I D
295006AA2.05 1 B
Monday, February 10, 2003 06:51:30 AM 1
ANSWER KEY REPORT
for FINAL SRO Test Brunswick 2003-301 Test Form: 0
Answers
- ...D
47 295006G2.2.20 1 A
48 295007AK3.06 1 C
49 295008AK3.04 1 C
50 295009AK1.05 2 A
51 295009G2.4.1 1 B
52 295010AA1.01 2 A
53 295010AA2.06 1 B
54 295012AA1.02 1 C
55 295013AA2.02 1 A
56 295013AK1.03 1 D
57 295014AA2.03 1 A
58 295014AK2.03 1 A
59 295015AKI.02 1 C
60 295016AK3.01 I C
61 295017G2.1.2 1 A
62 295019AA1.01 I C
63 295020AA2.06 1 C
64 295021AA2.01 1 B
65 295021AK2.01 1 C
66 295022G2.1.30 1 B
67 295023AA2.02 I C
68 295024EK3.01 1 A
69 295025EA1.02 1 B
70 295025G2.4.4 1 C
71 295026EK2.04 1 C
72 295028EK1.01 1 C
73 295030EA1.05 1 C
74
75
295031G2.1.1 1
295032EK3.01 I
D
C
A
A
76 295033G2.3.10 I
77 295034EK1.02 I DkA 0.r
A
78 295037EK2.05 1
79 295038EA2.03 1 D
80 300000K3.02 I C
81 400000G2.2.18 1 A
82 500000EA2.01 1 C
83 600000AA2.06 1 B
84 GEN 2.1.1 1 C
85 GEN 2.1.102 A
86 GEN 2.1.12 1 B
87 GEN 2.1.28 1 C
88 GEN 2.2.14 1 C
89 GEN 2.2.17 1 D
90 GEN 2.2.27 1 A
91 GEN 2.2.3 1 D
92 GEN 2.3.1 1 C
2
Monday, February 10, 2003 06:51:30 AM
ANSWER KEY REPORT
for FINAL SRO Test Brunswick 2003-301 Test Form: 0
- mI Answers
93 GEN 2.3.4 1 C
94 GEN 2.4.1 1 B
95 GEN 2.4.112 A
96 GEN 2.4.18 1 A
97 GEN 2.4.2 1 B
98 GEN 2.4.27 2 D
99 GEN 2.4.3 1 A
100 GEN 2.4.48 1 D
SECTION 1 ( 100 items) 100.00
Monday, February 10, 2003 06:51:31 AM 3
U.S. Nuclear Regulatory Commission
Site-Specific
Written Examination
Applicant Information
Name: - -Region: II
Date: 02/19/03 Facility/Unit: Brunswick
License Level: SRO Reactor Type: GE
Start Time: Finish Time:
Instructions
Use the answer sheets provided to document your answers. Staple this cover sheet on
top of the answer sheets. The passing grade requires a final grade of at least 80.00
percent. Examination papers will be collected six hours after the examination starts.
Applicant Certification
All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature
Results
Examination Value: Points
Applicant's Score: Points
Applicant's Grade: Percent
Brunswick 2003-301
SRO Inital Exam
1.
During a reactor startup, Control Rod 34-39 is selected to be NOTCHED OUT from
Position 10 to Position 12. The RWM Withdraw Limit is Position 16.
After initiating ROD OUT NOTCH Sequence, the Operator observes:
Full Core Display white select light for Control Rod 34-39 is OFF.
4-Rod Display indicates Control Rod 34-39 STOPPING at Position 14.
Control Rod Select Matrix Backlighting is UNCHANGED
Rod Drift alarm is sealed in
Which ONE of the following has occurred?
A. The RMCS Timer has failed.
B. The RPIS Reed Switch at Position 12 has failed.
C. UPS supply breaker to rod select power has tripped.
D. RWM is enforcing a Withdraw Block.
Brunswick 2003-301
SRO Inital Exam
2.
Which ONE of the following describes the conditions under which the "Rod Select
Permissive" light is illuminated?
A. REFUEL only and indicates all control rods are fully inserted; rod select power is Off
or rod select power is On with no rod selected.
B. REFUEL only and indicates all control rods are fully inserted except for the selected
rod; rod select power is On with only one rod selected.
C. SHUTDOWN or REFUEL and indicates all control rods are fully inserted; rod select
power is Off or rod select power is On with no rod selected.
D. SHUTDOWN or REFUEL and indicates all control rods are fully inserted except for
the selected rod; rod select power is On with only one rod selected.
Brunswick 2003-301
SRO Inital Exam
3.
Unit Two was 95% power when annunciator A-07 2-2, REACTOR WATER LEVEL
HIGH/LOW, alarmed. Feed pump "B" Flow Controller is in manual following erratic
operation in automatic. Plant conditions are:
Reactor power 83% lowering
Reactor water level +180 inches rising
-Fedwatet Flow A 5.3 Mlbs/hr
-- eedwate+ Flow B 0.9 Mlbs/hr
Recirc Pump A Speed 63% lowering
Recirc Pump B Speed 70% lowering
Core Flow 59 Mlbs/hr lowering
Which ONE of the following describe the actions that should be taken?
A. Lock the scoop tube for the 'A' Recirc pump; monitor for Thermal Hydraulic
Instabilities.
B. Lock the scoop tubes of both recirc pumps and then monitor for Thermal Hydraulic
Instabilities.
C. After level is restored, adjust recirc pump potentiometers to match demand and
speed, and reset runback.
D. Take manual control of recirc pump speeds and ensure that a mismatch of greater
than 10% does not occur.
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Brunswick 2003-301
SRO Inital Exam
4.
Unit Two (2) is in Mode 1, in an active LCO for Recirculation Pump 2A out of service.
Preparations are in progress to restart Recirculation Pump 2A per OP-02, Reactor
Recirculation System OperatingProcedure. The following data is recorded within 30
minutes of the planned start of Recirculation Pump 2A:
Reactor pressure 985 psig
Bottom head drain temp 41OF
Recirc loop A temp 486°F
Recirc loop B temp 522 0 F
Recirc loop B flow 25,800 gpm
Which ONE of the following is correct concerning the restart of Recirculation Pump
2A?
A. It may continue, all requirements are met.
B. It may NOT continue, the Delta T between the operating and the idle loop is
excessive.
C. It may NOT continue, the Delta T between the coolant in the dome and bottom
head is excessive.
D. It may NOT continue, the operating Recirc loop flow rate is excessive.
Brunswick 2003-301
SRO Inital Exam
5.
Unit 2 was at 100% RTP when a small break LOCA concurrent with a loss of all high
pressure makeup capability to the reactor occured. The Reactor is being
depressurized using the SRVs due to level not being able to be maintained above TAF.
All RHR and Core Spray pumps have started as required with normal indications.
Reactor pressure is approximately 400 psig at this time.
Concerning the "A" RHR system only, which ONE of the following describes the
expected sytem parameters and configuration?
A. Both LPCI "A" injection valves OPEN, "A"system flow indicates 0 gpm, "A" and "C"
RHR Pump discharge pressures are approximately 200 psig.
B. Both LPCI injection valves CLOSED, "A"system flow indicates 0 gpm, "A"and "C"
RHR Pump discharge pressures are approximately 200 psig.
C. Both LPCI "A" injection valves OPEN, "A" system flow indicates 12,000 gpm, "A"
and "C" Pump discharge pressures are approximately 400 psig.
D. Both LPCI "A"injection valves CLOSED, "A"system flow indicates 2300 gpm, "A"
and "C" RHR Pump discharge pressures are approximately 200 psig.
Brunswick 2003-301
SRO Inital Exam
6.
Following a reactor scram the Reactor operator attempts to place the RWCU in the
reject mode of operation to aid in level control. Following the valve manipulation you
note that: valve G31-F004 has closed, and the inboard isolation valve G31 -F001 is
opened and you have lost condenser vacuum.
Which ONE of the following could have caused the above?
A. BOTH the Reject to Condenser Valve, F034 AND the Reject to Radwaste Valve,
G31-F035 were opened simultaneously and there was a non-regenerative heat
exchanger high temperature signal.
B. BOTH the Reject to Condenser Valve, F034 AND the Reject to Radwaste Valve,
G31-F035 were closed simultaneously and there was a non-regenerative heat
exchanger high temperature signal.
C. BOTH the Reject to Condenser Valve, F034 AND the Reject to Radwaste Valve,
G31 -F035 were opened simultaneously and there was a Local SLC pump start
signal.
D. BOTH the Reject to Condenser Valve, F034 AND the Reject to Radwaste Valve,
G31-F035 were closed simultaneously and there was a Local SLC pump start
signal.
Brunswick 2003-301
SRO Inital Exam
7. Unit 2
is at 10% power with RWCU filter demin in service and RWCU
reject flow in
progress.
Which ONE of the following is correct concerning the PPC heat balance if Process
Computer Point B074, RWCU Inlet Flow, is NOT available?
The PPC heat balance will be:
A. up to 3 CMWT lower than actual reactor power because computer points only get
input from RWCU filter demin flow.
B. up to 6 CMWT lower than actual reactor power because computer points only get
input from RWCU temperature.
C. up to 3 CMWT higher than actual reactor power because computer points only get
input from RWCU filter demin flow.
get
D. up to 6 CMWT higher than actual reactor power because computer points only
input from RWCU temperature.
Brunswick 2003-301
SRO Inital Exam
8.
Which ONE of the following components prevents water from being forced up the HPCI
exhaust line as the suppression pool pressurizes during a LOCA?
A. HPCI exhaust line vacuum breakers.
B. HPCI exhaust line T-quencher.
C. HPCI exhaust isolation valve.
D. HPCI exhaust drain pot.
Brunswick 2003-301
SRO Inital Exam
9.
With Unit 1 operating at rated conditions and Unit 2 at 75% power, Unit 2 annunciator
A3 2-6, CORE SPRAY SYS 2 LOGIC PWR FAILURE, is received. Investigation
reveals a tripped circuit breaker in Panel 4B which powers CORE SPRAY SYS 2
LOGIC.
Which ONE of the following describes the effect this has on a subsequent Unit 2 LOCA
initiation?
A. DIV II Emergency diesel generators will not auto start.
B. DIV II Non Interruptible RNA isolation valve will not isolate and DIV IIN2 BU
isolation valve will not open.
C. Drywell coolers B and C will not trip.
D. DIV II RHR pumps will not auto start.
Brunswick 2003-301
SRO Inital Exam
10.
Which ONE of the following contains a correct list of indications that are used to verify
the Standby Liquid Control System is operating properly once the system has been
initiated? (Not necessarily all the indications)
A. Squib valve loss of continuity alarm annunciated, storage tank level decreasing,
discharge pressure slightly lower than reactor pressure.
B. Red light indicating pump is running, reactor water level will increase, squib valve
status lights are illuminated.
C. Storage tank level decreasing, RWCU suction valve G31-F004 opens, squib valve
status lights are extinguished.
D. Indicated SLC pump discharge pressure will increase to greater than reactor
pressure, squib valve status lights are extinguished, RWCU suction valve G31-F004
closes.
Brunswick 2003-301
SRO Inital Exam
11.
Unit two is operating at 100% power when there is a loss of 125 VDC distribution panel
4B on the Unit 2 Reactor Protection System.
Which ONE of the following describes the direct effect of this loss on the RPS?
A. All ARI valves fail open, venting the scram air header.
B. Outboard ARI valves fail open, venting the scram air header through the inboard
ARI bypass check valves.
C. Both backup scram valves remain as is, scram air header remains pressurized.
D. Upstream backup scram valve fails open, venting the scram air header through the
downstream backup scram valves bypass check valve.
Brunswick 2003-301
SRO Inital Exam
12. Which ONE
of the following explains why a "ROD DRIFT" alarm is received after
moving a control rod using the "EMERGENCY IN"switch?
A. "EMERGENCY IN"bypasses the Rod Position Indication System.
B. The sequence timer is bypassed causing an insert and withdraw signal at the same
time.
C. The rod is at an even reed switch and none of the selected relay busses are
energized (insert, withdraw or settle).
D. The rod is at an odd reed switch and none of the selected relay busses are
energized (insert, withdraw or settle).
Brunswick 2003-301
SRO Inital Exam
13.
Unit 1 is in the process of performing OGP-01, PrestartupChecklist step 6.2.9, Source
Range Monitor Checks.
Which ONE of the following describes the minimum requirements for the SRM's?
A. Ensure at least 2 SRM channels are OPERABLE and indicate > 5 cps.
B. Ensure at least 2 SRM channels are OPERABLE and indicate > 10 cps.
C. Ensure at least 3 SRM channels are OPERABLE and indicate > 5 cps.
D. Ensure at least 3 SRM channels are OPERABLE and indicate > 10 cps.
Brunswick 2003-301
SRO Inital Exam
14. Unit 1 is in Mode 2 with the Mode Switch in START/HOT STBY. Annunciator APP
A-05 2-2, ROD OUT BLOCK, is in alarm. APRM readings are as follows:
APRM 1 13%
APRM 2 Downscale
APRM 3 15%
APRM 4 14%
and
Which ONE of the following describes the effect on the plant for these conditions
the reason for the response?
APRM 3 at
A. A scram should have occurred due to APRM 2 being Downscale and
the Upscale Trip setpoint.
3 at the
B. A 1/2 scram should have occurred on RPS Channel A due to APRM
Upscale Trip setpoint.
2 being
C. A 1/2 scram should have occurred on RPS Channel B due to APRM
downscale.
to the position of
D. The ROD OUT BLOCK alarm is the only expected actuation due
the Mode Switch.
Brunswick 2003-301
SRO Inital Exam
15.
If the Topaz Inverter in Analog Trip Cabinet XU-68 (RPS B-2) had an open circuit and
failed, then which ONE of the following should occur?
A. There will be no interruption of power to cabinet XU-68 as the power supply in
XU-67 (RPS B-i) will provide power to both cabinets.
B. There will be no interruption of power to cabinet XU-68 as there is a second Topaz
Inverter in panel XU-68 that is in parallel with the Topaz Inverter that failed.
C. All associated instruments will lose power generating a trip signal. There will be a
1/2 scram and Group 1 PCIS as well as valve actuation for PCIS Groups 2, 6 and 8.
D. All associated instruments will lose power but will not generate any trip signals. The
plant will continue to operate, but Tech Specs should be addressed for each
instrument.
Brunswick 2003-301
SRO Inital Exam
16.
Which ONE of the following is correct concerning the RCIC Steam Supply Inboard
Isolation Valve (E51-F007)?
A. AC powered due to less likely to spark during operation and more reliable in a
hostile environment.
B. DC powered due to less likely to spark during operation and more reliable in a
hostile environment.
C. Cannot be powered from an Alternate Safe Shutdown Feeder since the valve is
normally in the Open position.
D. May be throttled closed or open if isolation signal is not present to slowly warm the
RCIC steam line.
Brunswick 2003-301
SRO Inital Exam
17.
Unit 2 is operating at 80% RTP. The RCIC system is in standby with a suction from the
CST. The quarterly HPCI flow rate test is in progress and is taking longer than
expected. Torus level has reached -24" and preparations are being made to pump the
torus down to normal level within the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Tech Spec time limit.
Which ONE of the following describes the effect high Torus level had on RCIC?
A. No effect since the RCIC suction valves do not transfer on high torus level.
B. The Torus suction valves (F029 & F031) received an open signal and once both
valves were full open then the CST suction valve (F010) received a closed signal.
C. The Torus suction valves (F029 & F031) received an open signal at the same time
the CST suction valve (F010) received a closed signal.
D. The CST suction valve (F010) received a closed signal and when it was full closed
then the Torus suction valves (F029 & F031) received an open signal.
Brunswick 2003-301
SRO Inital Exam
18. Unit Two just entered a shutdown LCO due to HPCI and RCIC being inop, when a
Loss of Off-site Power occurs. EDGs 3 and 4 tail to start. unit une u}uses r an
aI
remain energized throughout the event. Pressure is being maintained 800 - 1000 psig
+25 on the
using SRVs. Level has been below 45 inches for 5 minutes and is currently
N026's.
of the following describes how ADS
Assuming ADS was NOT inhibited, which ONE
would respond to #4 EDG starting?
7 ADS valves would auto open - seconds after the diesel tied to E4.
A. 10
B. 15
C. 83
D. 93
Brunswick 2003-301
SRO Inital Exam
19. Unit Two
is in RHR/LPCI suppression pool cooling mode with an elevated suppression
pool temperature of 180 OF. The VITAL Service Water Header supply valve was
inadvertantly closed. The valve was manually opened 10 minutes later.
Which ONE of the following occurred before the valve was reopened?
A. ONLY RHR Pump Seal temperatures increased.
B. ONLY RHR SW Pump Motor temperatures increased.
C. BOTH RHR Pump Seal temperatures and RHR SW Pump Motor temperatures
increased.
D. NEITHER RHR Pump Seal temperatures NOR RHR SW Pump Motor
temperatures all have increased.
Brunswick 2003-301
SRO Inital Exam
20.
Following a LOCA, Unit Two has been Emergency Depressurized during a high power
ATWS and all control rods are now fully inserted. Injection with the only available
injection systems (2A Core Spray, and B Loop RHR) has been maximized to raise RPV
level and adequate core cooling is assured.
Plant conditions are:
Torus Pressure 19 psig, slowly lowering
Torus Level -5.5 feet, slowly lowering
Torus Water Temp., 220 OF, steady
Drywell Avg. Temp. 287 OF, lowering
Reactor Level -35 ", rapidly rising
Reactor Pressure 50 psig
Operating
The operating crew should do which ONE of the following per Emergency
Procedures?
A. Continue with maximum injection until above the top of active fuel.
B. Secure the B Loop of RHR and continue to raise level with the 2A Core
Spray Pump.
C. Reduce injection flow from Core Spray to maintain the minimum containment
cooling requirements.
D. Secure the 2A Core Spray Pump and continue to raise level with the B Loop of
RHR.
Brunswick 2003-301
SRO Inital Exam
21. Unit
2 was in an extended shutdown. A startup has been conducted and reactor
power
is at 47%. A position indicator for one of the Suppression Chamber-to-Drywell Vacuum
Breakers indicates that the vacuum breaker is OPEN. Alternate vacuum breaker
position indication is not available.
Which ONE of the following statements is correct?
A. Continued operation is allowed as long as the other vacuum breakers indicate
closed and the containment differential pressure test is proven acceptable within 4
hours.
B. Begin a normal reactor shutdown within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Be in HOT SHUTDOWN within
the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Initiate repairs to the vacuum breaker to restore the breaker to
operation prior to restart.
C. Immediately begin a plant shutdown and cooldown. Be in HOT SHUTDOWN within
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Initiate repairs to
restore the vacuum breaker to operation.
D. Initiate a manual reactor scram. Conduct a drywell entry to initiate repairs to the
vacuum breaker as soon as possible. If repairs are not completed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />,
place the plant in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Brunswick 2003-301
SRO Inital Exam
22.
An Instrument Tech mistakenly throttles the bypass valves on an MSIV's hydraulic
dash pot.
Which ONE of the following describes the effect of this manipulation?
It will result in a change in:
A. closing torque.
B. packing leakage.
C. closing time.
D. closing setpoint.
Brunswick 2003-301
SRO Inital Exam
23.
U-2 RCIC System is running with the following conditions present 10 minutes after the
event:
Reactor Water Level -38 inches
Drywell Pressure +1.5 psig
Suppression Chamber Ambient Temp. 170OF
RCIC Steam Line pressure 900 psig
RCIC Room Ambient Temp 100OF and rising slowly
An operator has been sent to the RCIC room and reports that there is a small steam
leak on the line upstream of the Trip and Throttle valve. The Shift Supervisor orders
the Reactor Operator to manually isolate RCIC.
Which ONE of the following describes the effect on RCIC when the manual isolation
pushbutton is depressed?
A. Inboard and Outboard Steam Supply Isolation valves F007 and F008 close and the
B. Inboard Steam Supply Isolation valve F007 closes and the RCIC turbine trips.
C. Outboard Steam Supply Isolation valve F008 closes and the RCIC turbine trips.
D. No effect on RCIC since the system should already be isolated.
Brunswick 2003-301
SRO Inital Exam
24.
Unit 1 was operating at 100%, when a loss of EHC caused a turbine trip without
bypass valves. SRVs operated as required, and pressure crested at 1142 psig.
Disregarding the setpoint drift tolerance, which ONE of the following indicates how
many SRVs opened in response to the pressure transient?
A. 4
B. 7
C. 8
D. 11
Brunswick 2003-301
SRO Inital Exam
25.
During an overpressure transient, an operator has opened an SRV to control pressure.
RPV pressure is 1005 psig.
Which ONE of the following is the expected tail pipe temperature for the SRV that is
open, as indicated on ERFIS?
A. 212 OF
B. 300 OF
C. 350 OF
D. 545 OF
Brunswick 2003-301
SRO Inital Exam
26.
Unit 2 is holding load at 75% Reactor Power when the operator receives the "Turbine
Vacuum Low" alarm.
Which ONE of the following describes the expected sequence of actions as condenser
vacuum continues to decrease from 24.7" Hg Vac (alarm setpoint) to 0" Hg Vac?
A. 1st - Main Turbine trips.
2nd - Main Turbine Bypass Valves close.
3rd - MSIV's close.
B. 1st - MSIV's close.
2nd - Main Turbine trips.
3rd - Main Turbine Bypass Valves close.
C. 1st - Main Turbine trips.
2nd - MSIV's close.
3rd - Main Turbine Bypass Valves close.
D. 1st - Main Turbine Bypass Valves close.
2nd - MSIV's close.
3rd - Main Turbine trips.
Brunswick 2003-301
SRO Inital Exam
27.
Assume the Unit 2 Main Generator is operating with the following conditions:
- 800 MWe
- 400 MVARS out
- 60 psig Hydrogen Pressure
To facilitate an on-line adjustment to the Hydrogen Sealing system the Hydrogen
pressure is lowered to 48 psig.
Which ONE of the following describes the effect on the Main Generator?
A. Main Generator operation will be unaffected.
B. Main Generator armature will begin to overheat.
C. Main Generator armature core end will begin to overheat.
D. Main Generator field windings will begin to overheat.
Brunswick 2003-301
SRO Inital Exam
The following annunciators are
Unit One and Unit Two are operating at 100% power.
received on Unit One.
UA-13 3-9 SAT Fault Pressure
UA-13 1-9 SAT Lockout
Transfer Pump(s) will have
Which ONE of the following describes which Condensate
power?
A. Unit One only.
B. Unit Two only.
C. Both Unit One and Unit Two.
D. Neither Unit One nor Unit Two.
Brunswick 2003-301
SRO Inital Exam
29. Unit
One is at 100% power with Feedwater level control (FWLC)
in 3 ELEM and the
Reactor Water Level Select Switch in LEVEL A (NO04A).
Which ONE of the following describes how the DFWLC system will respond to the B
level instrument (NO04B) failing high?
A. Transfer to 1 ELEMENT and utilize the C level instrument (NO04C) for
level control.
B. Remain in 3 ELEMENT control and continue utilizing the A level
instrument (NO04A) for level control.
C. Transfer to 1 ELEMENT control and continue utilizing the A level
instrument (NO04A) for level control.
D. Remain in 3 ELEMENT and utilize the C level instrument (NO04C) for
level control.
Brunswick 2003-301
SRO Inital Exam
Brunswick 2003-301
SRO Inital Exam
31.
The following conditions exist on Unit 2:
Reactor Power 50%
Stator Water Coolant Pumps A/B De-energized 3 minutes ago
Rapid power reduction In-progress for 3 minutes
Generator output 400 MWe
Stator amps 9800 A
Turbine Bypass Valves CLOSED
Which ONE of the following describes how the plant would respond if all four of the
Unit 2 incoming 230 KV lines were suddenly lost?
A. A turbine trip due to failure to meet runback criteria, and a reactor scram.
B. A generator load reject will occur but the reactor will stay on line.
C. A generator load reject causes a TCV fast closure and a reactor scram.
D. A TCV fast closure causes an APRM setdown and an SRI initiation, but the reactor
will stay on line.
Brunswick 2003-301
SRO Inital Exam
32.
Unit One is operating at 100% and the following annunciators are received:
GEN LOSS OF EXC (UA-13 3-1)
VOLT BALANCE RELAY A OPERATION (UA-23 6-6)
GENERATOR AUTO TRIP TO MANUAL (UA-13 1-4)
Which ONE of the following describes the plant response to these conditions?
A. The generator remains on line and the voltage regulator will maintain generator field
voltage constant.
B. A generator lockout is received with a turbine trip. Four EDGs AUTO start and a
reactor scram occurs.
C. The generator remains on line. The voltage regulator will maintain generator
terminal voltage constant.
D. A generator lockout is received with a turbine trip. No EDGs AUTO start and a
reactor scram occurs.
Brunswick 2003-301
SRO Inital Exam
Brunswick 2003-301
SRO Inital Exam
34.
During an ATWS on Unit Two (2), RPV level is being controlled at Top of Active Fuel
(TAF).
Actions to terminate and prevent RHR injection have been completed. A fault on Bus
2C results in LOSS of Bus E4.
Which ONE of the following describe the RHR pump response as DG4 re-energizes
bus E4?
A. RHR pumps 2B and 2D both remain overridden off.
B. RHR pumps 2B and 2D both restart 10 seconds later.
C. RHR pump 2D restartsl0 seconds later, RHR pump 2B remains off.
D. RHR pump 2B restarts 10 seconds later, RHR pump 2D remains off.
Brunswick 2003-301
SRO Inital Exam
35.
Unit 2 experiences a Loss of Off-Site Power (LOOP) with EDG #4 under clearance.
Which ONE of the following describes how the Nuclear Service Water (NSW) and
Conventional Service Water (CSW) pumps will respond as EDG #3 output breaker
closes and energizes bus E3?
A. NSW pump 2A and CSW pump 2A start immediately.
B. NSW pump 2A starts immediately and CSW pump 2A does not start.
C. NSW pump 2A and CSW pump 2A start after a 5 second time delay.
D. NSW pump 2A starts after a 5 second time delay and CSW pump 2A does not
start.
Brunswick 2003-301
SRO Inital Exam
36.
During a radwaste discharge to the Unit One weir, a Radwaste Effluent RAD Hi Hi
alarm annunciates. Which one of the following describe the actions, if any, that must
be taken if you desire to close both Unit's Radwaste Discharge valves (D12-V27A and
D12-V27B) and the Radwaste Flow Control valve (G16-FCV-189)?
A. Valves D12-V27A, D12-V27B, and G16-FCV-189 must be closed manually, no
auto signal.
B. Valves D12-V27A and D12-V27B receive a close signal. Valve FCV-189 must be
manually closed, no auto signal.
C. Valve FCV-189 receives a close signal. D12-V27A and D12-V27B must be
manually closed, no auto signal.
D. No actions required, all three valves receive a close signal.
Brunswick 2003-301
SRO Inital Exam
37.
During Unit One operation at 100% power, the control operator is performing
OPT-04.1.7, Main Condenser Air Ejector Radiation Monitor Functional Test. The
backpanel operator places the "A"Steam Jet Air Ejector (SJAE) rad monitor NUMAC
drawer (D12-RM-K601A) "INOP/OPER" keylock switch to the "INOP" position.
Which one of the following is the expected plant response?
A. AOG bypass valve, HCV-102, immediately closes ONLY.
B. AOG bypass valve, HCV-1 02, immediately closes AND main condenser vacuum
begins to degrade.
C. PROCESS OFFGAS RAD MONITOR DOWNSCALE/INOP alarm is received and
the process offgas timer initiates.
D. PROCESS OFFGAS RAD MONITOR DOWNSCALE/INOP alarm is received and
the process offgas timer does NOT initiate.
Brunswick 2003-301
SRO Inital Exam
38.
You are the Shift Supervisor on Unit 1. Following a LOCA, plant conditions are:
Reactor water level +200 inches
Drywell pressure 28 psig
Rx Bldg Vent Radiation 12 mR/hr
Primary Containment H2 0 2 Cannot be determined
You direct a containment purge using the CAD system. The CAC DIV I and DIV II
Isolation (Soft) Override Switches and the CAC Purge Vent Isolation (Hard) Override
Switch, CAC-CS-5519, are placed in OVERRIDE.
The CAC isolation valves that you directed opened earlier are still under override to
OPEN, but have closed automatically.
Which ONE of the following caused this to occur?
A. Reactor water level has dropped an additional 50 inches.
B. Main stack radiation has risen to the Hi-Hi setpoint.
C. Reactor Building ventilation radiation has increased by an additional 8 mR/hr.
D. Reactor Building ventilation exhaust temperature has risen to 140 OF.
Brunswick 2003-301
SRO Inital Exam
39.
Unit 2 is in single loop operation at 45% RTP. Preparations are being made to restart
the idle Recirculation Pump. The Control Operator reduces the operating Recirc Pump
speed so that core flow is less that 40% rated core flow prior to starting the idle Recirc
Pump.
Which ONE of the following describes the affect on the plant if this condition is
maintained for an extended period of time?
A. The operating recirc pump seals may be damaged due to operating at the lower
pump speed.
B. Thermal hydraulic instabilities may develop due to the increased natural circulation
at the lower core flow.
C. The bottom head temperature will increase due to increased natural circulation at
the lower core flow.
D. The idle loop temperature may decrease such that the 50 OF differential
temperature limit between the operating loop and idle loop is exceeded.
Brunswick 2003-301
SRO Inital Exam
40.
The reactor is at 30% power. Which ONE of the following describes the impact on
continued plant operation during a complete loss of the Conventional Service Water
system?
A. The plant should commence a shutdown immediately due to loss of cooling water to
all of the ECCS Room coolers.
B. The plant should commence a shutdown immediately due to loss of cooling to the
RBCCW Heat Exchangers.
C. The plant should reduce power as necessary to maintain equipment operating that
is supplied by TBCCW.
D. The reactor must be scrammed due to imminent loss of condenser vacuum.
Brunswick 2003-301
SRO Inital Exam
41.
Which ONE of the following describes why the Main Turbine automatically trips on
lowering condenser vacuum?
A. Lowering condenser vacuum decreases the NPSH to the condensate pumps and
the turbine is tripped to prevent a loss of feedwater to the reactor due to the
Condensate pumps tripping on low suction pressure.
B. Lowering condenser vacuum reduces the amount of energy that can be removed
from steam entering the turbine which causes increased dynamic loading on the
last stage blades and increases turbine vibration.
C. The turbine is tripped on lowering condenser vacuum to prevent a steam leak into
Secondary Containment due to a positive pressure occurring within the condenser
and rupturing the turbine casing overpressure discs.
D. The turbine is tripped on lowering condenser vacuum to prevent damage to the
turbine shaft due to increased torque from trying to push the steam through the
turbine.
Brunswick 2003-301
SRO Inital Exam
42.
A LOCA has occurred on Unit 1 which requires the El Emergency Bus to be supplied
by Diesel Generator #1.
Which ONE of the following describes the sequence of events that prevents the Diesel
Generator from being overloaded?
A. Bus El load shed occurs and then the following pumps start in the given order at 5
second intervals: RHR pump 1C, Core Spray pump 1A, NSW pump 1A.
B. Bus El load shed occurs and then the following pumps start in the given order at 5
second intervals: NSW pump 1A, RHR pump 1C, Core Spray pump 1A.
C. Bus El sheds all loads except RHR pump 1C and then the following pumps start in
the given order at 5 second intervals: Core Spray pump 1A and NSW pump 1A.
D. Bus El sheds all loads except Core Spray pump 1A and then the following pumps
start in the given order at 5 second intervals: RHR pump 1C and NSW pump 1A.
Brunswick 2003-301
SRO Inital Exam
43.
During a Station Blackout, RPV cooldown is in progress on the Blacked Out Unit with
the following RPV pressures recorded at the indicated times:
0100 540 psig
0115 420 psig
0130 300 psig
0145 210 psig
0200 150 psig
Per AOP-36.2, the cooldown rate is:
A. satisfactory but the cooldown must be stopped.
B. satisfactory and the cooldown should be continued.
C. too low and the coodown rate should be increased.
D. excessively high and the cooldown rate should be lowered.
Brunswick 2003-301
SRO Inital Exam
44.
The following conditions exist on Unit 1:
- HPCI system will not auto initiate, HPCI flow controller indication is lost.
- B logic is lost for the ADS system.
- RCIC will not trip on Hi water level and the inboard isolation logic is lost.
- Core Spray Loop A will not auto initiate.
- Inboard MSIV DC solenoids de-energize.
Which ONE of the following 125 VDC Distribution Panels was lost?
A. 3A.
B. 11A.
C. 1XDA.
D. 1XDB.
Brunswick 2003-301
SRO Inital Exam
45.
Unit 2 was operating at 100% RTP when the reactor scrammed due to a turbine trip.
In addition to the Turbine Stop Valves closing, which ONE of the following correctly
describes the remaining turbine valve response?
A. Turbine Control Valves - Closed
Intercept Valves - Closed
Intermediate Stop Valves - Open
Bypass Valves - One or more may be open depending on throttle
pressure
B. Turbine Control Valves - Open
Intercept Valves - Closed
Intermediate Stop Valves - Closed
Bypass Valves - All open initially; throttle closed to control Rx pressure.
C. Turbine Control Valves - Closed
Intercept Valves - Open
Intermediate Stop Valves - Closed
Bypass Valves - One or more may be open depending on throttle
pressure
D. Turbine Control Valves - Closed
Intercept Valves - Closed
Intermediate Stop Valves - Closed
Bypass Valves - All open initially; throttle closed to control Rx pressure.
Brunswick 2003-301
SRO Inital Exam
46.
The following conditions exist on Unit 2:
Reactor power 23%
Reactor water level 160 inches
Reactor pressure 980 psig
Drywell pressure 1.3 psig
Drywell temperature 145 OF
Reactor Bldg Vent Exhaust Rad Monitor 2.5 mR/hr
Main Steam Line Rad Monitor 1.3 times normal full power reading
Which ONE of the following indicates which EOP's should be entered at this time?
A. EOP-01-LPC, Level/Power Control;
EOP-03-SCCP, Secondary Containment Control Procedure.
B. EOP-01 -LPC, Level/Power Control ONLY.
C. EOP-01-RVCP, Reactor Vessel Control Procedure ONLY.
D. EOP-01 -RVCP, Reactor Vessel Control Procedure;
EOP-04-RRCP, Radioactivity Release Control Procedure.
Brunswick 2003-301
SRO Inital Exam
47.
Unit Two has inserted a manual Reactor scram due to lowering condenser vacuum.
Control rods failed to insert on the scram. Plant conditions:
Reactor power 31%
Steam flow 3.2 Mlbm/hr.
Reactor pressure 960 psig, controlled by EHC
Drywell pressure 0.6 psig
Mode Switch RUN
Main Turbine Tripped on low vacuum
The operator is performing LEP-02, Section 3 to reset and scram the Reactor.
Jumpers to bypass RPS trip signals have been requested but NOT yet installed.
Which ONE of the following would prevent the operator from resetting RPS prior to
jumper installation?
A. Scram discharge volume Hi Hi level RPS trip sealed in.
B. Turbine stop valves closed with reactor power above 30%.
C. Reactor water level is controlling at the setdown setpoint.
D. IRMs upscale Hi Hi due to being inserted but not ranged up.
Brunswick 2003-301
SRO Inital Exam
48.
Unit 2 is operating at 80% power when INBOARD MSIV B21 -F022A fails closed.
Which ONE of the following describes the effect on Reactor Pressure and Pressure
Averaging Manifold (PAM) Pressure after conditions stabilized, relative to the 80%
power?
A. Reactor pressure would have increased, and PAM Pressure would have increased.
,B. Reactor pressure would have remained the same, and PAM Pressure would have
increased.
C. Reactor pressure would have increased, and PAM Pressure would have remained
the same.
D. Reactor pressure would have remained the same, and PAM Pressure would have
remained the same.
Brunswick 2003-301
SRO Inital Exam
49.
Which ONE of the following is the reason the Reactor Feed Pumps are required by
Technical Specifications to automatically trip on high reactor water level?
A. Tripping the feedwater pumps prevents vessel level from exceeding the high level
trip setpoints for HPCI and RCIC only, so that they remain available if necessary.
B. Tripping the feedwater pumps prevent damage to the feedwater pump turbines by
limiting water addition to the vessel.
C. Tripping the feedwater pump turbines limits further vessel level increase thereby
terminating the overfeed event.
D. Tripping the feedwater pump turbines limits further vessel level increase and is the
only means of preventing water from entering the main turbine.
Brunswick 2003-301
SRO Inital Exam
Brunswick 2003-301
SRO Inital Exam
51.
Reactor water level has just dropped suddenly to 158 inches. Control rod position
indications are unavailable. APRMs are down scale and periods indicate -80 seconds.
Which one of the following describes correct EOP pathway(s) that must be executed?
A. Enter RSP then go to RVCP.
B. Enter RSP then go to L/PC.
C. Enter LUPC then go to RVCP and execute RC/L and RC/P concurrently.
D. Enter RVCP then execute LUPC, RC/L and RC/P concurrently.
Brunswick 2003-301
SRO Inital Exam
52.
The following conditions exist on Unit 1:
Drywell pressure 2.0 psig
Drywell temperature 180 OF
Reactor water level +55 inches
Reactor pressure 400 psig
Drywell Cooler Overide Switch position NORMAL
Which ONE of the following describes the condition of the Drywell Cooler fans?
A. All cooling fans are tripped.
B. Div I cooling fans tripped, Div II cooling fans running.
C. Div I cooling fans running, Div II cooling fans tripped.
D. All cooling fans running.
Brunswick 2003-301
SRO Inital Exam
53.
A DBA LOCA has occurred on Unit 2 and the following conditions exist:
Drywell Pressure 62 psig and increasing at 2 psig/min
Reactor Water Level -20 inches and increasing at 10 "min with RHR pumps
Average Drywell Temp 280 OF
PC Water Level 20 ft and increasing slowly
Which ONE of the following should be ordered by the Shift Supervisor?
A. Vent the Torus. Do not exceed ODCM limits for radiological release rates.
B. Vent the Drywell IRRESPECTIVE of offsite radiological release rates.
C. Spray the Drywell after verifying within Drywell Spray Initiation Limit.
D. Enter the Severe Accident Guidelines (SAG's).
Brunswick 2003-301
SRO Inital Exam
54.
Following a reactor scram, drywell temperature is 225 OF. Which ONE of the following
describes the position of the MIN/MAX control switch on Panel XU-3 for the Drywell
Lower Vent dampers, the reason it is in that position, and the actual damper position?
Assume NO operator actions:
A. MIN position so that the Reactor Building Closed Cooling Water system is not
overloaded. Dampers will actually be in the MIN position.
B. MAX position to minimize DP between the torus and the drywell. Dampers will
actually be in the MIN position.
C. MIN position to prevent extreme temperature excursions in the upper drywell
regions during normal operation. Dampers will actually be in the MAX position.
D. MAX position to maximize drywell cooling AND to distribute the air flow in all
portions of the drywell evenly. Dampers will actually be in the MAX position.
Brunswick 2003-301
SRO Inital Exam
55.
During Unit 1 operation at rated power, annunciator A-03 1-1, SAFETY OR DEPRESS
VLV LEAKING was received. SRV sonics indicate the valve is OPEN. A check of the
Suppression Pool parameters indicate an average temperature of 93 OF with a steady,
rising trend.
Which one of the following describe the actions that should be immediately taken?
A. Cycle the control switch of the affected SRV to OPEN and CLOSE/AUTO several
times while maintaining Suppression Pool temperature below 110 OF.
B. Commence a reactor shutdown per OGP-05 and perform an inspection of the
drywell and suppression pool in the area of the failed SRV prior to startup.
C. Manually scram the reactor and enter EOP-01 and OAOP-14.0 due to the
increasing Suppression Pool temperature from the stuck open SRV.
D. Commence a reactor shutdown per OGP-05 and place RHR Suppression Pool
Cooling in service as required.
Brunswick 2003-301
SRO Inital Exam
56.
Unit 1 has been operating at 75% RTP with a leaking Safety/Relief valve (the valve is
still OPERABLE). This has caused the local Suppression Pool temperature in the area
around the T-quencher to reach 111OF. The average Suppression Pool temperature is
steady at 93 0 F.
Which ONE of the following describes the effect, if any, on continued plant operation?
A. The Tech Spec limit for Suppression Pool average temperature has been
exceeded. Average temperature must be lowered to < 90 OF within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B. No TS limit has been exceeded. However, Supression Pool Cooling MUST be
placed in service to restore the T-quencher to < 110 OF.
C. The Suppression Pool temperature Tech Spec limit of 110 OF has been exceeded.
The reactor must be scrammed immediately.
D. No TS limit has been exceeded.
Brunswick 2003-301
SRO Inital Exam
57.
During a Unit 2 main turbine trip, reactor pressure peaked at 1145 psig and reactor
water level lowered to 125 inches. While responding to the transient, the reactor
operator reports both Reactor Recirculation pumps are running. He is directed to trip
both pumps. Which one of the following is the basis for these actions?
A. Add negative reactivity counteracting the positive reactivity addition resulting from
the pressure rise during the turbine trip ONLY.
B. Promote level swell in the reactor vessel counteracting the level shrink effects
caused by the turbine trip ONLY.
C. Add negative reactivity counteracting the positive reactivity addition resulting from
the pressure rise AND promote level swell in the reactor vessel counteracting the
level shrink effects caused by the turbine trip.
D. Protect the recirculation pumps from inadequate NPSH due to the level shrink
caused by the turbine trip.
Brunswick 2003-301
SRO Inital Exam
58.
Which ONE of the following describes the Abnormal Operating Occurances (Plant
Transients) which increase fuel temperature?
A. Recirc Flow Control Failure-Increasing Flow, Loss of Feedwater Heating,
Inadvertent start of HPCI.
B. Loss of Shutdown Cooling, Loss of Condenser Vacuum, Recirc Flow Control
Failure-Decreasing Flow.
C. Loss of Feedwater Heating, Trip of one Recirc Pump, Startup of idle Recirc Pump.
D. Recirc Flow Control Failure-Increasing Flow, Loss of Condenser Vacuum, Turbine
Trip with Bypass Valves available.
Brunswick 2003-301
SRO Inital Exam
59.
Which ONE of the following describes the reason a cooldown is NOT initiated prior to
the Cold Shutdown Boron Weight (CSBW) being injected during an ATWS condition?
A. The cooldown will cause an increase in reactor power which will require more boron
to be injected to maintain the reactor in an analyzed condition.
B. Initiating a cooldown while injecting boron is an uncontrolled reactivity manipulation
and it will prevent the boron from being uniformly mixed.
C. Core reactivity response is unpredictable in a partially borated core and subsequent
EOP steps may not provide the correct actions for such conditions.
D. Cooldown is not allowed at this time to ensure that low pressure injection systems
cannot inject into the vessel and add positive reactivity.
Brunswick 2003-301
SRO Inital Exam
60. A chlorine
tank car rupture has made the Control Room inaccessable. If possible,
prior
to leavincg the Control Room the Control Operator inserts a manual Scram per
OAOP-32.0, PLANT SHUTDOWN FROM OUTSIDE CONTROL ROOM.
Which ONE of the following describes why the procedure also has steps to Scram the
reactor by de-energizing the RPS EPA's?
A. The Technical Requirements Manual requires the capability to Scram the reactor
from outside the Control Room.
B. The Technical Specifications require that Reactor Scram capability from outside the
Control Room be maintained.
C. The FSAR requires the ability for prompt hot shutdown of the reactor from locations
outside the Control Room.
D. The capability for prompt hot shutdown of the reactor from outside the Control
Room is not required but is a safe operating practice.
Brunswick 2003-301
SRO Inital Exam
61.
Fuel bundles are being moved in the Unit 1 Fuel Pool when alarm UA-03 3-5,
HI-HI isr. received
RAD .Ar-,-,-, followed that an notes
a reportflnerator
Thobyflnntrnl
PROCESS
.
-. b.t_,j ,..^RX ...BLDG. VENT
k,,*,.' knan,- ond dt~m~ci
that the Reactor Building ventilation failed to isolate on Unit 1 and manual actions to
close the isolation valves have been unsuccessful. Radiation levels at the site
boundary have started to increase.
Which ONE of the following is an immediate operator action for these conditions per
OAOP-05.0, Radioactive Spills, High Radiation, High Airborne Activity?
A. Ensure the Control Room Emergency Ventilation System (CREVS) is in operation.
B. Notify E&RC to perform surveys, post the area and control access to the affected
area.
C. Evacuate unnecessary personnel from the affected area.
D. Stop all fuel movements.
Brunswick 2003-301
SRO Inital Exam
62. The Unit
2 Reactor Instrument Air Non-interruptible/Pneumatic Nitrogen
Supply
(RNA/PNS) header pressure has dropped to 70 psig.
MSIV's?
Which ONE of the following describes the effect this will have on the Inboard
SV-5481
A. The Inboard MSIV's will not be affected due to the Backup Nitrogen valves
and SV-5482 opening.
associated with
B. The Inboard MSIV's should not be affected due to the accumulators
the valve operators.
C. The Inboard MSIV's may start drifting closed due to a sustained low
pressure.
pressure drops
D. The Inboard MSIV's will close immediately after RNA/PNS header
below 80 psig.
Brunswick 2003-301
SRO Inital Exam
63.
A partial Group 2 isolation has just occurred on Unit 2.
Which ONE of the following conditions initiated the isolation?
A. Drywell pressure at 1.5 psig.
B. Reference leg leaks that lower reference leg pressure for Reactor Vessel Water
Level LL#1 transmitters, LT-NO17C-1 andLT-NO17D-1.
C. A variable leg leak that lowers variable leg pressure for Reactor Vessel Water Level
LL#1 transmitters, LT-NO17A- 1 and LT-NO17B-1.
D. Drywell temperature at 155 OF.
Brunswick 2003-301
SRO Inital Exam
64.
Which ONE of the following indications is used to monitor plant heatup/cooldown rate
while in Alternate Shutdown Cooling with the SRVs?
A. Recirculation loop suction line temperature.
B. Safety relief valve tailpipe temperature.
C. Steam dome pressure using steam table conversion.
D. The running ECCS pump local suction temperature.
Brunswick 2003-301
SRO Inital Exam
65.
Unit 1 is in Mode 4 with Shutdown Cooling established with the A Loop of RHR. Both
Recirc Pumps are out of service at this time. A spurious signal has caused a Group 8
isolation which cannot be reset. Reactor vessel water level has been raised to +210".
Which ONE of the following describes the the most accurate method for determing if a
Mode Change has occurred under these conditions?
A. Verifying that the bottom head temperature is less than 212 OF ensures the Unit has
not entered Mode 3.
B. Verifying that the recirc loop suction temperatures are less than 212 OF ensures the
Unit has not entered Mode 3.
C. Verifying an increasing trend in reactor pressure has not been established ensures
the Unit has not entered Mode 3.
D. Verifying reactor vessel level has been raised to > 200" ensures natural circulation
has been established and the Unit has not entered Mode 3.
Brunswick 2003-301
SRO Inital Exam
66.
The Unit 1 Control Operator is walking down his panels when he notices that the CRD
Flow Control Valve controller,C1 1-FC-R600 has failed such that the demand is 0 gpm.
Flow Control Valve Cl1 -FO02A was in automatic at 60 gpm prior to the failure.
Which ONE of the following describes how Flow Control Valve C1 1-FO02A can be
controlled under these conditions?
A. The Flow Control Valve will continue to operate at 60 gpm due to the local controller
taking over control automatically.
B. The Flow Control Valve will close until local controller C1 1-FK-DO09A is taken to
manual and adjusted as necessary.
C. The Flow Control Valve will fully open until local controller C1 1-FK-DO09A is taken
to manual and adjusted as necessary.
D. The Flow Control Valve will close and cannot be operated until controller
C1 1-FC-R600 is repaired.
Brunswick 2003-301
SRO Inital Exam
67.
Unit 2 is in Mode 5 with the fuel pool gates removed. Fuel Handlers are verifying the
Refueling Interlocks after maintenance on the refuel bridge. 2A Core Spray pump is
running for a flow rate surveillance when the operator inadvertently opens the Core
Spray Injection Valve F005B. (Assume F004B is open)
Which ONE of the following describes the effect on the plant under these conditions?
A. Fuel Pool water level will fill the skimmer surge tanks and cause the Fuel Pool
Cooling Pumps to trip on high level.
B. Reactor cavity water will drain to Radwaste through adjustable weirs located around
the cavity walls.
C. Fuel Pool water level will overflow into the Reactor Building Ventilation system.
D. Fuel Pool water level will rise to the high level alarm setpoint at which time the Fuel
Pool Cooling Pumps will trip.
Brunswick 2003-301
SRO Inital Exam
68. Which
ONE of the following describes why Drywell Sprays are not
initiated until
Suppression Chamber pressure reaches 11.5 psig?
A. This ensures that Suppression Chamber sprays are attempted before operation of
Drywell sprays.
B. This ensures that 100% of the non-condensibles are in the Suppression Chamber.
C. This prevents opening of the Suppression Chamber to Drywell vacuum breakers
when sprays are initiated.
D. This prevents opening of the Reactor Building to Suppression Chamber vacuum
breakers when Drywell sprays are initiated in a 100% steam atmosphere.
Brunswick 2003-301
SRO Inital Exam
69.
Unit 1 was operating at 80% RTP when a loss of feedwater heating occurred.
Which ONE of the following describes the effect on the main turbine controls provided
no operator action is taken?
PAM (Throttle) Pressure will and send a signal to the Control Valves to
A. increase, close
B. increase, open
C. decrease, close
D. decrease, open
Brunswick 2003-301
SRO Inital Exam
70.
Which ONE of the following conditions would require entry in the Emergency Operating
Procedures?
A. Unit 1 Reactor Water Level at +168 inches following a Reactor Feed Pump trip.
B. Unit 2 HPCI flow rate test in progress and Suppression Pool temperature at 102 OF.
C. Unit 1 Reactor Pressure at 1065 psig following a spurious Group 1 isolation.
D. Units 1 and 2 in Mode 4 with new fuel being moved into Unit 2 fuel pool and
Reactor Building pressure cannot be maintained negative.
Brunswick 2003-301
SRO Inital Exam
71.
Unit 2 is operating at 100% RTP. The HPCI system is currently running for an
OPERABLILTY flow test after maintenance has been performed. The Control
Operator notes that Suppression Pool temperature is 96 OF.
Which ONE of the following indicates the event status and the color code displayed by
the Safety System Parameter Display System (SPDS) with regards to the Suppression
Pool temperature?
Event Status = __ .; Color Code =
A. Safe; Green.
B. Caution; Yellow.
C. Alarm; Red.
D. Inactive; Cyan.
Brunswick 2003-301
SRO Inital Exam
72.
Unit 2 was operating at 100% RTP when a LOCA occurred. Water level is being
maintained above TAF with the HPCI system. The following conditions exist in the
Drywell:
Drywell pressure 8.0 psig
Suppression Chamber pressure 7.5 psig
Drywell temperature 275 OF
Reactor pressure 700 psig
Suppression Chamber sprays in progress
Which ONE of the following describes the effect on the indicated water level?
Assume the fuel zone level instrument reference leg piping height is longer than the
variable leg piping height in the Drywell.
A. Level indication will be reading lower than actual water level due to the reference
leg having more water in it.
B. Level indication will be reading lower than actual water level due to Drywell
temperature being above 212 OF.
C. Level indication will be reading higher than actual water level due to Drywell
temperature being above 212 OF.
D. Level indication will still read accurate level since the high Drywell temperature
affects both the reference and variable legs equally.
Brunswick 2003-301
SRO Inital Exam
73.
Unit 2 has developed an unisolable leak on the ECCS Suction header. Suppression
Pool level continues to lower.
Which ONE of the following corresponds to the minimum level at which the HPCI
System must be isolated irrespective of adequate core cooling?
A. -2 feet and 7 inches
B. -5 feet and 6 inches
C. -6 feet and 5 inches
D. -9.0 feet
Brunswick 2003-301
SRO Inital Exam
74.
Unit 2 experienced a scram due to the loss of the Reactor Feedwater Pumps. Reactor
water level initially dropped to +90 inches and has been restored to +150 inches and
increasing slowly. The following conditions are present at this time:
HPCI system currently injecting
RCIC system in Standy alignment
Secondary Containment isolated
SBGT system operating normally
Group 2 isolated
Group 3 RWCU system in operation
Group 6 isolated
Group 8 isolated
Which ONE of the following describes the actions that should be taken at this time?
A. Continue to monitor HPCI operation and restore reactor water level to the normal
band. RCIC operation is not required.
B. Start RCIC manually and then secure HPCI. Increase reactor water level to the
normal operating band. All required PCIS Group isolations have occurred.
C. Reset the Group 2 isolation immediately to prevent high drywell pressure and
continue to monitor HPCI while restoring reactor water level to the normal band.
D. Isolate the RWCU System, start RCIC manually, if possible, and continue to
monitor reactor water level to ensure the normal operating band is obtained.
Brunswick 2003-301
SRO Inital Exam
75. Secondary
Containment Control Procedure, EOP-03-SCCP, requires Emergency
Depressurization if 2 or more areas exceed the Maximum Safe Operating Temperature
and a primary system is discharging reactor coolant into secondary containment.
Which ONE of the following statements explain the reason for this action?
A. The rise in secondary containment parameters indicate a wide-spread problem
which may pose a potential threat to secondary containment integrity or preclude
personnel access required for the safe operation of the plant.
of
B. The rise in secondary containment parameters indicate substantial degredation
the primary system and may lead to fuel failure ifthe leaks are not isolated.
C. The rise in secondary containment parameters indicate a wide-spread problem or
which may pose a direct and immediate threat to secondary containment integrity
equipment located in secondary containment.
of
D. The rise in secondary containment parameters indicate substantial degredation
leak.
the primary system and emergency depressurization effectively isolates the
Brunswick 2003-301
SRO Inital Exam
76.
Unit 2 is operating at 50% RTP when alarm AREA RAD RX BLDG HIGH annunciates.
Upon investigation the operator notes that the alarm is received from the Spent Fuel
Cooling System (Channel 30) which is reading 95 mR/HR. Reactor Building Exhaust
Radiation levels are 2 mR/HR with the system unisolated. The Equipment Operator
reports that the Fuel Pool Heat Exchanger is leaking approximately 50 gpm from the
end bell.
Which ONE of the following describes the actions required for this situation?
A. Isolate all systems discharging into the area except those required to shutdown the
reactor, assure adequate core cooling, or suppress a fire.
B. Emergency Depressurize the reactor per the RC/P section of EOP-01.
C. Shutdown the reactor by manual scram or GP-05 as directed by the SRO.
D. Perform actions required by the Annunciator Response procedure since an entry
condition to the EOP's does not exist.
Brunswick 2003-301
SRO Inital Exam
77.
Unit 1 is operating at 100% RTP when a high radiation condition occurs in the Reactor
Building. The following conditions exist in the Reactor Building:
Reactor Buidling Supply and Exhaust Fans tripped
Both SBGT trains running
Reactor Building vent isolation dampers (BFIVs) open
Reactor Building Dp zero
Which ONE of the following describes the impact on the plant due to the above
conditions?
A. An elevated release of radioactivity from the main stack could occur.
B. A release of radioactivity outside containment will NOT occur due to both SBGT
trains running.
C. A release of radioactivity outside containment will NOT occur since the Reactor
Building Supply and Exhaust fans have tripped.
D. A ground level release of radioactivity could occur.
Brunswick 2003-301
SRO Inital Exam
78.
Unit 2 has scrammed due to low reactor water level. Multiple control rods did not insert
and the ATWS procedure is being directed by the Shift Supervisor. Current power
level following the ATWS is 12% RTP. The Shift Supervisor has ordered the RO to
insert control rods by increasing CRD cooling water differential pressure (dp).
Which ONE of the following describes how this action causes control rods to insert?
Increased cooling water dp:
A. puts additional pressure on the underside of the CRDM drive pistons.
B. puts additional pressure on the top of the CRDM drive pistons.
C. causes driving flow to increase.
D. causes driving flow to decrease.
Brunswick 2003-301
SRO Inital Exam
79.
Unit 2 is executing EOP-04, Radiation Release Control Procedure. During the release,
the radiation level has exceeded the ALERT Emergency level. The crew is directed to
restart the Turbine Building Air Filtration Unit. Which one of the following is the reason
for this action?
To ensure:
A. any release to the Turbine Building can be routed through Standby Gas Treatment.
B. any release to the Turbine Building is exhausted via an elevated release path.
C. that the integrity of the Turbine Building is maintained.
D. that accessibility to the Turbine Building is preserved.
Brunswick 2003-301
SRO Inital Exam
80.
A loss of the Interruptible Instrument Air System has just occurred.
Which ONE of the following describe how the Reactor Feed Pump (RFP) recirculation
valves and Startup Level Control Valve (SULCV) will be affected?
The RFP recirculation valves:
A. and the SULCV fail open.
B. and the SULCV fail closed.
C. fail open and the SULCV fails closed.
D. fail closed and the SULCV fails open.
Brunswick 2003-301
SRO Inital Exam
81.
Unit One is in shutdown. You are reviewing a proposed special test of a Circulating
Water Ocean Discharge (CWOD) Pump. The test has the Caswell Beach Local
Control Panel control switch placed in the STOP position. The next step requires that
an operator place the LOCAL/REMOTE control switch for the operating CWOD Pump
in the LOCAL position.
Which ONE of the following describes the consequences of this action?
This will initiate:
A. pump discharge valve closure with a pump trip when the discharge valve is less
than 50% open.
B. pump discharge valve closure with a pump trip when the discharge valve is less
than 90% open.
C. an immediate pump trip due to undervoltage but will NOT close pump the discharge
valve.
D. an immediate pump trip due to undervoltage and will close the pump discharge
valve.
Brunswick 2003-301
SRO Inital Exam
82.
Unit 1 experienced a LOCA with the following conditions present:
Drywell pressure 8.5 psig
Drywell temperature 255 OF
Reactor water level +100 inches
Hydrogen concentration Unknown
No operator action has been taken up to this point.
Which ONE of the following describes the method for monitoring containment
Hydrogen concentration in accordance with EOP-02-PCCP?
A. Notify E&RC to coordinate with Chemistry to obtain containment atmosphere
samples manually. Hydrogen monitors are isolated and cannot be overridden.
B. Place CAC Div 1/11 AC ISOL OVRD switches, CS-4178 and CS-4179, to the
Override position and re-open the CAM sample valves. Depress the "Sample Start"
pushbutton.
C. Place CAM Div 1/11 ISOL OVRD switches, CS-2986 and CS-3452, to the "ON"
position. Place associated valve control switches to "close" and then to "open".
Depress the "Sample Start" pushbutton.
D. The containment is not required to be sampled for Hydrogen concentration unless
reactor water level drops below Top of Active Fuel (TAF).
Brunswick 2003-301
SRO Inital Exam
83.
Which ONE of the following conditions will cause the Control Room ventilation system
to enter into Fire Protection mode?
A. Smoke detected in Unit 2 Electronic Equipment room.
B. Smoke detected in the Unit 1 Electronic Equipment room AND the manual pull
station tripped in the Unit 2 Electronic Equipment Room.
C. Manual pull station tripped in Unit 1 Electronic Equipment room.
D. Manual pull station tripped in Unit 2 Cable Spread room.
Brunswick 2003-301
SRO Inital Exam
84.
Ifoperating in the Scram Avoidance Region of the Flow Control Operational Map,
which one of the following will reduce the likelihood of an instability event?
A. Control rod withdrawal.
B. Reducing recirculation flow.
C. Increasing recirculation flow.
D. Removing a feedwater heater string from service.
Brunswick 2003-301
SRO Inital Exam
85.
Which ONE of the following changes in plant operating conditions will result in a higher
MCPR operating limit as specified in the COLR?
A. Operation at the end of cycle vs. the beginning of cycle.
B. Operation at 90% power vs. 100% power for a given core flow.
C. Operation at 100% core flow vs. 90% core flow for a given power.
D. Setting the mechanical stop of the Reactor Recirculation Pumps to a lower setpoint.
Brunswick 2003-301
SRO Inital Exam
86.
Unit 2 is operating at 14% power with the Drywell de-inerted for mechanical
maintenance to repack a valve. When exiting the Primary Containment Air Lock the
outer door was damaged such that the door cannot be closed at this time.
Which ONE of the following describes the actions that are required?
A. The Inner Air Lock door must be verified closed and locked. Be in MODE 3 within
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
B. The Inner Air Lock door must be verified closed and locked. Operation may
continue until the next overall airlock leakage test provided the operable door is
verified locked every 31 days.
C. Either door must be verified closed. Action must be initiated to verify overall
containment leakage immediately. The Primary Containment Air Lock door must be
restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. The Inner Air Lock door must be verified closed and locked. The outer door must
have a security guard posted or must be blocked to prevent entry. Repair the
inoperable door within 31 days or be in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Brunswick 2003-301
SRO Inital Exam
87.
Which ONE of the following describes why the plant must be placed in HOT
SHUTDOWN with an inoperable jet pump?
A. There is an increased possibility of thermal hydraulic instabilities outside the
defined region.
B. An inoperable jet pump is sufficient reason to declare the recirculation loop
C. Blowdown area is increased or reflood capability eliminated in the event of a DBA.
D. To prevent undue stress on the reactor vessel nozzles and in the bottom head
region.
Brunswick 2003-301
SRO Inital Exam
88. You are the SCO and have just given interim approval of a temporary procedure
change.
Which ONE of the following describes the expiration date?
The date shall not to exceed:
A. 14 days from the interim approval date.
B. 14 days from the procedure's periodic review date.
C. 4 months from the interim approval date.
D. 4 months from the procedure's periodic review date.
Brunswick 2003-301
SRO Inital Exam
89.
You are the Unit 2 SS. During movement of material through the HPCI Room,
insulation has been damaged. A repair crew has been assembled.
The wet-bulb temperature is 103.1 OF
The work requires single cotton Blend PCs.
The work will take 2 man hours.
You have 3 mechanics plus an HP available.
Assume that HP will not participate in the repairs and that the actual exposure time to
the hot environment is the actual stay time.
Using the recommended action times of OAI-107, which ONE of the following is the
shortest duration for this task?
A. 20 minutes
B. 35 minutes
C. 80 minutes
D. 100 minutes
Brunswick 2003-301
SRO Inital Exam
90.
You are the refueling floor SRO. Unit 1 is in refueling with all but four assemblies off
loaded.
Supplemental Spent Fuel Pool Cooling System is operating as follows:
Primary Pump P-74A and both heat exchangers are in service
Secondary pump P-82A and both cooling towers are in service
P-82A tripped due to a flexible coupling failure. Following the trip P-74A also tripped.
Which ONE of the following conditions must be satisfied prior to restarting P-74A?
A. Secondary loop pressure must be restored.
B. Primary pump seal water must be restored.
C. One heat exchanger must be taken out of service.
D. One fire pump must be started and aligned to the supplemental cooling header.
Brunswick 2003-301
SRO Inital Exam
91.
Which one of the following is a feature of Unit 1 only?
A. Select Rod Insert may be manually initiated by the operator at P603 by use of a
single pushbutton.
B. The fixed Scram point is setdown from 116% to 90%.
C. The EOC-RPT is manually bypassed via administratively controlled key switches on
P609 and P611.
D. When not in "Run" an IRM upscale will provide an RPS trip. There is no APRM
downscale RPS trip.
Brunswick 2003-301
SRO Inital Exam
Brunswick 2003-301
SRO Inital Exam
93.
You are the Site Emergency Coordinator. Following a LARGE Break LOCA you are
considering attempting to save a 4 Million Dollar test rig that is just inside the
containment access hatch. The task can be accomplished with a projected dose of
Which ONE of the following statements regarding this task is correct?
A. This exceeds the exposure limit listed in EPA 400 Emergency Work Limits to
protect valuable equipment.
B. While this exceeds the exposure limit listed in EPA 400 Emergency Work Limits to
protect valuable equipment you can authorize a single exposure for this purpose.
C. This does not exceed the exposure limit listed in EPA 400 Emergency Work Limits
to protect valuable equipment and you have the authority to grant permission for
this task.
D. This does not exceed the exposure limit listed in EPA 400 Emergency Work Limits
to protect valuable equipment. However, you do not have the authority to grant
permission for this task, it must be granted by the site VP or his designee.
Brunswick 2003-301
SRO Inital Exam
94.
Following an incomplete Reactor scram, the operating crew is executing EOP-01 -LPC,
Level/Power Control. A decision step is reached asking "Is The Reactor Shutdown?".
Which one of the following conditions would satisfy the definition of "SHUTDOWN" as
it applies to the Reactor?
A. All operable APRMs are downscale.
B. The Reactor is subcritical on range 6 of IRMs.
C. The entire SLC tank has been injected to the Reactor.
D. Hot Shutdown Boron Weight has been injected to the Reactor.
Brunswick 2003-301
SRO Inital Exam
95.
Unit heatup and pressurization is in progress per GP-02. Current plant conditions:
Reactor power Range 9 on IRM's
RPV pressure 750 psig
RPV water level 187 inches
The operating CRD Pump trips on overcurrent. The operator attempts to start the
standby CRD Pump, which fails to start.
Which ONE of the following describes why AOP-02.0 requires a manual scram if CRD
pressure cannot be restored?
A. Control rods may fail to fully insert on a reactor scram if the HCU accumulator
pressure is lost.
B. Control rods cannot be inserted by normal means in the event of a positive
reactivity addition.
C. Control rod drive temperatures will rise and may result in a measurable delay in
scram response time.
D. Recirculation pump seal temperatures will rise to the point requiring both
Recirculation pumps to be tripped.
Brunswick 2003-301
SRO Inital Exam
96.
Emergency Operating Procedure guidance is provided to trip the reactor recirculation
pumps during an ATWS condition.
Which ONE of the following is the basis for taking this action?
A. To rapidly reduce reactor power and potentially reduce the amount of heat that
would be added to the containment.
B. To avoid the area of thermal hydraulic instability.
C. To promote the dispersion of the boron from Standby Liquid Control System.
D. To decrease reactor pressure which increases CRD drive differential pressure.
Brunswick 2003-301
SRO Inital Exam
97.
During a Station Blackout on Unit One HPCI, RCIC and LPCI have all become
unavailable for injection to the RPV. Plant conditions:
RPV water level -55 inches (N036)
RPV pressure 300 psig
Drywell ref leg temp 315 OF
Injection sources None available
Which one of the following describes the current RPV water level?
A. Above the Minimum Steam Cooling Reactor Water Level, adequate core cooling is
assured.
B. Above the Minimum Zero-Injection Reactor Water Level, adequate core cooling is
assured.
C. Below the Minimum Steam Cooling Reactor Water Level, adequate core cooling is
NOT assured.
D. Below the Minimum Zero-Injection Reactor Water Level, adequate core cooling is
NOT assured.
Brunswick 2003-301
SRO Inital Exam
98.
A fire in the Control Building requires Control Room evacuation and entry into
ASSD-02.
ASSD-02 directs the Diesel Generator Operator to trip the Unit Two RPS MG Set
output breakers and open the DC supply breakers to Distribution Panels 4A and 4B.
Failure to perform this action could result in which ONE of the following?
A. misoperation of RCIC.
B. loss of drywell cooling.
C. inability to operate SRVs.
D. spurious operation of MSIVs.
Brunswick 2003-301
SRO Inital Exam
99.
Following a steam leak in the Unit Two Secondary Containment, a manual Reactor Scram has been inserted. Plant conditions:
RPV pressure 1000 psig
Drywell ref leg area temp 197 OF
Rx Bldg 50' temp 145 OF
Recirculation Pump Running
RPV water level +150" (N036/N037)
RPV water level +170" (N026A/B)
RPV water level +155" (NO04A/B/C)
RPV water level +160" (N027A/B)
RPV water level may be determined using which ONE of the following?
A. N004A/B/C only.
B. N004A/B/C and N026A/B only.
C. N004A/B/C and N027A/B only.
D. N004A/B/C and N036/N037 only.
Brunswick 2003-301
SRO Inital Exam
100.
Unit 1 is operating at 100% power. The unit receives a Group 6 isolation and did NOT
receive a Secondary Containment Isolation.
Which ONE of the following may have occurred?
A. High Drywell Pressure.
B. Rx Bldg Exhaust Radiation High.
C. Rx Vessel Water Level Low LL2.
D. Rx Vessel Water Level Low LL1.
Brunswick 2003 License Exam Answer Sheet Senior Reactor Operator
Name: Date:
26. 51. 76. A B C D
27. 52. 77. A B C D
28. 53. 78. A B C D
29. 54. 79. A B C D
30. 55. 80. A B C D
31. 56, 81. A B C D
32Z 57. 82. A B C D
33. 58. 83. A B C D
34. 59. 84. A B C D
35. 60, 85. A B C D
36. 61. 86. A B C D
37, 62Z 87, A B C D
38. A B C D 631 A B C D 88. A B C D
39. D 64. D 89.
40. D 65. D 90.
41. D 66. 91.
42. D 67. 92.
431 D 68. 93.
44. D 69. 94.
45. D 70. 95.
46. D 71. 96.
47. D 72. 97.
48. D 73. 98.
49, D 74. 99.
A B C D 50. A B C D 75. A B C D 100. A B C D