ML030650572
| ML030650572 | |
| 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: ML030650572 (130) | |
See also: IR 05000325/2003301
Text
Final Submittal
(Blue Paper)
Combined RO/SRO Written Exam with KAs,
Answers, References, and Analysis
BRUNSWICK EXAM
50-2003-301
50-325 & 50-324
FEBRUARY 10 - 13 & 19, 2003
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
1. 201001K1.01 001/T2G1//CONTROL ROD DRIVE/MEM 3.1/3.1/N/BSEP 2003/RITCK/R!C
Which ONE of the following is the normal supply to the suction of the CRD pumps?
A. Condensate System upstream of the deepbed demineralizers.
B. CST from the same line that supplies the HPCI system.
C. Condensate System downstream of the deepbed demineralizers.
D. CST from the same line that supplies the Core Spray systems.
Feedback
References: SD-08, CRD Hydraulic System, Rev.4, pg.1 1
A. Incorrect since the supply is from the Condensate System downstream of the
deepbed demineralizers.
B. Incorrect since the alternate supply is the CST from the same line as the Core Spray
systems.
C. Correct answer.
D. Incorrect since this is the alternate supply to the CRD pump suction.
S....
...
^
==,I
Thursday, March 06, 2003 10:23:33 AM
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
2. 201002A3.03 001/T2G1/T2G2/RMCS/C/A 3.2/3.2/B/BSEP 2003/C/LSM/R/C
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.
Feedback
93.
LOI-CLS-LP-O07-A*06B001
A. The symptoms listed are those of a Select Block initiated by the RMCS Backup 2
Second Timer. The key to the question is understanding that the 2 Second Timer has
timed out with the RMCS Solid State Timer still running. The 2 Second Timer
deselected the control rod in order to cause rod withdrawal motion to cease. This type
of deselection occurs with no alarms and causes the Full Core Display's White Light for
that particular control rod to go out. The Select Matrix will appear as though nothing is
wrong.
LESSON 2: LOI-CLS-LP-007-A
LESSON 2 OBJECTIVE: 10d
REFERENCES: SD-07*
2
Thursday, March 06, 2003 10:23:33 AM
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
3. 201002K3.01 00I/T2G1//RMCS/C/A 3.4/3.4/N/BSEP 2003/R/TCK/R/C
Which ONE of the following is the result of a total loss of 28 VDC from 120 VAC Vital
UPS to Unit 1?
A. Normal control rod movement is unavailable.
B. Automatic Depressurization System (ADS) will not actuate automatically.
C. The High Pressure Coolant Injection System will not actuate automatically.
D. All SRM's and IRM's would be inoperable.
Feedback
References: SD-07, Reactor Manual Control System, Rev.1, pg 10
SD-51, DC Distribution System, Rev.2, pg 51
A. Correct answer. The 28 VDC is powered from UPS and interupts power to the
select matrix.
B. Incorrect since 125 VDC is the power supply to ADS logic.
C. Incorrect since 125 VDC is the power supply to the HPCI System.
D. Incorret since 24/48 VDC is the power supply to the Nr's.
~
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ARA3
Thursday, Marcn 06, 2UU3 j1u:23:33 AvI
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
4. 201002K402 001/T2G1/T2G2/FUEL HANDLING/MEM 3.5/3.5/B/BSEP 2003/C/LSM/TCK/R/C
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.
Feedback
A. Per SD-07 Section 2.1.3; Rod Motion Inhibits: The Rod Select Permissive light will
be energized if all the following conditions exist:
All rods fully inserted
Mode Switch in REFUEL
Either rod select power on with no rods selected or rod select power off.
4
Thursday, March 06, 2003 10:23:33 AM
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
5. 201003A2.09 001/T2G2//CRD SYSTEM/C/A 3.2/3.4/N/BSEP 2003/R/TCK/R/C
Unit 2 ii in Mode 2 starting up after a refueling outage. The following conditions exist
at this time:
Reactor water level
normal band
Reactor power
Range 8 on all IRM's
Reactor pressure
700 psig
Reactor temperature
505 OF
2B CRD Pump
Out-of-service
Alarm APP A-05 3-1, CRD PUMP 2A LO SUCT PRESS annunciates and the 2A CRD
Pump has tripped. The operator is unable to restart the 2A CRD pump.
Which ONE of the following indicates the action that should be taken per OAOP-02.0,
Control Rod Malfunction/Misposition if unable to move control rods?
A. Monitor CRD temperatures and expedite repairs of the 2B CRD Pump so that it can
be started.
B. Insert a manual scram if any control rod starts to drift.
C. Trip both Recirc Pumps due to loss of seal purge.
DO. Insert a manual scram immediately.
Feedback
References: SD-08, CRD Hydraulic System, Rev.4 pg 41
AOP-02.0,Control Rod Malfunction/Misposition, Rev.1 1, pg 3
APP A-05 3-1, CRD PUMP 2A LO SUCT PRESS
A. Incorrect since you can't wait until the out-of-service pump is fixed.
B. Incorrect since you don't manually scram until more than 1 CRD drifts.
C. Incorrect since you can still run the Recirc pumps if you have seal cooling.
D. Correct answer.
Thursday, March 06, 2003 10:23:33 AM
5
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
6. 201003K3.01 001/T202//CONTROL ROD DRIVE/C/A 3.2/3.4/N/BSEP 2003/R/TCK/R}C
Feedback
References: SD-07, Reactor Manual Control System, Rev.1
A. Incorrect since an alarm doesn't exist for "uncoupled control rod".
B. Correct answer.
C. Control rod withdraw time will not change since needle valve position has not
changed.
D. Incorrect since the control rod is not being withdrawn to position 48.
Thursday, March 06, 2003 10:23:34 AM
Unit 1 is at 90% RTP and a central control rod needs to be withdrawn from position 00
to position 24. While withdrawing the control rod it becomes uncoupled and remains at
position 00.
Which ONE of the following conditions should alert the operator that the control rod is
uncoupled?
A. The operator receives a "CONTROL ROD UNCOUPLED" annunciator.
B" Reactor power is not increasing on the LPRM bar graphs displayed on the Rod
Block Monitors.
C. The control rod withdraw time will be noticeably faster while withdrawing the control
rod.
D. The operator will recieve a "ROD OVERTRAVEL." annunciator.
6
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
7. 201006G2.2.12 0O1/T2G2//ROD WORTH MINIMIZER/C/A 3.0/3.4/N/BSEP 2003/R/TCK/R/C
Which ONE of the following describes the plant conditions required to perform the Rod
Worth Minimizer Operability surveillance prior to startup?
A. Mode Switch in REFUEL with reactor in Mode 4.
B. Mode Switch in REFUEL with reactor in Mode 2.
C. Mode Switch in START/HOT STBY with reactor in Mode 2.
D. Mode Switch in START/HOT STBY with reactor in Mode 4.
Feedback
References: OGP-01, Prestartup Checklist, Rev.156
A. Incorrect since the Mode Switch must be in START/HOT STBY.
B. Incorrect since the Mode Switch must be in START/HOT STBY.
C. Correct answer.
D. Incorrect since the reactor is in Mode 2 with Mode Switch in START/HOT STBY
unless Reactor Mode Switch testing is in progress.
7
Thursday, March u0, 2uu0
1Iu:2J:34 Mi
SQUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
8. 202001A1.07 001/T2G2/T2G2/RECIRC SYSTEM/C/A 2.7/2.8/B/BSEP 2003/C/LSM/R/C
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
Feedwater Flow A
5.3 Mlbs/hr
Feedwater 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.o 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.
Feedback
REFERENCES: OP-02, S. 8.3, R. 75, AOP-23, SECT. 2.1, REV.3
QTRAK REF. NO: R281
45.LOI-CLS-LP-002-A*029001
8
Thursday, March 06, 2003 10:23:34 AM
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
9. 202002K4.06 001/T2G1/T2G1/RECIRC SYSTEM/C/A 3.1/3.1/M/BSEP 2003/C/LSM/TCK/R/C
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 Operating Procedure. The following data is recorded within 30
minutes of the planned start of Recirculation Pump 2A:
Reactor pressure
985 psig
Bottom head drain temp
410OF
Recirc loop A temp
4860F
Recirc loop B temp
522 0F
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.
Feedback
References: 20P-02 Rev. 110 pg 25
SD-02, Rev.5 pg 50
Enabling Objective CLS-LP-02 Rev.1 #22
A. Incorrect since the operating loop flow rate is too high. The limit for restart of the idle
Recirc Pump is 23,500 gpm.
B. Incorrect since the delta T between the loops is <500F.
C. Incorrect since the delta T between the dome and bottom head temperature is
<1450 F.
D. Correct answer since the operating loop flow rate is >23,500 gpm.
_.
.
..
.
A
9
Thursday, March U0, ZUU210 u:23:3q ,VI
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
10. 203000A1.04 001/T2G1/T2G1/RHR SYSTEMIC/A 3.6/3.3/N/BSEP 2003/C/LSM/TCKJR/C
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.
Feedback
References: SD-17, Residual Heat Removal System, Rev.4, pg.10 & 11
A. Correct answer since reactor pressure is < 410 psig.
B. Incorrect since the inboard injection valve auto opens and the outboard injection
valve is normally open.
C. Incorrect since there will be no flow indicated since reactor pressure is greater than
pump discharge pressure.
D. Incorrect since there should be no indicated flow since reactor pressure is greater
than pump discharge pressure. If the candidate doesn't know where the flow element
is located then he may believe that the flow would indicated flow through the min flow
valve.
~.~a~J
A*A10
Thursday, March 0J6, UU310 u:23:34 AM
-
QUESTIONS REPORT
-for-FINAL BSEP 2003-301 Written Exam
11. 204000K1.06 001/T2G2/T2G2/RX LEVEL/C/A 2.8/2.8/N/BSEP 2003/C/LSM/R/C
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.
Feedback
New derived from the questions below
55.
LOI-CLS-LP-01 2-A*04CO01
Which of the following signal(s) will cause the Group 3 PCIS RWCU outboard isolation
valve (G31--F004) to close, yet leaves the inboard isolation valve (G31-FO01) open?
A.
Local SLC pump start.
B.
RPV level at low level 2 on trip channel B2 only.
C.
Non-regenerative heat exchanger high temperature.
D.
Area ventilation temperature high on trip channels Al and A3.
C.
Answer:
C
99.
LOI-CLS-LP-014-A*09F0O2
Following a reactor scram the Reactor operator places RWCU in the reject mode of
S..
.
.
...
...
^o~o
^..11
Thursday, March 06, 20U3 1U:23:34 AM
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
operation to aid in level control. The operator is cautioned not to open the parallel paths to the
main condenser and radwaste to avoid:
A.
voiding of RWCU piping.
B.
C.
inadvertant RWCU isolation.
D.
high airborne activity in radwaste.
Answer:
B
100.
LOI-CLS-LP-014-A*09F003
While using Reactor Water Cleanup (RWCU) to reduce reactor vessel level, BOTH the
Reject to Condenser Valve, F034 AND the Reject to Radwaste Valve, F035 are inadvertently
opened simutaneously.
Plant conditions are:
Shutdown in progress
Which of the
A.
B.
C.
D.
RPV pressure 200 psig
MSIVs open
Condenser vacuum 26" Hg.
following would result from the established lineup?
RWCU Reject FCV, F033, closure on high pressure.
Reduced RWCU pressure and increased demineralizer delta-pressures.
RWCU Isolation on Non Regenerative Heat Exchanger high outlet temperature.
Answer:
A
12
Thursday, March 06, 2003 10:23:34 AM
QUESTIONS-REPORT
for-FINALBSEP 2003-301 Written Exam
12. 204000K5.04 OO1/T2G2/T2G2/RWCU/C/A 2.7/2.7/N/BSEP 2003/C/LSM/R/C
Unit 2 is at 10% power with RWCU filter demin in serviceand 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.
D. up to 6 CMWT higher than actual reactor power because computer points only get
input from RWCU temperature.
Feedback
BSEP REVIEWER ADD NOUN NAME FOR COMPUTER POINT B074
20P-14 Rev. 107 Page 11 of 148
5.1.2 Procedural Steps
CAUTION
IF Process Computer Points B074 or B075, or NUMAC LDM B21-XY-5949B is NOT
available, THEN the PPC heat balance may be up to 3 CMWT lower than actual reactor
power because computer points only get input from RWCU filter demin flow. Raising
reactor power to rated will exceed 2558 CMWT if either of the following exist:
-RWCU is in service with G31-F044 open.
-RWCU filter demin(s) is in service with RWCU reject flow in progress.
--.........
^.13
Thursday, March U0, 2UU310 u:23:o3
AMv
QUESTIONS REPORT
-for FI NAL-BSEP2003ý301-Written Exam
13. 205000A3.01 001/T2G2//SHUTDOWN COOL/C/A 3.2/3.1/N/BSEP 2003/R/TCK/R/C
Unit 2 is in Mode 3 in the process of shutting down for a refueling outage. The
following conditions are present at this time:
Reactor water level
190 inches
Reactor pressure
75 psig
Reactor coolant temperature
265 0 F
In service on A Loop (B Loop in stby)
A break occurs in the Drywell which causes Drywell pressure to increase to 4.5 psig
and Drywell temperature to increase to 2350 F. All automatic actions occur as
designed.
Which ONE of the following describes the automatic operation of the RHR System for
these conditions?
A loop RHR:
A. realigns for injection after one Shutdown Cooling suction valve closes; B loop RHR
aligns for injection immediately; Both loops inject at full flow.
B. remains aligned in Shutdown Cooling; B loop RHR aligns for injection immediately;
B loop RHR injects at full flow.
C. isolates Shutdown Cooling suction path with LPCI injection valve reopening after
going closed; B loop RHR aligns for injection immediately; B loop RHR injects at full
flow.
D. realigns for injection after one Shutdown Cooling suction valve closes; B loop RHR
remains in stby; A loop RHR injects at full flow.
Feedback
References: SD-17, Residual Heat Removal System, Rev.4, pg 56
A. Incorrect since A RHR loop does not inject since there is not a suction path for the
pumps.
B. Correct answer.
C. Incorrect since A RHR loop does not isolate in the Shutdown Cooling mode.
D. Incorrect since A RHR loop does not inject and B RHR loop aligns and injects.
14
Thursday, March 06, 20U3 lu0:3:354 AM
-QUESTIONS-REPORT
-forf INALBSEP 2003-301 -Written Exam
14. 206000K5.08 001/T2G1/T2G1/HPCI SYSTEM/MEM 3.0/3.2/N/BSEP 2003/C/TCK/R/C
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.
Feedback
References: SD-19, High Pressure Coolant Injection (HPCI) System, Rev.7
A. Correct answer.
B. Incorrect since a t-quencher does not prevent water from going back up into a line.
C. Incorrect since the exhaust isolation valve doesn't prevent backflow.
D. Incorrect since the exhaust drain pot doesn't prevent water from going back into the
exhaust line.
15
Thursday, March 06, 2003 10:23:35 AM
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
15. 209001K2.03 001/T2GI/T2GI/CORE SPRAY/C/A 2.9/3.I/B/BSEP 2003/C/LSM/R/C
Feedback
BSEP BANK 132. LOI-CLS-LP-018-A*15FO03
Thursday, March 06, 2003 10:23:35 AM
16
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 II N2 BU
isolation valve will not open.
C< Drywell coolers B and C will not trip.
D. DIV II RHR pumps will not auto start.
QUESTIONS REPORT
-for-FINAL-BSEP 2003-301 Written Exam
16. 21 1000A3.08 001/T231!T2G1/SBLC/MEM 4.2.4.2/B/BSEP 2003/C/LSM/TCK/R
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.
Feedback
References: SD-05 Rev.3 pg 23, Standby Liquid Control System
A. Incorrect since discharge pressure should be higher than reactor pressure.
B. Incorrect since reactor water level increasing is not an indication that SBLC is
injecting. Also, neutron level should be decreasing.
C. Incorrect since storage tank level should decrease.
D. Correct answer.
17
Thursday, March 0U, 2U03 10:23:35 A'M
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
17. 212000G2.1.27 001/T2GI//U-NIT DIFF RX PROT/MEM 2.8/2.9/N/BSEP 2003/R/TCKfR/C
Which ONE of the following is a purpose of the Unit Two (2) Reactor Protection
System?
A. To prevent premature actuation of Emergency Core Cooling Systems.
B.t To maintain the ability to insert selected control rods when rapid power reduction is
required by specific abnormal procedures.
C. To monitor critical parameters when the Unit is in Mode 1, 2 or 3 so that Cold
Shutdown can be obtained.
D. To monitor critical parameters at all times to initiate a reactor SCRAM and initiate
Emergency Core Cooling System when the nuclear process barrier is threatened.
Feedback
References: SD-03, Reactor Protection System Including Alternate Rod Injection
System, Rev.2, pg 6.
A. Incorrect since a Safety Limit may still be exceeded even if a reactor SCRAM
occurs.
B. Correct answer.
C. Incorrect since RPS is required in all Modes.
D. Incorrect since RPS does not initiate any Isolation functions.
18
Thursday, March 06, 2003 10:23:35 AM
QUESTIONS- REPORT
-forFINALBSEP 2003-301 Written Exam
18. 212000K6.04 001/T2G1/T2GI/RPS/C/A 2.8/3.1/M/BSEP 2003/C/LSM/R/C
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.
Feedback
REFERENCES: OP-03
LOI-CLS-LP-003-A*007002
Thursday, March 06, 2003 10:23:35 AM
19
QUESTIONS REPORT
-forPFNAL BSEP2003-301-Written Exam
19. 214000K4.01 OO/T2G2/T2G2/REED SWITCH/MEM 3.0/3.1/B/BSEP 2003/C/LSM/R/C
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).
DV The rod is at an odd reed switch and none of the selected relay busses are
energized (insert, withdraw or settle).
Feedback
References: SI-LP-05401-00 Rev. SI-00, pg 7 & 8 of 26, Reactor Manual Control
EO 001.010.a.12, 001.026.a.02
A. Incorrect since this switch does not bypass RPIS.
B. Incorrect since this does not cause an insert and withdraw signal at the same time.
C. Incorrect since being at an even reed switch position ensures a rod drift alarm does
not occur.
D. Correct answer since this alarm is actuated when rod is at an odd position and relay
buses are not energized.
-.
.
.
.
.
aarA** ^20
Thursday, March U6, 2UU6 10u:23:35 ,lV
S- QUESTIONSREPORT
-for-FINALtSEP-2003301 -Written Exam
20. 215001A2.01 OO1/T2G3//TIP SYSTEM/C/A 2.7/2.9/MIBSEP 2003/RILSM/TCK/R/C
Feedback
References: SD-09.5, Traversing In-Core Probe (TIP) System, Rev.2, pg. 29
KA change from K1 to A2
A. Incorrect since the TIP system does not de-energize on a scram and turbine trip.
B. Incorrect since the detector retracts at fast speed on a Group II signal (Low water
level of <166").
C. Incorrect since the detector retracts to the in-shield position upon a Group II signal.
D. Correct answer.
Thursday, March 06, 2003 10:23:35 AM
The following conditions exist on Unit 1:
Rx power
100%
Rx level
190"
Drywell pressure
0.6 psig
Rx pressure
1005 psig
The reactor engineer has selected TIP Probe 'A' for a core flux trace and the probe is
currently traversing into the core. Suddenly, both reactor feed pumps trip causing
water level to lower below 150".
Which ONE of the following describes how theTIP probe will respond to these
conditions?
A. Stops at its current position due to the drive motor deenergizing on a reactor scram
and turbine trip signal.
B. Retracts in slow speed until it reaches the indexer where it is left for eight hours to
decay.
C. Continues to traverse into the core until it reaches core top where it will stop.
D*' Retracts in fast speed until it reaches the in-shield position where it will stop.
21
QUESTIONS REPORT
forFINALtSEP 2003-301 -Written Exam
21. 215002K6.04 001/T2G2//ROD BLOCK MONITOR/C/A 2.8/3.0/N/BSEP 2003/R/TCK/R/C
The Unit I operator is in the process of performing the weekly control rod exercise
surveillance. A central control rod has been selected but prior to moving the rod
APRM 1 fails downscale. After verifying all other APRM's are OPERABLE then
APRM 1 is bypassed.
Which ONE of the following describes the status of Rod Block Monitor A and B?
A. Rod Block Monitor A is bypassed; Rod Block Monitor B is in service.
B. Rod Block Monitor A is in service; Rod Block Monitor B is bypassed.
C!. Rod Block Monitor A and B are both in service.
D. Rod Block Monitor A and B are both bypassed.
Feedback
References: 1SD-09.6, Power Range Neutron Monitoring System, Rev.0, pg 24 & 25
A. Incorrect since RBM will AUTO select APRM 3 with APRM 1 failed downscale.
B. Incorrect since APRM 1 is the reference APRM forRBM A so RBM B is unincorrect
since RBM A is bypassed.
C. Correct answer since RBM will AUTO select APRM 3 with APRM 1 failed downscale.
D. Incorrect since RBM B is not affected.
22
Thursday, March 06, 2003 1U:23:35 AM
QUESTIONS REPORT
forFFINAL-BSEP 2003-301 Written Exam
22. 215003A4.07 001/T2G1//IRM/C/A 3.6/3.6/N/BSEP 2003/R/TCK/R/C
Unit 1 is commencing a startup with all SRM's fully inserted and reading approximately
3 X 105 cps. The IRM's are reading the following:
IRM A
20 on Range 1
IRM E
21 on Range 1
IRM B
28 on Range 1
IRM F
19 on Range I
IRM C
21 on Range 2
IRM G
23 on Range 2
IRM D
25 on Range I
IRM H
20 on Range 1
The operator takes the Range Switch for IRM B to Range 3 and the Downscale light
comes on but no other alarms occur.
Which ONE of the following describes the OPERABILITY of IRM B?
A. IRM B is still OPERABLE because no other alarms should have occured for this
condition.
B0 IRM B is INOPERABLE because a rod block should have been initiated.
C. IRM B is still OPERABLE because the power level is too low for accurate indication.
D. IRM B is INOPERABLE because it is reading significantly higher than the other
IRM's.
Feedback
References: SD-09.1, Neutron Monitoring System (Startup and Intermediate Range),
Rev.1, pg 6 & 7.
B. Correct answer since a Rod Block should have occured due to downscale condition
and on Range 2.
A, C and D. Incorrect since Range 2 should have initiated a Rod Block.
Thursday, March 06, 2003 10:23:35 AM
23
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
23. 215004 G2.2.1 001/T2G1/T2GI/SOUREC RANGE MONITOR/MEM 3.7/3.6/N/BSEP 2003/C/TCK/R/C
Feedback
References: OGP-01, Prestartup Checklist, Rev.156, pg 25
A. Incorrect since 3 SRM's are required to be operable prior to entering Mode 2.
B. Incorrect since 3 SRM's are required to be operable prior to entering Mode 2 and the
minimum count rate is > 5 cps.
C. Correct answer.
D. Incorrect since the minimum count rate is > 5 cps.
Thursday, March 06, 2003 10:23:36 AM
24
Unit 1 is in the process of performing OGP-01, Prestartup Checklist 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.
QUESTIONS REPORT
-for-PINAL-BSEP 2003-301 Written Exam
24. 215005A4.06 001/T2G1/T2G1/APRM SYSTEM/C/A 3.6/3.8/N/BSEP 2003/C/TCK/R/C
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
APRM3
15%
APRM 4
14%
Which ONE of the following describes the effect on the plant for these conditions and
the reason for the response?
A. A scram should have occurred due to APRM 2 being Downscale and APRM 3 at
the Upscale Trip setpoint.
B. A 1/2 scram should have occurred on RPS Channel A due to APRM 3 at the
Upscale Trip setpoint.
C. A 1/2 scram should have occurred on RPS Channel B due to APRM 2 being
downscale.
Dt. The ROD OUT BLOCK alarm is the only expected actuation due to the position of
the Mode Switch.
Feedback
References: APP A-05 2-2 Rod Out Block, Rev.43
APP A-05 4-7 Neutron Mon Sys Trip, Rev.43
A. Incorrect since the APRM Downscale is not an RPS Trip signal with the Mode Switch
in Start/Hot Stby.
B. Incorrect since only APRM 3 at or exceeding the APRM UPSCL setpoint, downscale
is not a RPS trip, two concurrent APRM trips required for full scram.
C. Incorrect since a 1/2 Scram should have occurred due to APRM 3 at the upscale trip
setpoint.
D. Correct answer.
25
Thursday, March 06, 2003 10:23:36 AM
Feedback
QUESTIONS REPORT
AorFINALBSEP-2003'301 Written Exam
25. 216000K2.01 001/T2G1/T2G1/INSTRUMENTATION/MEM 2.8/2.8/B/BSEP 2003/C/LSM/R/C
Feedback
A. Ans b is wrong because no power is lost. Ans c is correct for ECCS trip cabinets.
Ans d is wrong since no power is lost. (Modified from bank #1437 H)
LOI-CLS-LP-1 18-A*009004
REFERENCES: SD-02,
26
Thursday, March 06, 2003 10:23:36 AM
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-1I) 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.
I
QUESTIONS REPORT
-forTFINALBSEP 2003-301 Written Exam
26. 217000G2.1.28 001/T2G1/T2GI/RCIC SYSTEM/MEM 3.2/3.3/N/BSEP 2003/C/TCK/R/C
Feedback
References: SD-16, Reactor Core Isolation Cooling (RCIC) System, Rev.4, pg 14 & 26
A. Correct answer.
B. Incorrect since the valve is AC powered.
C. Incorrect since the valve may be powered from an ASSD Feeder.
D. Incorrect since the valve may only be throttled in the open direction.
Thursday, March 06, 2003 10:23:36 AM
27
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.
-QUESTIONS REPORT
-for-FNAL-BSEP 2003-301-Written Exam
27. 217000K1.01 001/T2G1/T2G1/RCIC/C/A 3.5/3.5/B/BSEP 2003/C/LSM/R/C
Feedback
References: SI-LP-03901 Rev. SI-00 pg 10 of 37
A. Correct answer.
B. Incorrect since RCIC suction does not transfer on high torus level at BNP.
C. Incorrect since the CST and Torus suction valves do not get a signal to change
position at the same time. The CST gets a closed signal "After" the Torus suction
valves are full open.
D. Incorrect since the Torus suction valves come open before the CST suction valve
goes closed.
Thursday, March 06, 2003 10:23:36 AM
28
Unit 2 is operating at 80% RTP. The RCIC syster 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 (FO10) received a closed signal.
C. The Torus suction valves (F029 & F031) received an open signal at the same time
the CST suction valve (FO10) 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.
QUESTIONS REPORT
-forFINAL-BSEP 2003-301 Written Exam
28. 218000A4.02 001/T2GI/T2G1/ADS/C/A 4.2/4.2/B/BSEP 2003/C/LSM/R/C
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 fail to start. Unit One buses El and E2
remain energized throughout the event. Pressure is being maintained 800 - 1000 psig
using SRVs. Level has been below 45 inches for 5 minutes and is currently +25 on the
N026's.
Assuming ADS was NOT inhibited, which ONE
would respond to #4 EDG starting?
7 ADS valves would auto open
seconds
of the following describes how ADS
after the diesel tied to E4.
Ar 10
B. 15
C. 83
D. 93
Feedback
BSEP BANK 142.
LOI-CLS-LP-020-A*007005 Rearranged answers
A. as soon as 2B RHR pump starts, assuming 2D already running.
REFERENCES: SD-20
Thursday, March 06, 2003 10:23:36 AM
29
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
29. 219000A2.03 OO1/T2G2/T2G2/RHR SYSTEM/C/A 3.1/3.2/NIBSEP 2003/C/LSM/R/C
Feedback
Solution : Has no effect on RHR SW Pump Motor temperatures
Reference - the following Bank question:
(((27. LOI-CLS-LP-043-A*003001
The VITAL Service Water Header provides cooling water to all of the following
components EXCEPT the:
A.
RHR Room Coolers
B.
RHR Pump Seal Coolers
C.
Core Spray Room Coolers
D.
Answer:
D)))
Thursday, March 06, 2003 10:23:36 AM
Unit Two is in RHR/LPCI suppression pool cooling mode with an elevated suppression
pool temperature of 180 'F. 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.
30
QUESTIONS REPORT
IforFtNALSSEP 2003-301 Written Exam
30. 223001A2.01 OO1//T2GI/CONTAINMENT/C/A 4.3.4.4/B/BSEP 2003/S/LSM/R/C
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
Torus Level
Torus Water Temp.,
Drywell Avg. Temp.
Reactor Level
Reactor Pressure
The operating crew should
Procedures?
19 psig, slowly lowering
-5.5 feet, slowly lowering
220 OF, steady
287 OF, lowering
-35 ", rapidly rising
50 psig
do which ONE of the following per Emergency Operating
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.
Feedback
258.
LOI-CLS-LP-300-B*018001
Thursday, March 06, 2003 10:23:36 AM
31
QUESTIONS REPORT
-forFINAL-BSEP 2003-301 Written Exam
31. 223001G2.1.7 001//T2GI/DIFFERENTIAL PRES/C/A 3.7/4.4/B/BSEP 2003/S/LSM/R
Feedback
REFERENCES: TECH SPEC 3.6.4.1 /AM 159*
Thursday, March 06, 2003 10:23:36 AM
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 />.
32
QUESTIONS REPORT
Aor-FINALBSEP 2003-301 -Written Exam
32. 223001K4.03 O01/T2G1/IPRIMARY CONTAINMENT/C/A 3.7/3.8/N/BSEP 2003/R/TCK/R/C
Feedback
References: SD-12, Primary Containment Isolation System, Rev.1 pg 24 & 52
A. Incorrect since all valves would close when subsequent Group II isolation signal is
generated.
B. Incorrect since all valves would close.
C. Correct answer.
D. Incorrect since all valves would close.
Thursday, March 06, 2003 10:23:37 AM
Unit 1 has experienced a small LOCA with the following conditions present:
Drywell pressure
4.5 psig
Drywell temperature
201 OF
Reactor water level
145 inches
Reactor Bldg Exhaust Rad
8 mRlhr
Per the EOP's the CAC Div I and CAC Div II AC and DC Isolation (Soft) Override
switches have been initiated to allow sampling of containment parameters. The RHR
Process Sampling valves (El 1-F079A,B and F080A,B) have been opened to allow for
sampling.
If reactor water level was to increase to 180 inches and then drop back down to 145
inches, which ONE of the following indicates the status of the RHR Process Sampling
valves?
A. All valves would remain open due to the Override switches being actuated.
B. The Inboard valves would close and the Outboard valves would remain open.
C. All valves would close when reactor vessel level dropped below 166 inches.
D. The Inboard valves would remain open and the Outboard valves would close.
33
SQUESTIONS REPORT
ifor-fINALPSEP 2003-301 Written Exam
33. 223002A3.02 001/T2G1/T2G1/MSIV/C/A 3.5/3.5/MIBSEP 2003/C/LSM/R/C
Feedback
205.
LOI-CLS-LP-025-A*004001 (Modified stem and all 4 distractors)
original question:
205.
LOI-CLS-LP-025-A*004001 (Modified C and D)
The MSIV closure time is adjusted by:
A.
regulating the closure piston air pressure.
B.
adjusting or replacing the valve packing.
C.
throttling the bypass valves on the hydraulic dash pot.
D.
relapping or replacing the Stellite on the valve seat.
Answer:
C
Thursday, March 06, 2003 10:23:37 AM
34
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.
QUESTIONS REPORT
--for-FINALBSEP2003'301 -Written Exam
34. 223002KI.07 001/T2G1/T2G1/RCIC/C/A 3.4/3.6/B/BSEP 2003/C/LSM!R/C
Feedback
Reference:
A. Incorrect since only the F008 valve is affected by the "Manual Isolation" pushbutton
while there is an initiation signal present.
B. Incorrect since the F007 valve is not affected by the "Manual Isolation" pushbutton
while there is an initiation signal present.
C. Correct answer.
D. Incorrect since the only isolation signal could be Suppression Chamber Ambient
Temp but it has a 30 minute time delay when temp is > 165OF and this is 10 minutes
into the event.
Thursday, March 06, 2003 10:23:37 AM
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 Emergency Area Cooler Temp
1 00OF 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.
35
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
35. 230000A2.15 OOI/T2G2//RHR SYSTEM/C/A 4.0/4.1/N/BSEP 2003/R/TCK/R/C
Unit 2 has experienced a large LOCA with the following conditions present:
Reactor Pressure
10 psig
Drywell pressure
25 psig steady
Torus pressure
24 psig steady
Drywell Temperature
275 OF steady
Reactor water level
-30 inches
The Unit Supervisor has ordered Torus and Drywell sprays to be initiated.
Which ONE of the following describes the minimum actions necessary per
OEOP-01-SEP-02, Drywell Spray Procedure, to initiate Drywell sprays after verifying
Recirc Pumps and Drywell Coolers are off?
Verify or start an RHR pump and:
A. Place 2/3 Core Height LPCI Initiation Override switch Ell -CS-SI 8 to the "Manual
Overrd" position. Open Drywell Spray Inbd Isol Valve, Ell -F021, then throttle
Drywell Spray Outbd Isol Valve, El 1-F016.
B.3 Place Containment Spray Valve Control switch E1I-CS-S17 to the "Manual"
position. Open Drywell Spray Inbd Isol Valve, E11-F021, then throttle Drywell Spray
Outbd Isol Valve, Ell -F016.
C. Place Containment Spray Valve Control switch ElI-CS-$17 to the "Manual"
position. Open Drywell Spray Outbd Isol Valve, E1I-F016, then throttle open
Drywell Spray Inbd Isol Valve, Ell -F021.
D. Place Containment Spray Valve Control switch E 1I-CS-$l7 to the "Manual"
position and the 2/3 Core Height LPCI Initiation Override switch El1-CS-S18 to the
"Manual Overrd" position. Open Drywell Spray Inbd Isol Valve, ElI-F021, then
throttle Drywell Spray Outbd Isol Valve, El1-F016.
ý
nnn
A
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7AA
36
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iviar
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- .U
UL
.3 ~v
QUESTIONS REPORT
Ifor-FINALtSEP 2003-301 -Written Exam
Feedback
References: SD-01, Nuclear Boiler System, Rev.4, Figure 01-02
OOEP-01-SEP-02, Drywell Spray Procedure, Rev.13, pg 3
SD-17, Residual Heat Removal System, Rev.4, pg
A. Incorrect since you don't need to reposition the 2/3 Core Height switch yet. Level is
not down that low yet.
B. Correct answer.
C. Incorrect since you don't have to reposition both switches.
D. Incorrect since the spray valves are operated backwards.
Thursday, March 06, 2003 10:23:37 AM
37
QUESTIONS REPORT
-forFINAL-BSEP 2003-301-Written Exam
36. 233000K2.02 OO1/T2G3//SDC/MEM 2.8/2.9/N/BSEP 2003/R/LSM/R/C
Unit 1 is on Shutdown Cooling using RHR Loop 1 B. I&C Techs are working on the
RPS logic power supply. During the repair work the Techs cause an inadvertent loss of
Division 11 125/250 VDC electrical distribution.
Which ONE of the following describes the effect of this loss of Shutdown Cooling?
A. Group 8 outboard SDC suction valve remains OPEN. LPCI injection valves will fail
CLOSED.
B. Group 8 outboard SDC suction valve and LPCI injection valves will fail CLOSED.
C. Group 8 outboard SDC suction valve remains OPEN. LPCI injection valves remain
OPEN.
D. Group 8 outboard SDC suction valve fails CLOSED. LPCI injection valves remain
OPEN.
Feedback
NEW
SD-12 Page 72 of 217
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QUESTIONS REPORT
-for-FINAL-BSEP 2003-301 Written Exam
37. 239001K3.16 001/T2G2/T2G3/MAIN STEAM/MEM 3.6/3.6/B/BSEP 2003/C/LSM/R/C
Feedback
BSEP BANK 135. LOI-CLS-LP-020-A*O03001
Thursday, March 06, 2003 10:23:37 AM
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
39
QUESTIONS REPORT
-forFItAL-BSEP 2003-301 Written Exam
38. 239002A1.01 001/T2G1/T2G1/SRV/C/A 3.3/3.4/B/BSEP 2003/C/LSM/R/C
During an overpressure transient,
RPV pressure is 1005 psig.
Which ONE of the following is the
open, as indicated on ERFIS?
an operator has opened an SRV to control pressure.
expected tail pipe temperature for the SRV that is
A. 212 OF
B. 300 OF
C.' 350 OF
D. 545 OF
Feedback
b. Ans a is based on saturated conditions for atmospheric pressure. Ans c is based on
moving from sat conditions to the other side of the saturation curve at 1000 psig on the
Mollier diagram. Ans d is based on saturated conditions for 1015 psia steam.
104.
LOI-CLS-LP-110-A*03AO02
40
Thursday, March 06, 2003 10:23:37 AM
QUESTIONS-REPORT
-for FINAL-BSEP 2003-301 Written Exam
39. 239002K6.05 001/T2G2//VACUUM BRKR/C/A 3.0/3.2/M/BSEP 2003/R/LSM/TCK/R/C
Feedback
REFERENCES: SD-20
163.
LOI-CLS-LP-020-A*07DO01
Thursday, March 06, 2003 10:23:38 AM
During normal power operation of Unit 1, SRV FOI3H lifted.
Which ONE of the following describes the consequences of SRV F01 3H tailpipe
vacuum breaker (F037H) failing open prior to the SRV actuation?
A. Steam will discharge directly to the suppression pool airspace.
Br3 Steam will discharge directly to the drywell.
C. Water from the suppression chamber will draw into the SRV tailpipe following
actuation.
D. A redundant vacuum breaker will open with no operational consequences.
41
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
40. 241000K6.05 00I/T2GIT2G1/CONDENSER VACUUM/MEM 3.4/3.4/B/BSEP 2003/C/LSM/R/C
Feedback
Reference: SI-LP-02501-00 Rev. SI-00 Pg 7 of 13.
EO 200.087.a.01
A. Incorrect since Main Turbine trip at 22.3" Hg
Bypass valves close at 7" Hg Vac.
B. Incorrect since Main Turbine trip at 22.3" Hg
Bypass valves close at 7" Hg Vac.
Vac., MSIV's close at 10" Hg Vac and
Vac., MSIV's close at 10" Hg Vac and
C. Correct answser since Main Turbine trip at 22.3" Hg Vac, MSIV's close at 10" Hg
Vac and Bypass valves close at 7" Hg Vac.
D. Incorrect since Main Turbine trips prior to the MSIV's closing.
Thursday, March 06, 2003 10:23:39 AM
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.
42
QUESTIONS REPORT
-for PINALBSEP2003-301-Written Exam
41. 245000A4.10 001/T2G2/T2G2/MAIN TURBINE/C/A 2.6/2.6/B/BSEP 2003/C/LSM/R/C
Feedback
245000 A4.10
398.
LOI-CLS-LP-027-D*05D002
Reference required ***Generator Estimated Capability Curves (spider web graph)
Thursday, March 06, 2003 10:23:39 AM
43
Assume the Unit 2 Main Generator is opeiating 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.
QUESTIONS REPORT
iorftNAL-BSEP2003-301 Written Exam
42. 256000K2.01 001/T2G2/T2G3/CONDENSATE/MEM 2.7/2.8/B/BSEP 2003/C/LSMIR/C
Unit One and Unit Two are operating at 100% power. The following annunciators are
received on Unit One.
UA-13 3-9 SAT Fault Pressure
UA-13 1-9 SAT Lockout
Which ONE of the following describes which Condensate Transfer Pump(s) will have
power?
A. Unit One only.
B. Unit Two only.
C. Both Unit One and Unit Two.
D. Neither Unit One nor Unit Two.
Feedback
406.
LOI-CLS-LP-031-B*07BO01
Thursday, March 06, 2003 10:23:39 AM
44
-QUESTIONS REPORT
for FINAL-BSEP-2003-301 Written Exam
43. 259001A2.07 001/T2GIT2G2/FEEDWATER/IMEM 3.7/3.8/B/BSEP 2003/C/LSM/R/C
Feedback
418.
LOI-CLS-LP-032-C*003004
REFERENCES: OBJ 2C
Thursday, March 06, 2003 10:23:39 AM
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.3 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.
45
QUESTIONS REPORT
AorFINALtSEP 2003301-Written Exam
44. 261000K3.04 001/T2G1/T2G1/SBGT SYSTEM/MEM 3.1/3.1/N/BSEP 2003/C/LSM/R/C
Feedback
System description
1.1.1 Reactor Core Isolation Cooling
The RCIC test return line is shared with the HPCI System via redundant test return
valve E41 -F011. RCIC cannot be operated in the flow test (pressure control) mode if
HPCI has an initiation signal or if either HPCI suppression pool suction valve is open.
The RCIC Barometric Condenser Discharge Line was rerouted to the SBGT to prevent
air injection to the containment during an emergency response. This reroute was made
by connecting a tee to the HPCI Vacuum Pump discharge to the SBGT. A check valve
was installed in the HPCI Vacuum Pump discharge line to allow isolation of the HPCI
Barometric Condenser from the RCIC Vacuum Pump exhaust.
Thursday, March 06, 2003 10:23:39 AM
46
Which ONE of the following describes the effect that a loss of SBGT would have on the
A. There would be no effect since the SBGT system is not connected to HPCI or
RCIC.
B.r Both the RCIC Barometric Condenser and the HPCI Vacuum Pump Discharge line
would be effected.
C. Only the RCIC Barometric Condenser would be effected.
D. Only the HPCI Vacuum Pump Discharge line would be effected.
-
QUESTIONSREPORT
-forR-FNAL BSEP 2003-301 Written Exam
45. 261000K4.01 001/T2GI//SBGT SYSTEM/C/A 3.7/3.8/M/BSEP 2003/R/LSM/R/C
Standby Gas Treatment control switches on Unit One are aligned as follows:
Train A is in the STBY position.
Train B in the PREF B position.
Emergency Bus El is de-energized due to a bus fault.
Which ONE of the following describes how the Standby Gas Treatment system will
respond?
A. SBGT A will IMMEDIATELY start.
B. SBGT B will IMMEDIATELY start.
C. SBGT A will start following a 10 second time delay.
D. SBGT B will start following a 10 second time delay.
Feedback
Bank-
LOI-CLS-LP-010-A*02G003
Thursday, March 06, 2003 10:23:39 AM
47
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
46. 262001A2.03 001//T2G1/AC/C/A 3.//4.3/B/BSEP 2003/S/LSM/R
Feedback
References: LOI-CLS-LP-003-A*008018
Thursday, March 06, 2003 10:23:39 AM
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
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.
48
QUESTIONSREPORT
-for-FiNAL-BSEP 2003-301 Written Exam
47. 262001A4.05 001/T2G2/T2G1/AC/C/A 3.3/3.3/B/BSEP 2003/C/LSM/R
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.
Feedback
381.
LOI-CLS-LP-027-A*1FO01
S
aOAO 4n
o
On ARA
49
I Hrllsuay, IviarCHUI UV,*
- UU
IU
- OO
SQUESTIONS-REPORT
Afor-FINAL-SEP-2003-301 Written Exam
48. 263000K2.01 OOI/T2G2/T2G2/DC SYSTEMS/MEM 3.1/3.4/N/BSEP 2003/C/TCK/R/C
Feedback
References: SD-51, DC Distribution System, Rev.2, pg 39-43
A, B and C. Incorrect since none of these cause the outboard MSIV's to close.
D. Correct answer.
Thursday, March 06, 2003 10:23:39 AM
-Which ONE of the following is the power supply to the Outboard MSIV's DC solenoids
on Unit One (1)?
A. Div 1 Switchboard 21A.
B. Div 2 Switchboard 22B.
C. Div 1 Switchboard IA.
DV Div 2 Switchboard 1 B.
50
" QUESTIONS REPORT
lfor-FINALBSEP 2003-301 Written Exam
49. 264000K4.05 001/T2G1I/T2G1/SPRAY/C/A 3.2/3.5/B/BSEP 2003/C/LSM/R/C
Feedback
256.
LOI-CLS-LP-01 7-A*007020
51
Thursday, March 06, 2003 10:23:39 AM
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 restarts10 seconds later, RHR pump 2B remains off.
DP. RHR pump 2B restarts 10 seconds later, RHR pump 2D remains off.
QUESTIONS REPORT
-for FIN-AL-BSEP2003-301 Written Exam
50. 264000K5.06 001/T2G1/T2GI/EDG/C/A 3.4/3.5/B/BSEP 2003/C/LSM/R/C
Feedback
LOI-CLS-LP-043-A*006001
Thursday, March 06, 2003 10:23:39 AM
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*3 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.
52
-- QUESTIONSREPORT
Ior-FINALPBSEP 2003M301 Written Exam
51. 268000A1.01 OOI/T2G3/T2G3/RADWASTE/C/A 2.7/3.1/N/BSEP 2003/C/LSM/R/C
Feedback
B: Both Units discharge valves receive a close signal. FCV-189 must be manually closed, no
auto signal.
REFERENCES: APP UA-03, 2-8
Answer:
B
new question based on LOI-CLS-LP-01 1*B-08E001
53
Thursday, March 06, 2003 10:23:40 AM
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 (D1 2-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.
B0 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.
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
52. 271000A3.02 001/T2G2//OFF GAS SYSTEMIC/A 2.9/2.8/N/BSEP 2003/R/TCK/R/C
Feedback
References: SD-30, Conderser Air Removal and Off-Gas Recombiner System, Rev.4,
pg. 46.
A. Incorrect since a fuel element failure causes rad levels to increase significantly vice
off-gas flows.
B. Correct answer.
C. Incorrect since low Recombiner temperature basically results in higher Hydrogen
concentrations only.
D. Incorrect since this does not cause high Off-Gas system flows.
Thursday, March 06, 2003 10:23:40 AM
The following indications are noted by the operator regarding the Off-Gas System:
Off-Gas flows
increasing
Off-Gas filter Dp's
increasing
Recombiner temperature
increasing
Oxygen concentration
increasing
Hydrogen concentration
decreasing
Which ONE of the following describes the probable cause for these conditions and the
consequence of Off-Gas flow increasing above 150 scfm?
A. Fuel element failure is the problem; The Off-Gas flow will be routed to the filter train
and cause filter radiation levels to increase.
B.3 Air intrusion is the problem; The Off-Gas flow will go directly to the Main Stack
causing Main Stack Effluent Radioactivity to increase.
C. Low Recombiner temperature is the problem; The Off-Gas flow will be routed to the
filter train and cause filter radiation levels to increase.
D. Charcoal Adsorber bed high Dp is the problem; The Off-Gas flow will go directly to
the Main Stack causing Main Stack Effluent Radioactivity to increase.
54
QUESTIONS REPORT
-for-FINALBSEP2003-301 Written Exam
53. 272000K1.02 001/T2G2/T2G2/RAD MONITORING/MEM 3.2/3.5/B/BSEP 2003/C/LSM/R/C
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-102, 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.
DV PROCESS OFFGAS RAD MONITOR DOWNSCALE/INOP alarm is received and
the process offgas timer does NOT initiate.
Feedback
BSEP REVIEWER - THIS CAME FROM THE BANK, PLEASE VERIFY THE CORRECT
ANSWER IS MARKED. THANK YOU
404.
LOI-CLS-LP-030-A*031001
It requires any combination of train A and train B rad monitor trip signals (hi-hi, downscale, or
inop) initiates closure of AOG bypass valve.
Thursday, March 06, 2003 10:23:40 AM
55
QUESTIONS REPORT
-forFINALBSEP 2003-301 Written Exam
54. 288000A2.02 001//T2G3/CAD/C/A 3.4/3.6/M/BSEP 2003/S/LSM/R/C
Feedback
A.
Lesson 2: LOI-CLS-LP-012-A
References: SD-12
185.
LOI-CLS-LP-024-A*008004
Lesson 2 Objectives: 06
Thursday, March 06, 2003 10:23:40 AM
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 H20 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 'F.
56
QUESTIONS REPORT
ifor$FINALtBSEP 2003-301 Written Exam
55. 295001AK2.02 001/TIG2/T1G2/RECIRC SYSTEM/MEM 3.2/3.3/N/BSEP 2003/C/TCK/R/C
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.
Feedback
References: 20P-02 Rev.1 10, Reactor Recirculating System Operating Procedure
A. Incorrect since the lower Recirc Speed is procedurally limited to 28% speed to
prevent seal damage.
B. Incorrect since the region for instabilities is not entered prior to starting the idle recirc
pump.
C. Incorrect since the bottom head temperature tends to decrease at the lower core
flows.
D. Correct per caution statement on page 27.
57
Thursday, March 06, 2003 10:23:40 AM
QUESTIONS REPORT
-for-FNAL-BSEP 2003-301 Written Exam
56. 295002AK2.08 00I/TIG2/TIG2/CONV SERVICE WATER/C/A 3.1/3.2/N/BSEP 2003/C/TCK/R/C
Feedback
References: OAOP-19.0 Rev.13, Conventional Service Water System Failure
A. Incorrect since Conventional Service Water does not supply cooling to the ECCS
Room Coolers.
B. Incorrect since Conventional Service Water does not supply cooling to the RBCCW
Heat Exchangers.
C. Incorrect since there is no guidance to reduce load to prevent overheating
equipment supplied by TBCCW.
D. Correct answer since Conventional Service Water supplies bearing lubrication to the
C.W. pumps.
Thursday, March 06, 2003 10:23:40 AM
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.
D4. The reactor must be scrammed due to imminent loss of condenser vacuum.
58
QUESTIONS REPORT
iforFINALBSEP 2003-301 Written Exam
57. 295002AK3.02 001/TIG2/TfG2/CONDENSER VACUUM/MEM 3.4/3.4/N/BSEP 2003/C/TCK/R/C
Feedback
References: SD-26 Rev.5, Turbine System
A. Incorrect since lowering condenser vacuum will not affect the suction pressure to the
condensate pumps enough to trip the pumps.
B. Correct answer.
C and D. Incorrect since the reason the turbine is tripped is due to higher vibrations and
increased loading on the last turbine blades.
Thursday, March 06, 2003 10:23:40 AM
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.3 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.
59
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
58. 295003AK1.02 001/T1G2/T1IG1/LOSS OF AC/MEM 3.1/3.4/N/BSEP 2003/C/TCK/R/C
Feedback
References: SD-50.1 Rev.4, 4160 VAC Electrical Distribution System
SD-39 Rev.2, Emergency Diesel Generators
A. Incorrect since the order that the pumps start is incorrect.
B. Correct answer.
C. Incorrect since the load shed occurs prior to the pumps starting.
D. Incorrect since the load shed occurs prior to the pumps starting and the order that
the pumps start is incorrect.
Thursday, March 06, 2003 10:23:40 AM
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 IC, 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.
60
QUESTIONS REPORT
IorFtNALBSEP 2003-301 Written Exam
59. 295003G2.1.10 001//T1G1/LOSS OF ALL AC/MEM 2.7/3.9/B/BSEP 2003/S/LSM/R/C
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.
Feedback
Cooldown rate is 120 degrees per hour which meets requirements of > 100 degrees per hour,
but required pressure band is 150-300 psig and the cooldown should be stopped.
Thursday, March 06, 2003 10:23:40 AM
61
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
60. 295004AA2.02 00I/TIG2/TIG2/DC SYSTEMS/MEM 3.5/3.9/N/BSEP 2003/C/TCK/C
Feedback
References: OAOP-39.0 Rev.15, Loss of DC Power
001-50 Rev.24, 125/250 VDC Electrical Load List
A. Correct answer.
B,C and D. Incorrect since these buses do not supply power that affects all of the listed
items.
Thursday, March 06, 2003 10:23:41 AM
62
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. IXDA.
D. 1XDB.
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
61. 295005AA1.05 001/TIG1/T1G2/TURBINE TRIP/MEM 3.6/3.6/B/BSEP 2003/C/LSM/R/C
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
Dt. Turbine Control Valves
-
Closed
Intercept Valves
-
Closed
Intermediate Stop Valves - Closed
Bypass Valves
-
All open initially; throttle closed to control Rx pressure.
Feedback
References: SI-LP-01901-00 Rev. 3 pg 44-46 of 79
SI-LP-01701-00 Rev. SI-00 pg 17 of 36
EO 019.010.a.01
A. Incorrect since all valves close except bypass valves on a turbine trip.
B. Incorrect since all valves close except bypass valves on a turbine trip.
C. Incorrect since all valves close except bypass valves on a turbine trip.
D. Correct answer.
Thursday, March 06, 2003 10:23:41 AM
63
QUESTIONS REPORT
for pINALBSEP 2003-301 Written Exam
62. 295006AA2.05 OOI//T1GI/EOP ENTRY/C/A 4.6/4.6/N/BSEP 2003/S/TCK/R/C
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 norm
Which ONE of the following indicates which EOP's should be en
A. EOP-01 -LPC, Level/Power Control;
EOP-03-SCCP, Secondary Containment Control Procedure.
B.r 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.
ial full power reading
tered at this time?
Feedback
References: APP-UA-23 Annunciator
EOP's
A. Incorrect since entry into EOP-03 is 3 mR/hr for Rx bldg vents.
B. Correct answer since scram should have occurred due to low water level and reactor
power is still above 3%.
C. Incorrect since power is above APRM setpoint.
D. Incorrect since entry into EOP-04 is 1.4 times normal rad levels for MSIV's.
Thursday, March 06, 2003 10:23:41 AM
64
QUESTIONS REPORT
4or$INAL BSEP 2003-301 -Written Exam
63. 295006AA2.06 001/TIG1//REACTOR SCRAM/C/A 3.5/3.8/N/BSEP 2003/R/TCK/R/C
Feedback
References: SD-03, Reactor Protection System Rev.2
A. Incorrect since the Reactor Scram setpoint is > 1060 psig.
B. Correct answer since reactor power is >30% RTP.
C. Incorrect since the MSIV's need to be 90% full open to cause a scram signal.
D. Incorrect since the Reactor Water Level scram setpoint is 166".
Thursday, March 06, 2003 10:23:41 AM
Unit 2 is in Mode 1 with the following conditions present:
Reactor Power
34% RTP
Reactor Pressure
1050 psig
Reactor Water Level
168 inches
MSIV A and B
94% open
Turbine Control Valve Fast Closure
500 psig (Disk dump oil pressure)
Which ONE of the above conditions should have resulted in a full Reactor Scram?
A. Reactor Pressure of 1050 psig.
B* Turbine Control Valve Fast Closure disk dump oil pressure of 500 psig.
C. MSIV A and B not full open.
D. Reactor Water Level of 168 inches.
65
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
64. 295006G2.2.20 001//TlG1/SCRAM/C/A 2.2/3.3/B/BSEP 2003/S/LSM/R/C
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
Steam flow
Reactor pressure
Drywell pressure
Mode Switch
31%
3.2 MIbm/hr.
960 psig, controlled by EHC
0.6 psig
RUN
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.
Feedback
Bank
LOI-CLS-LP-003-A*008011
A. SDV hi hi trip can be bypassed only if the Mode switch is in Shutdown or Refuel.
Turbine stop valve closure bypass sensed by turbine 1st stage pressure(isolated).
Setdown setpoint is 170", 4" above scram setpoint, IRM trips bypassed in RUN.
Thursday, March 06, 2003 10:23:41 AM
66
QUESTIONS REPORT
ior-FINALPBSEP2003-301 Written Exam
65. 295007AK3.06 0O1/TIG1/TIG1/REACTOR PRESSURE/C/A 3.7/3.8/B/BSEP 2003/C/TCK/R
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.
Ct. 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.
Feedback
A. Incorrect
B. Incorrect
C. Correct
D. Incorrect
,AA
g onA'
00m
.1:.A34 AM
67
urs ay,
arc
I
QUESTIONS REPORT
-forFINALtSEP-2003-301 Written Exam
66. 295008AK3.04 001/T1G2/TIG2/MAIN TURBINE/MEM 3.3/3.5/N/BSEP 2003/C/TCK/R
Feedback
References: Tech Spec Sectin 3.3.2.2 Bases.
A. Incorrect since HPCI and RCIC have their own trip setpoints for vessel level and
they are still available for operation since the high level trip automatically resets.
B. Incorrect since the primary reason to trip the turbines is to terminate the event.
C. Correct answer.
D. Incorrect since the Main Turbine has a seperate trip which also closes the turbine
stop valves to protect the turbine from water.
Thursday, March 06, 2003 10:23:41 AM
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.
68
QUESTIONS REPORT
-for FINAL BSEP 2003-301 Written Exam
67. 295009AK1.05 002/T1G1/T1G1/RPV/MEM 3.3/3.4/B/BSEP 2003/C/LSMIR/C
Feedback
Reference: LR-LP-20327 Rev. 10 Pg 42 of 53
Revised correct answer lAW lesson plan.
A. Correct answer.
B, C or D. Incorrect answer.
Thursday, March 06, 2003 10:23:41 AM
Which ONE of the following is the basis-for lowering RPV water level during an ATWS
condition?
A' Reduces reactor power by reducing the natural circulation driving head.
B. Reduces steam generation rate which reduces the moderator temperature.
C. Prevents thermal stratification which prevents localized power peaks.
D. Reduces reactor pressure which allows more injection from low pressure systems.
69
QUESTIONS REPORT
-for-FINAL BSEP2003-301 Written Exam
68. 295009G2.4.1 001//TIGI/EOP ENTRY/C/A 4.3/4.6/N/BSEP 2003/S/LSM/R/C
Feedback
Per 1-EOP-UG
B is the correct answer
Thursday, March 06, 2003 10:23:41 AM
Reactor water level has just dropped suddenly to 158 inches. Control rod position
indications are unavailable. APRMs are down scale andperiods 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 L/PC then go to RVCP and execute RC/L and RC/P concurrently.
D. Enter RVCP then execute L/PC, RC/L and RC/P concurrently.
70
-QUESTIONS REPORT
-forFtNAL-BSEP 2003-301 Written Exam
69. 295010AA1.01 002/TIGI/TIGI/DRYWELL VENTILATION/C/A 3.4/3.5/N/BSEP 2003/C/TCKJR/C
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.
Feedback
References: SD-04, Primary Containment Rev.1 pg 17-19.
SD-18, Core Spray Rev.0 pg 21
A. Correct answer. Drywell coolers trip on Core Spray Initiation Logic (Hi Drywell
Pressure concurrent with Low Reactor Pressure).
B. Incorrect since all the Drywell coolers trip.
C. Incorrect since all the Drywell coolers trip.
D. Incorrect since the Override switches are in NORMAL.
Thursday, March 06, 2003 10:23:42 AM
71
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
70. 295010AA2.06 00!//TIG1/DRYWELL PRESSURE/C/A 3.6/3.6/M/BSEP 2003/S/LSM/TCK/C
Feedback
Reference: PC-1 Primary Containment Control
Drywell Spray Initiation Limit (Graph 8)
(Consider providing PC-1 and Graph 8)
A. Incorrect since Torus water level is above 6 feet.
B. Correct answer.
C. Incorrect since the Torus to Drywell vacuum breakers are submerged and can spray.
D. Incorrect since EOP's have direction to cover this situation.
Thursday, March 06, 2003 10:23:42 AM
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.
Bý' 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).
72
QUESTIONS REPORT
-forFINAL-BSEP 2003-301 Written Exam
71. 295012AA1.02 001/T1G2/TIG2/DRYWELL TEMPERATURE/MEM 3.8/3.8/N/BSEP 2003/C/TCK/R/C
Feedback
References: SD-04 Rev.1, Primary Containment
A. Incorrect since running the fans in MAX position will not overload RBCCW System.
B. Incorrect since the normal position for the switch is MIN position.
C. Correct answer.
D. Incorrect since the normal position for the switch is MIN position.
Thursday, March 06, 2003 10:23:42 AM
73
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.
Co 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.
QUESTIONS-REPORT
for FINALBSEP 2003-301 Written Exam
72. 295013AA2.02 001//TGIO/TORUS TEMP/MEM 3.2/3.5/M/BSEP 2003/S/LSM/R/C
Feedback
LESSON 2: LOI-CLS-LP-302-M
LESSON 3: LOI-CLS-LP-302-D
LOI-CLS-LP-004-A*1 5M001
LESSON 2 OBJECTIVES: 03c
LESSON 3 OBJECTIVES: 02
Thursday, March 06, 2003 10:23:42 AM
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.
74
QUESTIONS REPORT
-forFINAL-BSEP 2003-301 Written Exam
73. 295013AK1.03 001/TIG2/T1G1/SUPPRESSION POOL TEM/C/A 3.0/3.3/N/BSEP 2003/C/TCK/R/C
Feedback
References: Tech Spec section 3.6.2.1
A. Incorrect since the Tech Spec limit for Suppression Pool temperature is 95 0F
average pool temperature. This has not been exceeded.
B. Incorrect since there is not a spec for ANY temperature. The spec is for AVERAGE
pool temperature.
C. Incorrect since the Tech Spec limit of 1 10OF is for AVERAGE pool temperature.
D. Correct answer.
Thursday, March 06, 2003 10:23:42 AM
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 111 0F. The average Suppression Pool temperature is
steady at 93 0F.
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.
75
QUESTIONS REPORT
for FINAL-BSEP 2003m301 Written Exam
74. 295014AA2.03 0O1//TIGI/REACTIVITY/C/A 4.0/4.3/M/BSEP 2003/S/LSM/R/C
Feedback
Answer:
A
63.
LOI-CLS-LP-002-A*161001
Thursday, March 06, 2003 10:23:42 AM
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.
76
QUESTIONS REPORT
-for FINAL-BSEP 2003-301 Written Exam
75. 295014AK2.03 001/TIGI/TIGI/FUEL TEMPERATURE/C/A 3.3/3.4/B/BSEP 2003/C/LSM/R/C
Feedback
References: FSAR section 15.2
A. Correct answer - all occurances increase reactor power and fuel temperature.
B, C and D. Incorrect since at least one occurance decreases reactor power and fuel
temperature.
Thursday, March 06, 2003 10:23:42 AM
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.
77
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
76. 295015AK1.02 001/T1G1/T1G1/ATWS/MEM 3.9/4.I/N/BSEP 2003/C/TCK/R/C
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.
Ct. 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.
Feedback
References: 001-37.5, Level/Power Control Basis Document Rev.4
A. Incorrect since this action will not cause more boron to be added. The CSBW will
ensure that the reactor stays shutdown at any temperature.
B. Incorrect since it does not prevent the boron from being uniformly mixed.
C. Correct answer.
D. Incorrect since EOP guidance directs the prevention of injection from Condensate
and ECCS during an ATWS condition.
Thursday, March 06, 2003 10:23:42 AM
78
QUESTIONS REPORT
1for FtNAL-BSEP 2003-301 Written Exam
77. 295016AK3.01 0OO/T1G2/T1Gl/REMOTE SHUTDOWN/MEM 4.1/4.2/B/BSEP 2003/C/TCKJR/C
Feedback
References: OAOP-32.0 Rev.35, PLANT SHUTDOWN FROM OUTSIDE CONTROL
ROOM:
FSAR Section 7.2.1
A. Incorrect since the Technical Requirements Manual does not describe how to
shutdown the plant from outside the control room.
B. Incorrect since the Technical Specifications do not describe how to shutdown the
plant from outside the control room.
C. Correct answer.
D. Incorrect since it is a requirement to be able to perform a prompt hot shutdown from
outside the control room.
Thursday, March 06, 2003 10:23:42 AM
A chlorine tank car rupture has made the Control Room inaccessable. If possible, prior
to leaving 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.
79
QUESTIONS REPORT
Afor-FINAL-BSEP-2003-301 Written Exam
78. 295017G2.1.2 001/T1G2/T1G1/OFFSITE RELEASE/MEM 3.0/4.0/N/BSEP 2003/C/TCK/R/C
Feedback
Reference: OOAP-05.0 Rev. 14
A. Correct answer.
B, C and D. Incorrect since these actions are all subsequent actions.
Thursday, March 06, 2003 10:23:43 AM
Fuel bundles are being moved in the Unit I Fuel Pool when alarm UA-03 3-5,
PROCESS RX BLDG. VENT RAD HI-HI is received followed by a report that an
irradiated fuel assembly has been dropped and damaged. The Control Operator notes
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.
80
QUESTIONS REPORT
for FINALBSEP 2003-301 Written Exam
79. 295019AA1.01 001/T1G2/T1G2/LNSTRUMENT AIR/MEM 3.5/3.3/N/BSEP 2003/C/TCK/R/C
The Unit 2 Reactor Instrument Air Non-Interruptible/Pneumatic Nitrogen Supply
(RNA/PNS) header pressure has dropped to 70 psig.
Which ONE of the following describes the effect this will have on the Inboard MSIV's?
A. The Inboard MSIV's will not be affected due to the Backup Nitrogen valves SV-5481
and SV-5482 opening.
B. The Inboard MSIV's should not be affected due to the accumulators associated with
the valve operators.
C. The Inboard MSIV's may start drifting closed due to a sustained low header
pressure.
D. The Inboard MSIV's will close immediately after RNA/PNS header pressure drops
below 80 psig.
Feedback
References: SD-46 Rev.4, Pneumatic Systems
A. Incorrect since Backup Nitrogen does not supply the MSIV's.
B. Incorrect since the accumulators maintain pressure for a short time.
C. Correct answer.
D. Incorrect since the MSIV's will not close immediately due to the accumulators
associated with the valves.
Thursday, March 06, 2003 10:23:43 AM
81
QUESTIONS REPORT
ifor-F[NALPSEP 2003-301 Written Exam
80. 295020AA2.06 001/T1G2/T1G2/CONTAINMENT ISOL/C/A 3.4/3.8/N/BSEP 2003/C/TCK/R/C
Feedback
References: SD-011.2 Rev.2, Reactor Vessel Instrumentation.
A. Incorrect since the Group II Isolation setpoint is > 1.7 psig.
B. Incorrect since a reference leg leak would cause the instrumentation to read a higher
level.
C. Correct answer since a variable leg leak would indicate a lower level and the two
instruments are from different divisions to cause the actuations.
D. Incorrect since high Drywell temperature does not cause a Group II Isolation.
Thursday, March 06, 2003 10:23:43 AM
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 and LT-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.
82
QUESTIONS REPORT
ior-FINALPSEP 2003-301 Written Exam
81. 295021AA2.01 001//T1G2/SHUTDOWN COOL/MEM 3.5/3.6/B/BSEP 2003/S/LSM/R/C
Feedback
B. Correct
SRO ONLY
83
Thursday, March 06, 2003 10:23:43 AM
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.3 Safety relief valve tailpipe temperature.
C. Steam dome pressure using steam table conversion.
D. The running ECCS pump local suction temperature.
Feedback
Feedback
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
82. 295021AK2.01 001/T1G3/T1G2/SHUTDOWN COOL/C/A 3.6/3.7/N/BSEP 2003/C/TCK/R/C
Feedback
References: OAOP-15.0, Loss of Shutdown Cooling, Rev.13
A. Incorrect since the vessel bottom head temperature may not be indicative of average
vessel coolant temperature.
B. Incorrect since the recirc loop suction temperatures may not be indicative of average
vessel coolant temperature.
C. Correct answer. If an increasing trend in vessel pressure is established then it must
be assumed that 212OF has been exceeded and a Mode change has occurred.
D. Incorrect since natural circulation cannot be relied upon to establish enough
circulation to provide accurate temperature indication.
84
Thursday, March 06, 2003 10:23:43 AM
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.
QUESTIONS REPORT
forFINAL BSEP 2003-301 Written Exam
83. 295022G2.1.30 001/TIG2/T1G2/CRD SYSTEM/MEM 3.9/3.4/N/BSEP 2003/C/TCK/R/C
Feedback
References: SD-08 Rev.4, CRD Hydraulic System
A. Incorrect since the flow control valve will go closed since it is in automatic.
B. Correct answer.
C. Incorrect since the valve cannot be operated in the automatic mode locally without
input from Cl 1-FC-R600.
D. Incorrect since the valve can be operated in the manual mode locally.
Thursday, March 06, 2003 10:23:43 AM
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 C 11-FO02A was in automatic at 60 gpm prior to the failure.
Which ONE ofthe following describes how Flow Control Valve C 1I-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 C11 -FK-DO09A is taken to
manual and adjusted as necessary.
C. The Flow Control Valve will fully open until local controller C11 -FK-DO09A is taken
to manual and adjusted as necessary.
D. The Flow Control Valve will close and cannot be operated until controller
C11-FC-R600 is repaired.
85
QUESTIONS REPORT
iot-FINAL BSEP 2003-301 Written Exam
84. 295023AA2.02 001/T1G3/TIGI/FUEL POOL/C/A 3.4/3.7/N/BSEP 2003/C/TCK/R/C
Feedback
References: SD-13 Rev.2 pg 41
A. Incorrect since the Fuel Pool Cooling Pumps do not trip on skimmer surge tank high
level.
B. Incorrect since the adjustable weirs do not drain to Radwaste.
C. Correct answer.
D. Incorrect since the Fuel Pool Cooling Pumps do not trip on Fuel Pool high level.
Thursday, March 06, 2003 10:23:43 AM
86
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.
QUESTIONS REPORT
-orFINAL BSEP 2003-301 Written Exam
85. 295024EK3.01 0O1/T1G1/TIGI/DRYWELL SPRAYS/MEM 3.6/4.0/N/BSEP 2003/C/TCK/R/C
Feedback
References: CLS-LP-300-L Rev.1 pg 21,22,27-3 0
A. Correct answer.
B. Incorrect since only 95% of the non-condensibles are assumed to be in the
Suppression Chamber.
C. Incorrect since the Suppression Chamber to Drywell vacuum breakers will open and
the non-condensibles will be transferred back to the Drywell when sprays are initiated.
D. Incorrect since the Suppression Chamber spray interlock for low pressure will
prevent the Reactor Building to Suppression Chamber vacuum breakers from opening.
Thursday, March 06, 2003 10:23:43 AM
87
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.
QUESTIONS REPORT
ifor-PINAL BSEP 2003-301 Written Exam
86. 295025EA1.02 001/T1GI/T1G1/MAIN TURBINE/C/A 3.8/3.8/N/BSEP 2003/C/TCK/R/C
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
Feedback
References: SD-26.3 Rev. 2, EHC Electrical
A. Incorrect since the increase in PAM Pressure sends a signal to the control valves to
open.
B. Correct answer.
C. Incorrect since the PAM Pressure increases due to the increase in Reactor Power
from the loss of feedwater heating.
D. Incorrect since the PAM Pressure increases due to the increase in Reactor Power
from the loss of feedwater heating. Also, a decrease in PAM Pressure would cause the
control valves to close down.
Thursday, March 06, 2003 10:23:43 AM
88
QUESTIONS REPORT
-forFINAL BSEP 2003-301 Written Exam
87. 295025G2.1.20 001/TI GI//REACTOR PRESSURE/MEM 4.3/4.2/N/BSEP 2003/R/TCK/R
Feedback
References: APP A-05 3-5 Rev.43
A. Incorrect, since pressure peak requires a scram.
B. Correct answer.
C. Incorrect, since pressure peak requires a scram.
D. Incorrect since you only initiate a WR/JO for the indicator if it is suspected that it
malfunctioned.
Thursday, March 06, 2003 10:23:43 AM
Unit 2 is operating at 75% RTP when alarm APP A-05 3-5, REACTOR VESS HI
PRESS is received. After verifying that pressure peaked at 1065 psig you note that "C"
Main Steam Line Flow indicates downscale. No other abnormal indications exist.
Which ONE of the following describes the next action that should be taken for this
condition?
A. Close the MSIV's associated with the blocked steam line.
B." Immediately SCRAM the reactor.
C. Reduce reactor pressure to 1030 psig.
D. Initiate a WR/JO for the Main Steam Line Flow indicator.
89
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
88. 295025G2.4.4 00I//TiGi/EOP ENTRY/C/A 4.0/4.3/N/BSEP 2003/S/TCK/R/C
Feedback
References: EOP entry conditions
A. Incorrect since reactor water level is above +166 inches.
B. Incorrect since entry condition for Suppression Pool temperature with testing in
progress is 1050F.
C. Correct answer. Entry condition is reactor pressure >1060 psig.
D. Incorrect since Secondary Containment is not required even though new fuel is
being moved in containment. If irradiated fuel was being moved in containment then
this would be an entry condition.
Thursday, March 06, 2003 10:23:44 AM
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.
90
-QUESTIONSREPORT
-for-FINAL-BSEP 2003-301 Written Exam
89. 295026EK2.04 001/T1G2/TIG1/SUPPRESSION POOL/MEM 2.5/2.8/N/BSEP 2003/C/TCK/R
Feedback
Reference: SD-60 Rev.2, ERFIS DATA ACQUISITION, PROCESSING, AND DISPLAY
A. Incorrect since the temperature of the suppression pool is > 920F.
B. Incorrect since Temperature of the suppression pool is not > 950F.
C. Correct answer since the temperature of the suppression pool is > 950F.
D. Incorrect since all of the inputs to SPDS are operable.
Thursday, March 06, 2003 10:23:44 AM
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.
91
QUESTIONS REPORT
-forFINAL BSEP 2003-301 Written Exam
90. 295028EK1.01 001/TIG2/TIG2/DRYWELL TEMPERATURE/MEM 3.5/3.7/N/BSEP 2003/C/TCK/R
Unit 2 was operating at 100% RTP when a LOCA occurred.
maintained above TAF with the HPCI system. The following
Drywell:
Drywell pressure
Suppression Chamber pressure
Drywell temperature
Reactor pressure
Suppression Chamber sprays
Water level is being
conditions exist in the
8.0 psig
7.5 psig
275 OF
700 psig
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.
Feedback
References: SD-01.2 Rev.2 pg 38 and 39, Reactor Vessel Instrumentation
CLS-LP-01.2 Rev.1 Enabling Objective 5c
A. Incorrect since both instrument lines are the same length in the Drywell and the
indicated level error will be zero.
B. Incorrect since higher temperatures would cause the level to indicate higher since
there is less density. Since the instrument lines are of equal length then the level error
is zero.
C. Incorrect since both instrument lines are the same length in the Drywell and the
indicated level error will be zero.
D. Correct answer.
Thursday, March 06, 2003 10:23:44 AM
92
QUESTIONS REPORT
1'or FINALBSEP 2003-301 Written Exam
91. 295030EA1.05 001/T1G2/T1G1/SUPPRESSION POOL/MEM 3.5/3.5/N/BSEP 2003/C/TCK/R/C
Feedback
References: CLS-LP-300-L Rev.1 Figure 4
0-EOP-02-PCCP, Primary Containment Control Procedure
Enabling Objective CLS-LP-300-L Rev.1 #13
A. Incorrect since this is the level that is an entry condition to O-EOP-02-PCCP.
B. Incorrect since this is the level at which the downcomers are uncovered. The HPCI
Exhaust line is still covered.
C. Correct answer. This is the level at which the HPCI Exhaust line is uncovered.
D. Incorrect since this is the level at which the Tee Quenchers are uncovered.
Thursday, March 06, 2003 10:23:44 AM
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
93
QUESTIONS REPORT
-for-FINAL-BSEP 2003-301 Written Exam
92. 295031G2.1.1 001/T1G1/TIGI/REACTOR WATER LEVEL/C/A 3.7/3.8/N/BSEP 2003/C/TCK/R/C
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
RCIC system
SBGT system
Group 2
Group 3
Group 6
Group 8
currently injecting
in Standy alignment
isolated
operating normally
isolated
RWCU system in operation
isolated
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
band. RCIC operation is not required.
to the normal
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.
94
Thursday, March 06, 2003 10:23:44 AM
QUESTIONS-REPORT
forFINALBSEP 2003-301 Written Exam
Feedback
References: Conduct of Operations
A. Incorrect since RCIC failed to start and RWCU failed to isolate. Expectations are to
ensure automatic actions occurred or make them happen. RCIC operation is required.
B. Incorrect since RWCU system should be isolated thus, all required PCIS groups
have not isolated. HPCI may or may not be secured.
C. Incorrect since the Gr 2 isolation cannot be reset immediately due to reactor water
level. Also, RCIC and RWCU not addressed.
D. Correct answer. RCIC should have started automatically and RWCU should have
isolated automatically. Even though level is above the isolation or start level the
actions that should have happened still need to be taken.
Thursday, March 06, 2003 10:23:44 AM
95
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
93. 295032EK3.01 0O1/T1G3/TIG2/SECONDARY CONTAIN/MEM 3.5/3.8/B/BSEP 2003/C/LSM/R/C
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.
B. The rise in secondary containment parameters indicate substantial degredation of
the primary system and may lead to fuel failure if the leaks are not isolated.
C* The rise in secondary containment parameters indicate a wide-spread problem
which may pose a direct and immediate threat to secondary containment integrity or
equipment located in secondary containment.
D. The rise in secondary containment parameters indicate substantial degredation of
the primary system and emergency depressurization effectively isolates the leak.
Feedback
References: LR-LP-20325 Rev. 05, pg 19 and 20 of 40
EO 201.077.a.14, 201.078.a.15, 201.079.a.19
A. Incorrect since condition pose a DIRECT threat to containment, not an INDIRECT
threat.
B. Incorrect since this condition does not indicate substantial primary system
degredation.
C. Correct answer.
D. Incorrect since this condition does not indicate substantial primary system
degredation.
Thursday, March 06, 2003 10:23:44 AM
96
QUESTIONS-REPORT
tor-FiNAL-BSEP 2003-301 Written Exam
94. 295033G2.3.10 001//TIG2/SECONDARY CONTAIN/C/A 2.9/3.3/N/BSEP 2003/S/TCKIR/C
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.
Feedback
References: EOP-03-SCCP Rev.5
A. Correct answer. EOP-03-SCCP is entered at 90 mR/HR for ARM Channel 30. Since
no primary system is discharging into the reactor building then isolate systems as
required.
B. Incorrect since 2 or more areas are required to be above max safe with a primary
system discharging into the reactor building.
C. Incorrect since a primary system must be discharging into the reactor building.
D. Incorrect since
channel 30).
an entry condition exists for EOP-03-SCCP (>90 mR/HR for ARM
Thursday, March 06, 2003 10:23:44 AM
97
QUESTIONS REPORT
-for FINAL BSEP 2003-301 Written Exam
95. 295033G2.3.2 001/T1G2//RADIATION CONTROL/MEM 2.5/2.9/N/BSEP 2003/R/TCK/R/C
Feedback
References: OE&RC 0040, Administrative Controls for High Radiation Areas, Locked
High Radiation Areas and Very High Radiation Areas, Rev.22, pg 3 and 4.
A. Incorrect since RC Supervision cannot waive this prerequisite for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
B. Incorrect since the Operations Shift Superintendent cannot waive this prerequisite
unless an emergency exists.
C. Correct answer.
D. Incorrect since there is not a requirement that the TIP room cannot be entered for 72
hours after a TIP trace has been performed.
Thursday, March 06, 2003 10:23:44 AM
Unit 1 has just entered Mode 4 for a refueling outage. A set of TIP traces were run
approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago for the Nuclear Engineer. You note that a clearance for
the TIP system has not been performed as required by OE&RC 0040, Administrative
Controls for High Radiation Areas, Locked High Radiation Areas and Very High
Radiation Areas.
Which ONE of the following is required prior to entering the TIP room?
A. RC Supervision can waive this prerequisite after reviewing the scope of the work.
B. The Operations Shift Superintendent can waive this prerequisite due to the impact
on the outage.
Cý. The TIP system must be under clearance prior to entering the TIP room.
D. The TIP room cannot be entered for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> since entry into the room is prohibited
for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after TIP traces being performed.
98
QUESTIONS REPORT
-for-FINAL-BSEP 2003-301 Written Exam
96. 295034EK1.02 001/T1G2/T1G2/SECONDARY CONTAIN/C/A 4.1/4.4/N/BSEP 2003/C/TCK/R/C
Feedback
References: SD-37.1, Rev.4 pg 35, Reactor Building HVAC
A. Incorrect since the only path to the chimney is through SBGT and this is filtered
exhaust.
B. Incorrect since the isolation dampers are open and Rx Bldg Dp is zero.
C. Incorrect since the isolation dampers are still open and Rx Bldg Dp is zero.
D. Correct answer.
Thursday, March 06, 2003 10:23:45 AM
99
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.
QUESTIONSREPORT
-for FINAL BSEP 2003-301 Written Exam
97. 295035EK1.01 00!/TIG3//SECONDARY CONTAIN/MEM 3.9/4.2/N/BSEP 2003/R/TCK/R/C
Feedback
References: Tech Spec Section 3.6.4.1
A. Incorrect since Unit 1 can stay in Mode I for 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
B. Correct answer.
C. Incorrect BSEP does not have a common refuel floor.
D. Incorrect since Unit 2 cannot commence fuel moves until the blowout panel is
repaired and tested.
Thursday, March 06, 2003 10:23:45 AM
Unit 1 is in Mode I at 50% RTP. Unit 2 is in Mode 5 with preparations in progress to
commence core offload. Secondary containment has experienced a high differential
pressure and a blowout panel on Unit 2 has relieved the pressure. The panel will
require 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> to be repaired and tested.
Which ONE of the following describes the impact to both units for this condition?
A. Unit 1 must 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 />; Unit 2
cannot commence fuel movement until the blowout panel is repaired and tested.
B." Unit 1 is unaffected by the blowout panel on Unit 2; Unit 2 cannot commence fuel
movement until the blowout panel is repaired and tested.
C. Unit 1 must be in Mode 3 within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />; Unit 2 cannot commence fuel movement
until the blowout panel is repaired and tested.
D. Unit 1 must 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 />; Unit 2 can commence fuel movement for
up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> at which time fuel movement must be stopped.
100
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
98. 295037EK2.05 001/T I GI/T1G1/CRD/MEM 4.0/4.1/B/BSEP 2003/C/LSM/R/C
Feedback
Reference: LR-LP-20314 Rev. 03 pg 13
EO 001.034.a.01
A. Correct answer.
B. Incorrect. Additional pressure is placed on the underside of the drive piston.
C. Incorrect answer. Increasing cooling water Dp has no effect on drive flow.
D. Incorrect answer. Increasing cooling water Dp has no effect on drive flow.
Thursday, March 06, 2003 10:23:45 AM
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.
101
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
99. 295038EA2.03 001//T1G1I/I4GH RAD LEVEL/MEM 3.5/4.3/N/BSEP 2003/S/LSM/R/C
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.
Feedback
New
LESSON 2: LOI-CLS-LP-300-N
LESSON 2 OBJECTIVE: 07a, 11
Answer:
D
Thursday, March 06, 2003 10:23:45 AM
102
QUESTIONS REPORT
- orFINALBSEP 2003m301 Written Exam
100. 300000K3.02 001/T2G2/T2G2/INSTRUMENT AIR/C/A 3.3/3.4/M/BSEP 2003/C/LSM/R/C
Feedback
416.
LOI-CLS-LP-032-A*09A003
Thursday, March 06, 2003 10:23:45 AM
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.
103
QUESTIONS REPORT
for-FINAL BSEP 2003-301 Written Exam
101. 400000G2.2.18 001//T2G2/MAINTENANCE/C/A 2.3/3.6/N/BSEP 2003/S/LSM/R/C
Feedback
LOI-CLS-LP-029-A*02H001
Thursday, March 06, 2003 10:23:45 AM
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.
104
QUESTIONS-REPORT
for FINALJBSEP 2003-301 Written Exam
102. 500000EA2.01 00I/T1G1/TlGI/CONTAINMENT HYDROGEN/C/A 3.1/3.5/N/BSEP 2003/C/TCK/R/C
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).
Feedback
References: SD-24 Rev.3, Containment Atmospheric Control System
A. Incorrect since the CAM system is available for sampling and is required to be
placed in service per EOP-02-PCCP.
B. Incorrect since these control switches do not allow the CAM sample valves to be
re-opened.
C. Correct answer.
D. Incorrect since EOP-02-PCCP require hydrogen monitoring regaurdless of water
level.
Thursday, March 06, 2003 10:23:45 AM
105
QUESTIONS REPORT
for-INAL BSEP 2003-301 Written Exam
103. 600000AA2.02 001/T1G2//CONTROL ROOM VENTS/MEM 2.8/2.9/N/BSEP 2003/R/TCK/R/C
Smoke has been detected in an area that causes the Control Room Ventilation System
dampers to reposition.
Which ONE of the following describes the expected damper positions for this situation?
A. Washroom exhaust damper closes; emergency recirc damper closes; normal
makeup damper opens.
B. Washroom exhaust damper opens; emergency recirc damper opens; normal
makeup damper closes.
C. Washroom exhaust damper opens; emergency recirc damper closes; normal
makeup damper opens.
D0. Washroom exhaust damper closes; emergency recirc damper opens; normal
makeup damper closes.
Feedback
References: SD-37, Control Building Heating, Ventilation and Air Conditioning System,
Rev.4, pg.34
A, B and C are incorrect since the washroom exhaust damper closes, the emergency
recirc damper opens and the normal makeup damper closes.
D. Correct answer.
Thursday, March 06, 2003 10:23:45 AM
106
QUESTIONS-REPORT
for FINAL-BSEP 2003-301 Written Exam
104. 600000AA2.06 00 1//T I G2/FIRE PROTECTION/MEM 2.5/2.8/N/BSEP 2003/S/TCK/R
Feedback
References: SD-37, Rev.4 pg 27 and 34
B. Correct answer.
A, C and D. Incorrect since it takes a combination of smoke or manual pull stations in
zone C4 and C5.
Thursday, March 06, 2003 10:23:45 AM
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.3 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.
107
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
105. GEN 2.1.1 OOI/T3/T3/FLOW MAP/MEM 3.7/3.8/M/BSEP 2003/C/LSM/R/C
If operating 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'd Increasing recirculation flow.
D. Removing a feedwater heater string from service.
Feedback
C: Rod withdrawal would raise power and move you vertically on the map; reducing
flow would drive you toward the Restricted Region; removing a feedwater string would
increase the chance for instability where you are in the map (flux tilt).
Not modified.
REFERENCES: OENP-24.0
Answer:
C
LOI-CLS-LP-201-G*03E001
S..
.........
....
- ~
n.n.~.At AA
^108
I nursday, March UO, 2UU3 iu c3:qo ,iv
QUESTIONS REPORT
for-FINAL BSEP 2003-301 Written Exam
106. GEN 2.1.10 002/T3/T3/COLR/C/A 2.7/3.9/B/BSEP 2003/C/LSM/R/C
Feedback
References: CLS-LP-106-A*013
001
MCPR OL increases with exposure since rod density is lower at EOC, therefore longer
time to complete a scram in the event of a transient.
Operation at lower power w/ flow given increases MCPR OL since operation is further
away from APRM flow bias scram setpoint. (MCPRp higher @ lower power)
MCPRf is lower at higher flow to protect against a recirc pump runaway transient.
Same reasoning is true for the mechanical stop setpoint.
Thursday, March 06, 2003 10:23:46 AM
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.
109
QUESTIONS REPORT
-for FINAL BSEP 2003-301 Written Exam
107. GEN 2.1.12 001//T3/MAINTENANCE/C/A 2.9/4.0/N/BSEP 2003/S/LSM/TCK/R/C
Feedback
References: Tech Spec 3.6.1.2
LOI-CLS-LP-004
A. Incorrect since you do not have to go to Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
B. Correct answer.
C. Incorrect since the interlock is not inoperable for other reasons than for a door.
D. Incorrect since you do not have the option to post a guard and you do not have to
have the door repaired within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Thursday, March 06, 2003 10:23:46 AM
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 />.
110
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
108. GEN 2.1.28 001/T3/T3/TS/MEM 3.2/3.3/BiBSEP 2003/C/LSM/R/C
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.
Feedback
References: LOI-CLS-LP-002-A*035001
-..
.
.....
a.... .......
A
111
Thursday, Marcn u0, LUU3 1Iu:2,.:. GlVI
QUESTIONS-REPORT
-for FINAL BSEP 2003-301 Written Exam
109. GEN 2.2.12 001/T3//SURVEILLANCE/MEM 3.0/3.4/N/BSEP 2003/RILSM/R/C
Feedback
A. This is the correct configuration
B. The mechanical interlock is not working incorrectly
C. This is not a knife switch breaker
D. This is not a knife switch breaker
Switchyard Panels 7A, 7B, 8A, and 8B have walking beam type interlocks externally
mounted to the back of the breakers. When one of the breakers is closed, the walking
beam interlock forces the alternate breaker to open.
Thursday, March 06, 2003 10:23:46 AM
You have been directed to perform OPT-12.6, Breaker Alignment Surveillance step
7.39, Outside Area - 125Volt DC Panel Interlock Check.
On distribution panel 7A you find the normal feeder breaker from the 125/250 Vdc 1A
in the closed position. Which one of the following describes the reason you find the
Alternate feeder breaker in the open position?
AX The mechanical interlock is working properly.
B. The mechanical interlock has been improperly installed on the breakers.
C. The knife switch breaker is working properly.
D. The knife switch breaker has been improperly installed on the breakers.
112
QUESTIONS REPORT
-or-FINAL BSEP 2003-301 Written Exam
110. GEN 2.2.13 001/T3//TAGGING/MEM 3.6/3.8/N/BSEP 2003/R/LSM/R/C
Feedback
OPS-NGGC-1 301 rev 10 pages 68 - 70
A. Per OPS-NGGC-1 301 butterfly valves and flow control valves require that you
monitor for seat leakage. Can not be used as isolation.
B. Correct
C. Limitorque valve
D. Hydraulic Operated valve
Thursday, March 06, 2003 10:23:46 AM
You have been asked to place a boundary device tag on a butterfly valve. This valve
is air operated, fails closed, and is primarily used for flow control. According to
OPS-NGGC-1 301, which one of the following describe the restrictions associated with
using this valve for a tagging boundary?
A. Cannot be used for a tagging boundary.
B" Should be monitored for seat leakage.
C. Should be monitored for drift.
D. A mechanical positioning device or a gag is REQUIRED.
113
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
111. GEN 2.2.14 001//T3/ADMIN/MEM 2.1/3.0/B/BSEP 2003/S/LSM/R/C
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.
Feedback
REFERENCES: PRO-NGGC-0204 rev. 2
114
Thursday, March 06, 2003 1U0:2:46 AM
QUESTIONSREPORT
for-FINAL BSEP 2003-301 Written Exam
112. GEN 2.2.17 001//T3/MAINTENANCE/C/A 2.3/3.5/N/BSEP 2003/S/LSM/R/C
Feedback
Reference allowed
OAI-107
Per attachment 2 for moderate work (this meets the definition of moderate work per
attachment 1) in this temperature, the maximum stay time is 20 minutes. Three
workers at 20 minutes is 1 man hour- required rest period is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (per formula on
page 12). There is still one man hour of work to be completed which will take 20
minutes for the three workers. Total time 20 minutes + 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> rest + 20 minutes = I
hour 40 minutes
Thursday, March 06, 2003 10:23:46 AM
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 0A1-1 07, which ONE of the following is the
shortest duration for this task?
A. 20 minutes
B. 35 minutes
C. 80 minutes
Dt. 100 minutes
115
QUESTIONS REPORT
-for FINAL BSEP 2003-M301 Written Exam
113. GEN 2.2.27 001//T3/REFUELING/C/A 2.6/3.5/M/BSEP 2003/S/LSM/R/C
Feedback
References: based on LOI-CLS-LP-013-A*16B
Thursday, March 06, 2003 10:23:46 AM
You are the refueling floor SRO. Unit I 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?
At 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.
116
QUESTIONS REPORT
for FINALBSEP 2003-301 Written Exam
114. GEN 2.2.3 OO1/T3/T3/UNIT DIFFERENCES/MEM 3.1/3.3/N/BSEP 2003/C/LSM/R/C
Feedback
SD-03
Solution - A, B, and C are Unit 2 only features
Thursday, March 06, 2003 10:23:46 AM
Which one of the following is a feature of Unit I 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.
Dt. When not in "Run" an IRM upscale will provide an RPS trip. There is no APRM
downscale RPS trip.
117
QUESTIONS REPORT
IforFINAL-BSEP 2003-301 Written Exam
115. GEN 2.3.1 001/T3/T3/RADWASTE/MEM 2.6/3.0/B/BSEP 2003/C/LSM/R/C
A rupture has occurred on the end-bell (tube side) of a TBCCW heat exchanger.
Which ONE of the following color floor drain hubs should leakage be routed to?
A. YELLOW
B. BLACK
C. GREEN
D. RED
Feedback
-.....
... ..
.
.
.
Onno *.4f
.AV ARA
118
I nursday, Mavchl Up, 40uuo Iuvaot ilyl
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
116. GEN 2.3.11 00 I/T3//RAD RELEASE/MEM 2.7/3.2/M/BSEP 2003/R/LSM/R/C
Feedback
119
Thursday, March 06, 2003 10:23:47 AM
Unit 2 is at 89% power when the Reactor Building Vent Exhaust Rad Monitor N01 OA
fails upscale. Shortly after you override the CAC isolation due to the Rad Monitor
N01OA failing upscale , a Unit I Main Stack Rad Hi Hi signal initiates. Assuming all
automatic actions occur, which one of the following describe how you would isolate the
CAC system?
A. All group 6 CAC valves would remain open, and would require manual closure.
B. Only inboard group 6 CAC valves would close and the outboard valves would
require manual closure.
C. Only outboard group 6 CAC valves would close and the inboard would require
manual closure.
i% All
-*n*, ,**
CA
valv*s wnold automaticallv close.
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
117. GEN 2.3.4 001//T3/RAD MONITORING/CA 2.5/3.1/N/BSEP 2003/S/LSM/R/C
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.
................~
....... ~ A,
120
I nursday, Marcn u0, 2uu3 10u;o;
3:
lVi
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
Feedback
SRO ONLY
Based on a previous bank question
LOI-CLS-LP-102-A*I 1B001
The exposure limit listed in EPA 400 Emergency Work Limits to protect valuable equipment is
10 Rem TEDE. The approval to receive this dose while performing an onsite function can be
granted by the Site Emergency Coordinator (SEC)
EPA 400 Emergency Work Limits
Approval Required
A.
Site Emergency Coordinator (SEC)
B.
Emergency Response Manager (ERM)
C.
Site Emergency Coordinator (SEC)
D.
Emergency Response Manager (ERM)
Answer:
C
LOI-CLS-LP-102-A*l 1B001
The exposure limit listed in EPA 400 Emergency Work Limits to protect valuable
equipment is
. The approval to receive this dose while performing an onsite
function can be granted by the
EPA 400 Emergency Work Limits
Approval Required
A.
Site Emergency Coordinator (SEC)
B.
Emergency Response Manager (ERM)
C.
Site Emergency Coordinator (SEC)
D.
Emergency Response Manager (ERM)
Answer:
C
Thursday, March 06, 2003 10:23:47 AM
121
QUESTIONS REPORT
for-FINAL BSEP 2003-301 Written Exam
118. GEN 2.4.1 001/T3/T3/SHUTDOWN/C/A 4.3/4.6/B/BSEP 2003/C/LSM/R/C
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.
Feedback
Answer:
B
bank - LOI-CLS-LP-300-B*008001
122
Thursday, March u0, 2uu,10 u:*3:47
lVi
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
119. GEN 2.4.11 001/T3//RPIS/MEM 3.4/3.6/B/BSEP 2003/R/LSM/R/C
Feedback
A.
REFERENCES: AOP-02.0 R7
Answer:
A
Bank -
LOI-CLS-LP-302-B*003001
123
Thursday, March 06, 2003 10:23:47 AM
A Unit 2 startup is in progress per GP-02. The reactor has been declared critical. The
control operator is withdrawing control rods to achieve a stable positive period of 100
seconds.
Circuit Breaker #1 on Distribution Panel V1 A trips resulting in a loss of power to the
RPIS cabinet. The control operator should immediately do which one of the following?
A0 Stop any power changes in progress.
B. Insert a manual reactor scram and enter EOP-01-RSP.
C. Use the Process Computer to determine Control Rod position.
D. Insert Control Rods to shutdown the Reactor by inserting 10 control rods past
where it was declared critical.
Feedback
Feedback
QUESTIONS- REPORT
for FINALBSEP 2003-301 Written Exam
120. GEN 2.4.11 002//T3/CRD/C/A 3.4/3.6/N/BSEP 2003/S/LSM/R/C
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.
Feedback
Scram normally combination of HCU and RPV pressure during normal operation. At
low RPV pressure, scram relies only on HCU pressure, therefore if CRD cannot
maintain HCU pressure, a manual scram is required before HCU pressure bleeds off
through check valves
.
.
. ..
-
an nn
f...... Ao.,
A
^,,
124
I nursday, March uo, LUUO iu;0o.2:,
AVI
QUESTIONS REPORT
-for-FINAL-BSEP 2003-301-Written Exam
121. GEN 2.4.18 001/T3/T3/EOP BASIS/C/A 2.7/3.6/B/BSEP 2003/C/LSM/R/C
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.
Feedback
References: LOI-CLS-LP-002-A*019002
Thursday, March 06, 2003 10:23:47 AM
125
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
122. GEN 2.4.2 001/T3/T3/BLACKOUT/C/A 3.9/4.1/B/BSEP 2003/C/LSM/R/C
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
RPV pressure
Drywell ref leg temp
Injection sources
-55 inches (N036)
300 psig
315 OF
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.
Feedback
BSEP PROVIDE APPROPRIATE REFERENCE IF REQUIRED
5.
LOI-CLS-LP-300-B*008004
126
Thursday, March 06, 2003 10:23:47 AM
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
123. GEN 2.4.27 002//T3/SAFE SHUTDOWN/C/A 3.0/3.5/N/BSEP 2003/S/LSM/R/C
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.
Feedback
Opening specified breakers disables HPCI flow control circuitry to prevent uncontrolled
injection, removes power from SRV solenoids (but does not prevent operation from
alternate circuitry @ RSDP) and MSIV solenoids to establish high/low pressure
interface. Will remove power from normal RCIC circuitry, but alternate power @ RSDP,
has no impact on drywell coolers
...
.
..
.
127
Thursday, March U0, 2uu. 1U:2L3,:4
IVl
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
124. GEN 2.4.3 001/T3/T3/SCRAM/C/A 3.5/3.8/M/BSEP 2003/C/LSM/RIC
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" (N0O4A/B/C)
RPV water level
+160" (N027A/B)
RPV water level may be determined using which ONE of the following?
A'ý 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.
Feedback
Bank LOI-CLS-LP-300-B*016001
N026A/B cannot be used with Rx Bldg 50' temp above 140 degrees F. N027A/B are
below minimum indicated level, N036/37 cannot be used with Recirc Pumps running.
EOP-01-UG Attachment 6 (Caution 1) to be provided as reference.
Answer:
A
..............
128
Thursday, Marcn u0, 2uu3 iu;,34LO:l
dVl
QUESTIONS REPORT
for FINAL BSEP 2003-301 Written Exam
125. GEN 2.4.48 001//T3/1NDICATIONS/C/A 3.5/3.8/N/BSEP 2003/S/LSM/R
Unit I 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.
Dt Rx Vessel Water Level Low LLI.
Feedback
References: LOI-CLS-LP-012-A
LOI-CLS-LP-004-B
129
Thursday, March U0, 2003 1u:23:48 MLVI