ML030840218
| ML030840218 | |
| 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: ML030840218 (142) | |
See also: IR 05000325/2003301
Text
Draft Submittal
(Pink Paper)
BRUNSWICK EXAM
50-2003-301
50-325 & 50-324
FEBRUARY 10 - 13 & 19, 2003
DRAFT Combined RO/SRO Written Exam
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
1. 201001K1.0l 001
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.11
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.
Notes
Response form
Categories
Keyword: CONTROL ROD DRIVE Cog Level: MEM 3.1/3.1
Source: N Exam: BSEP 2003
Test: R Misc: TCKIR/C
Thursday, February 06, 2003 03:05:43 PM I
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
2. 201002A3.03 001
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-007-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: 1Od
REFERENCES: SD-07*
Notes
Response form
Categories
Keyword: RMCS Cog Level: C/A 3.2/3.2
Source: B Exam: BSEP 2003
Test: C Mise: LSM/R/C
Thursday, February 06, 2003 03:05:43 PM 2
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
3. 201002K3.01 001
Which ONE of the following is the result of a total loss of 28 VDC from 120Vac Vital
UPS to Unit 1?
Af 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 Ni's.
Notes
24/48Vdc supplies are actually at 28Vdc with charger voltage, Stem clarification
necessary.
Response form
Categories
Keyword: RMCS Cog Level: C/A 3.4/3.4
Source: N Exam: BSEP 2003
Test: R Misc: TCK/R/C
Thursday, February 06, 2003 03:05:43 PM 3
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
4. 201002K402 001
Which ONE of the following describes the conditions under which the "Rod Select
Permissive" light is illuminated?
Af 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 onwith no rods selected or rod select power off.
Notes
Response form
Categories
Keyword: FUEL HANDLING Cog Level: MEM 3.5/3.5
Source: B Exam: BSEP 2003
Test: C Misc: LSM/TCK/R/C
Thursday, February 06, 2003 03:05:44 PM 4
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
5. 201003A2.09 001
Unit 2 is 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 505OF
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/Mispositionif 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.
D. 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.
Notes
700 psiq saturation temp 505F
Response form
Thursday, February 06, 2003 03:05:44 PM 5
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
Categories
Keyword: CRD SYSTEM Cog Level: C/A 3.2/3.4
Source: N Exam: BSEP 2003
Test: R Misc: TCKIR/C
Thursday, February 06, 2003 03:05:44 PM 6
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
6. 201003K3.01 001
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.
B0 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.
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.
Notes
4 Rod Display removed with PRNM mod.
Response form
Categories
Keyword: CONTROL ROD DRIVE Cog Level: C/A 3.2/3.4
Source: N Exam: BSEP 2003
Test: R Misc: TCK/R/C
Thursday, February 06, 2003 03:05:44 PM 7
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
7. 201006G2.2.12 001
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.
Cf 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.
Notes
Response form
Categories
Keyword: ROD WORTH MINIMIZER Cog Level: C/A 3.0/3.4
Source: N Exam: BSEP 2003
Test: R Misc: TCK/R/C
Thursday, February 06, 2003 03:05:44 PM 8
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
8. 202001A1.07 001
Unit Two was 95% power when annunciator A-07 2-2, REACTOR WATER LEVEL
HIGH/LOW, alarmed. Feed pump "B"-FlowController is in manual following erratic
operation in automatic. Plant conditions are:
Reactor power 83% lowering
Reactor water level +180 inches rising
fZ) (.:&*
R-eczA~
Feedwater Flow A 5.3 Mlbs/hr
Focedwater-Fluw B3 0.9 Mlbs/hr
'er &4b&ý
Recirc Pump A Speed 63% lowering
Recirc Pump B Speed 70% lowering
Core Flow 59 Mlbs/hr lowering
Which ONE of the following describe the actions that should be taken?
A. Lock the scoop tube for the 'A' Recirc pump; monitor for Thermal Hydraulic
Instabilities.
B. Lock the scoop tubes of both recirc pumps and then monitor for Thermal Hydraulic
Instabilities.
C" After level is restored, adjust recirc pump potentiometers to match demand and
speed, and reset runback.'
D. Take manual control of recirc pump speeds and ensure that a mismatch of greater
than 10% does not occur.
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
Notes
reworded C to match OP-02
Response form
Categories
Keyword: RECIRC SYSTEM Cog Level: C/A 2.7/2.8
Source: B Exam: BSEP 2003
Test: C Misc: LSM/R/C
Thursday, February 06, 2003 03:05:44 PM 9
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
9. 202002K4.06 001
Unit Two (2) is in Mode 1, in an active LCO for Recirculation Pump 2A out of service.
Preparations are-ln-progress to restart Recirculation Pump 2A per OP-O 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 410°F
Recirc loop A temp 486 0 F
Recirc loop B temp 522 0 F
Recirc loop B flow 25,800 gpm
Which ONE of the following is correct concerning the restart of Recirculation Pump
2A?
A. It may continue, all requirements are met.
B. It may NOT continue, the Delta T between the operating and the idle loop is
excessive.
C. It may NOT continue, the Delta T between the coolant in the dome and bottom
head is excessive.
W. 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 <50OF.
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.
Notes
Response form
Thursday, February 06, 2003 03:05:44 PM 10
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
Categories
Keyword: RECIRC SYSTEM Cog Level: C/A 3.1/3.1
-Source: M Exam: BSEP 2003
Test: . -C........ Misc: LSM/TCK/R/C------
Thursday, February 06, 2003 03:05:44 PM 11
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
1f02 Y0f000ALO.4 001
10 20300OAl 04 001
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?
Af 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. Ifthe 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.
Notes
Response form
Thursday, February 06, 2003 03:05:44 PM 12
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
Categories
Keyword: RHR SYSTEM Cog Level: C/A 3.6/3.3
Source: N Exam: BSEP 2003
Test: C Misc: LSM/TCK/R/C
Thursday, February 06, 2003 03:05:44 PM 13
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
11. 204000K1.06 001
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-FOOI is
opened and you have lost condenser vacuum.
Which ONE of the following could have caused the above?
Af 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-012-A*04CO01
Which of the following signal(s) will cause the Group 3 PCIS RWCU outboard isolation
valve (G3 1-F004) to close, yet leaves the inboard isolation valve (G31-FOO1) 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*09FO02
Following a reactor scram the Reactor operator places RWCU in the reject mode of
operation to aid in level control. The operator is cautioned not to open the parallel paths to the
Thursday, February 06, 2003 03:05:44 PM 14
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
main condenser and radwaste to avoid:
A. voiding of RWCU piping.
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
RPV pressure 200 psig
MSIVs open
Condenser vacuum 26" Hg.
Which of the following would result from the established lineup?
A. A loss of condenser vacuum.
B. RWCU Reject FCV, F033, closure on high pressure.
C. Reduced RWCU pressure and increased demineralizer delta-pressures.
D. RWCU Isolation on Non Regenerative Heat Exchanger high outlet temperature.
Answer:
A
Thursday, February 06, 2003 03:05:44 PM 15
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
12. 204000K5.04 001
Unit 2 is at 10% power with RWCU filter demin in service and RWCU reject flow in
-progress.
Which ONE of the following is correct concerning the PPC heat balance if Process
Computer Point B074, RWCU Inlet Flow, is NOT available?
The PPC heat balance will be:
A' up to 3 CMWT lower than actual reactor power because computer points only get
input from RWCU filter demin flow.
B. up to 6 CMWT lower than actual reactor power because computer points only get
input from RWCU temperature.
C. up to 3 CMWT higher than actual reactor power because computer points only get
input from RWCU filter demin flow.
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.
Notes
Response form
Categories
Keyword: RWCU Cog Level: C/A 2.7/2.7
Source: N Exam: BSEP 2003
Test: C Misc: LSM/R/C
Thursday, February 06, 2003 03:05:44 PM 16
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
13. 205000A3.01 001
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 2650 F
Shutdown cooling 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 235 0 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.
BV remain sn Shutdown Cooling; B loop RHR aligns for injection immediately; B loop
RHR in ects 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.eocrr cC
B...l.cerrect sinc .A.RHR locp. .... nt iu,*l in,thehu tdowun,,, ,o.,O ,,ug ode
C. Correct answer.
D. Incorrect since A RHR loop does not inject and B RHR loop aligns and injects.
Notes
changed correct answer to B
Thursday, February 06, 2003 03:05:44 PM 17
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
Response form
Categories
Keyword: SHUTDOWN COOL Cog Level: C/A 3.2/3.1
Source: N Exam: BSEP 2003
Test: R Misc: TCK/R/C
Thursday, February 06, 2003 03:05:45 PM 18
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
14. 206000K5.08 001
Which ONE of the following components prevents water from being forced up the HPCI
exhaust line as-the suppression pool pressurizes during a LOCA?
Af 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 th'e
exhaust line.
Notes
Response form
Categories
Notes
Categories
Response
Keyword: HPCISYSTEM Cog Level: MEM 3.0/3.2
Source: N Exam: BSEP 2003
Test: C Misc: TCK/R/C
Thursday, February 06, 2003 03:05:45 PM 19
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
15. 209001K2.03 001
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.
Feedback
BSEP BANK 132. LOI-CLS-LP-018-A*15FO03
Notes
Distractor since was not correct since HPCI will actuate from Div I instruments.
Changed to Drywell coolers B and C will not trip.
Response form
Categories
Keyword: CORE SPRAY Cog Level: C/A 2.9/3.1
Source: B Exam: BSEP 2003
Test: C Misc: LSM/R/C
Thursday, February 06, 2003 03:05:45 PM 20
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
16. 211000A3.08 001
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.
Notes
Response form
Categories
Keyword: SBLC Cog Level: MEM 4.2.4.2
Source: B Exam: BSEP 2003
Test: C Misc: LSM/TCK/R
Thursday, February 06, 2003 03:05:45 PM 21
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
17. 212000G2.1.27 001
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.
BW 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.
Notes
Reworded for SRI purpose only on Unit Two. SRI is configured to provide full scram if
auto initiated. Manual SRI is authorized in specific AOPs. Reworded distractor B.
Reworded D since RPS instruments feed PCIS. Changed to ECCS.
Response form
Categories
Keyword: REACTOR PROTECTION Cog Level: MEM 2.8/2.9
Source: N Exam: BSEP 2003
Test: R Misc: TCK/R/C
Thursday, February 06, 2003 03:05:45 PM 22
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
18. 212000K6.04 001
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.
Cf 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
Notes
Specified panel number to clarify stem.
Response form
Categories
Keyword: RPS Cog Level: C/A 2.8/3.1
Source: M Exam: BSEP 2003
Test: C Misc: LSM/R/C
Thursday, February 06, 2003 03:05:45 PM 23
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
19. 214000K4.01 001
Which ONE of the following explains why a "ROD DRIFT" alarm is received after
moving a control rod using the "EMERGENCY IN"switch?
A. "EMERGENCY IN"bypasses the Rod Position Indication System.
B. The sequence timer is bypassed causing an insert and withdraw signal at the same
time.
C. The rod is at an even reed switch and none of the selected relay busses are
energized (insert, withdraw or settle).
D. The rod is at an odd reed switch and none of the selected relay busses are
energized (insert, withdraw or settle).
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.
Notes
Notegois
Response form
Categories
Keyword: REED SWITCH Cog Level: MEM 3.0/3.1
Source: B Exam: BSEP 2003
Test: C Misc: LSM/R/C
Thursday, February 06, 2003 03:05:45 PM 24
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
20. 215001A2.01 001
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.
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 IIsignal.
D. Correct answer.
Notes
added 0.6 psig.
Response form
Thursday, February 06, 2003 03:05:45 PM 25
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
Categories
Keyword: TIP SYSTEM Cog Level: C/A 2.7/2.9
Source: Exam: BSEP 2003
Test: R Misc: LSM/TCK/R/C
Thursday, February 06, 2003 03:05:45 PM 26
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
21. 215002K6.04 001
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. Correct answer since a control rod has been selected and the null sequence is
complete. APRM 1 (RBM reference APRM) going downscale generates a bypass signal
for RBM A.
B. Incorrect since APRM 1 is the reference APRM for RBM A so RBM B is unaffected.
C. Incorrect since RBM A is bypassed.
D. Incorrect since RBM B is not affected.
Notes
changed correct answer to C, RBM will AUTO select APRM 3 with APRM 1 failed
downscale.
Response form
Categories
Keyword: ROD BLOCK MONITOR Cog Level: C/A 2.8/3.0
Source: N Exam: BSEP 2003
Test: R Misc: TCK/R/C
Thursday, February 06, 2003 03:05:45 PM 27
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
22. 215003A4.07 001
Unit I 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 1
IRM C 21 on Range 2 IRM G 23 on Range 2
IRM D 25 on Range I IRM H 20 on Range I
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.
Bf 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.
Notes
Changed stem "The operator takes the Range Switch for IRM B to Range 2" to Range
3. This ensures that IRM B should be below downscale setpoint of 5 +/- 1.5, which
should cQenerate a Rod Block.
Response form
Notes
Categories
Keyword: IRM Cog Level: C/A 3.6/3.6
Source: N Exam: BSEP 2003
Test: R Misc: TCK/R/C
Thursday, February 06, 2003 03:05:45 PM 28
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
23. 215004 G2.2.1 001
Unit 1 is in the process of performing OGP-01, PrestartupChecklist step 6.2.9, Source
Range Monitor Checks.
Which ONE of the following describes the minimum requirements for the SRM's?
A. Ensure at least 2 SRM channels are OPERABLE and indicate > 5 cps.
B. Ensure at least 2 SRM channels are OPERABLE and indicate > 10 cps.
Cf 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.
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.
Notes
Response form
Categories
Keyword: SOUREC RANGE MONITOR Cog Level: MEM 3.7/3.6
Source: N Exam: BSEP 2003
Test: C Misc: TCK/R/C
Thursday, February 06, 2003 03:05:45 PM 29
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
24. 215005A4.06 001
Unit 1 is in Mode 2 with the Mode Switch in START/HOT STBY. Annunciator APP
A-05 2-2, ROD OUT BLOCK, is in alarm. APRM readings are as follows:
APRM 1 13%
APRM 2 Downscale
APRM 3 15%
APRM 4 14%
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.
D. 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. Correct answ
C. Incorrect since 2 Scram should have occurred due to APRM 3 at the upscale trip
setpoint.
D. I rrec§ since a 1/2 Scram should have urred due to APRM 3 at the upscale trip
setpoint.
Notes /
Changed Unit Two to Unit One. Changed correct nswer to D as only APRM 3 at or
exceeding the APRM UPSCL setpoint, downsc e is not a RPS trip, two concurrent
APRM trips required for full scram.
Response form
Thursday, February 06, 2003 03:05:45 PM 30
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
Categories
Keyword: APRM SYSTEM Cog Level: C/A 3.6/3.8
Source: N Exam: BSEP 2003
Test: C Misc: TCK/R/C
Thursday, February 06, 2003 03:05:46 PM 31
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
25. 216000K2.01 001
If the Topaz Inverter in Analog Trip Cabinet XU-68 (RPS B-2) had an open circuit and
failed,-thenwhich ONE of the following should occour?-
Af There will be no interruption of power to cabinet XU-68 as the power supply in
XU-67 (RPS B-I) will provide power to both cabinets.
B. There will be no interruption of power to cabinet XU-68 as there is a second Topaz
Inverter in panel XU-68 that is in parallel with the Topaz Inverter that failed.
C. All associated instruments will lose power generating a trip signal. There will be a
1/2 scram and Group 1 PCIS as well as valve actuation for PCIS Groups 2, 6 and 8.
D. All associated instruments will lose power but will not generate any trip signals. The
plant will continue to operate, but Tech Specs should be addressed for each
instrument.
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 I 8-A tO09004
REFERENCES: SD-02,
Notes
Response form
Categories
Keyword: INSTRUMENTATION Cog Level: MEM 2.8/2.8
Source: B Exam: BSEP 2003
Test: C Misc: LSM/R/C
Thursday, February 06, 2003 03:05:46 PM 32
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
26. 217000G2.1.28 001
Which ONE of the following is correct concerning the RCIC Steam Supply Inboard
Isolation Valve (E51-F007)?
Af 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.
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.
Notes
Response form
Categories
Keyword: RCIC SYSTEM Cog Level: MEM 3.2/3.3
Source: N Exam: BSEP 2003
Test: C Misc: TCK/R/C
Thursday, February 06, 2003 03:05:46 PM 33
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
27. 217000K1.01 001
Unit 2 is operating at 80% RTP. The RCIC system is in standby with a suction from the
-CST.-The quarterly-H PCI flow rate test is in progress and is taking longer than
expected. Torus level has reached -24" and preparations are being made to pump the
torus down to normal level within the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Tech Spec time limit.
Which ONE of the following describes the effect high Torus level had on RCIC?
A" No effect since the RCIC suction valves do not transfer on high torus level.
B. The Torus suction valves (F029 & F031) received an open signal and once both
valves were full open then the CST suction valve (F010) received a closed signal.
C. The Torus suction valves (F029 & F031) received an open signal at the same time
the CST suction valve (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.
Feedback
References: SI-LP-03901 Rev. SI-00 pg 10 of 37
A. Incorrect since the U2 RCIC suction swap takes place at a suppression pool level of
150.5" Unit 1 takes place at 152".
B. Correct answer.
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.
Notes
Modified torus level to match BNP. Modified and selected A as correct answer since
RCIC suction does not transfer on high torus level at BNP.
Response form
Categories
Keyword: RCIC Cog Level: C/A 3.5/3.5
Source: B Exam: BSEP 2003
Test: C Misc: LSM/R/C
_. , .- L. -.... o,,oa a.or.Ao.oA 34
I Tursaay, FeDruary u0, 0UUO 03:U0o;: 6V'
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
28. 218000A4.02 001
28 218000 02001
Unit Two just entered a shutdown LCO due to HPCI and RCIC being inop, when a
Loss of Off-site-Power o-ccurs._EDGs 3 and-4fail 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 of the following describes how ADS
would respond to #4 EDG starting?
7 ADS valves would auto open __ seconds after the diesel tied to E4.
Af 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
Notes
Response form
Categories
Keyword: ADS Cog Level: C/A 4.2/4.2
Source: B Exam: BSEP 2003
Test: C Misc: LSM/R/C
Thursday, February 06, 2003 03:05:46 PM 35
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
29. 219000A2.03 001
29 21900 203001
Unit Two is in RHR/LPCI suppression pool cooling mode with an elevated suppression
pool temperature of 180 0 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.P NLtRHR Pump Seal temperatureLincreased.
B.OONLY RHR SW Pump Motor temperatures increased.
C. BOTH RHR Pump Seal temperatureand RHR SW Pump Motor temperatures
increased.
D. NEITHER RHR Pump Seal temperature6 NOR RHR SW Pump Motor temperatures
all have increased.
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
Answer: D)))
Notes
RHR pump seal coolers are only necessary for elevated suction temperatures such as
in SDC. Room temperature may or may not increase depending on if room cooler were
running. Modified distractor to make all plausible with one correct answer.
Response form
Categories
Keyword: RHR SYSTEM Cog Level: C/A 3.1/3.2
Source: N Exam: BSEP 2003
Test: C Misc: LSM/R/C
Thursday, February 06, 2003 03:05:46 PM 36
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
S0_
30
223001 A2.01 001
2200 A2 01001....
Following a LOCA, Unit Two has been Emergency Depressurized during a high power
ATWS and-all -control rods are now fully inserted. Injection with the only available
injection systems (2A Core Spray, and B Loop RHR) has been maximized to raise RPV
level and adequate core cooling is assured. Plant conditions are:
Torus Pressure 19 psig, slowly lowering
Torus Level -5.5 feet, slowly lowering
Torus Water Temp., 220 0 F, steady
Drywell Avg. Temp. 287 0 F, lowering
Reactor Level -35 ", rapidly rising
Reactor Pressure 50 psig
The operating crew should do which ONE of the following per Emergency Operating
Procedures?
A" Continue with maximum injection until above the top of active fuel.
B. Secure the B Loop of RHR and continue to raise level with the 2A Core
Spray Pump.
C. Reduce injection flow from Core Spray to maintain the minimum containment
cooling requirements.
D. Secure the 2A Core Spray Pump and continue to raise level with the B Loop of
RHR.
Feedback
258. LOI-CLS-LP-300-B*018001
Notes
Added reactor pressure 50 psig to the stem and changed correct answer to A to
continue to maintain iniection until above TAF.
Response form
Categories
Keyword: CONTAINMENT Cog Level: C/A 4[.3.4.4
Source: B Exam: BSEP'2003
Test: S Misc: LSM 'R/C
Thursday, February 06, 2003 03:05:46 PM 37
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
31. 223001G2.1.7 001
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?
Af 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 />.
Feedback
REFERENCES: TECH SPEC 3.6.4.1 /AM 159*
WRoNG CONTA INET-k I
Notes
Added Alternate vacuum breaker position indication is not available to stem changed 8
to 4 in A added test to A to make A correct per BNP TS. Added immediately begin to C
to make it incorrect.
Response form
Categories
Keyword: DIFFERENTIAL PRES Cog Level: C/A 3.7/4.4
Source: B Exam: BSEP 2003
Test: S Misc: LSM/R
Thursday, February 06, 2003 03:05:46 PM 38
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
32. 223001K4.03 001
Unit I has experienced a small LOCA with the following conditions present:
. Drywell-pressure - .4.5 psig .. . . .. ...
Drywell temperature 201OF
Reactor water level 145 inches
Reactor Bldg Exhaust Rad 8 mR/hr
Per the EOP's the CAC Div I and CAC Div IIAC 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.
Feedback
References: SD-12, Primary Containment Isolation System, Rev.1 pg 24 & 52
A. Incorrect since both valves would close when subsequent Group II isolation signal is
generated.
B. Incorrect since both valves would close.
C. Correct answer.
D. Incorrect since both valves would close.
Notes
Changed stem to add the word "Isolation (Soft)" to match OP-15 and consistent with
question 288000A2.02 and replaced floor drain valves with... The RHR Process
Sampling valves (El 1-F079A,B and F080A,B) which are the actual names of the PASS
sample valves
Response form
-rk..*.*..
ur all*~
y,
=K..,
e
n6 2003 0q.nlRA4
ru arIy ",* -V, J.**r
unn
39
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
Categories
Keyword: PRIMARY CONTAINMENT Cog Level: C/A 3.7/3.8
Source: N Exam: -BSEP 2003
Test: - -R Misc: TCK/R/C
Thursday, February 06, 2003 03:05:46 PM 40
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
33. 223002A3.02 001
33 223002A3 02 001
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.
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
Notes
Response form
Categories
Keyword: MS1V Cog Level: C/A 3.5/3.5
Source: M Exam: BSEP 2003
Test: C Misc: LSM/R/C
Thursday, February 06, 2003 03:05:46 PM 41
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
34. 223002K1.07 001
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 100OF and rising slowly
An operator has been sent to the RCIC room and reports that there is a small steam
leak on the line upstream of the Trip and Throttle valve. The Shift Supervisor orders
the Reactor Operator to manually isolate RCIC.
Which ONE of the following describes the effect on RCIC when the manual isolation
pushbutton is depressed?
A. Inboard and Outboard Steam Supply Isolation valves F007 and F008 close and the
B. Inboard Steam Supply Isolation valve F007 closes and the RCIC turbine trips.
Cf Outboard Steam Supply Isolation valve F008 closes and the RCIC turbine trips.
D. No effect on RCIC since the system should already be isolated.
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 > 165°F and this is 10 minutes
into the event.
Notes
added noun names for F007 and F008
Response form
.A=
-...... n*' fnO O C,R.o.A* 42
I Tursday, Ft-eruary UU, ZUVJo VO.Vu.t rVvs
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
Categories
Keyword: RCIC Cog Level: C/A 3.4/3.6
Source: B Exam: BSEP 2003
Test: C Misc: LSM/R/C
Thursday, February 06, 200303:05:46 PM 43
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
35. 230000A2.15 001
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 0 F 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,Diywell 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 E1i-CS-$18 to the "Manual
Overrd" position. Open Drywell Spray Inbd Isol Valve, E1I-F021, then throttle
Drywell Spray Outbd Isol Valve, E1I-F016.
B.3 Place Containment Spray Valve Control switch El 1-CS-S17-7o the "Manual"
position. Open Drywell Spray Inbd isol Valve, Eli-F021 4("e throttle Drywell Spray
Outbd Isol Valve, Ell -F016.
C. Place Containment Spray Valve Control switch E11-CS-Si 7 to the "Manual"
position. Open Drywell Spray Outbd Isol Valve, E1i-FO16, then throttle open
Drywell Spray Inbd Isol Valve, E11-F021.
D. Place Containment Spray Valve Control switch E11-CS-Si 7 to the "Manual"
position and the 2/3 Core Height LPCI Initiation Override switch Eli-CS-S8 to the
"Manual Overrd" position. Open Drywell Spray Inbd Isol Valve, Ell-F021, then
throttle Drywell Spray Outbd Isol Valve, Ell-FO16.
Thursday, February 06, 2003 03:05:47 PM 44
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
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.
Notes
added F021 and F016 and added reactor pressure 10 psig. deleted lowering slowly
from RPV level trend
Response form
Categories
Keyword: RHR SYSTEM Cog Level: C/A 4.0/4.1
Source: N Exam: BSEP 2003
Test: R Misc: TCK/R/C
Thursday, February 06, 2003 03:05:47 PM 45
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
36. 233000K2.02 001
Unit 1 is on Shutdown Cooling using RHR Loop lB. I&C Techs are working on the
RPS logic power supply. During the repair work the Techs cause an inadvertent loss of
Division II 125/250-VDC electrical distribution.
Which ONE of the following describes the effect of this loss of Shutdown Cooling?
A.j4roup 8 outboard SDC suction valve remains OPEN. LPCI injection valves will fail
"Vclosed.
B. Group 8 outboard SOC suction valve and LPCI injection valves will fail closed.
C" Group 8 outboard SDC suction valve remains OPEN. LPCI injection valves remain
OPEN. 4
D. Group 8 outboard SDC suction valve fails cLoed. LPCI injection valves remain
OPEN.
Feedback
NEW
SD-12 Page 72 of 217
"W--T,QLJ$43ESTIO,'tOES ;'OT HXEJAKTOD WITH FPC.-
Notes
removed reference to Fuel Pool Temperature in distractors. Modified distractors to read
outboard isolation valve instead of valves, replaced wording fail as is are not affected
with "remain open". specified RHR Loop 1B in stem
Response form
Categories
Keyword: SDC Cog Level: MEM 2.8/2.9
Source: N Exam: BSEP 2003
Test: R Misc: LSMIR/C
. . . -....... . aaaan,^ .ac.A, nd 46
Thursday, -eDruary uo, 2uu0 u03:u0A, HV
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
37. 239001K3.16 001
Unit 1 was operating at 100%, when a loss of EHC caused a turbine trip without
-bypass valves. SRVs operated a-s requiredand-pressuwe 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
Feedback
BSEP BANK 135. LOI-CLS-LP-020-A*003001
Notes
Response form
Categories
Keyword: MAIN STEAM Cog Level: MEM 3.6/3.6
Source: B Exam: BSEP 2003
Test: C Misc: LSM/R/C
-. 3Jq
. .. Tusa,1erayULU ~~~~~~~~47
Thursday, February 06, 2003 U03:05:47 HvI
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
38. 239002A1.01 001
During an overpressure transient, an operator has opened an SRV to control pressure.
RPV pressure is 1005 psig.
Which ONE of the following is the expected tail pipe temperature for the SRV that is
open, as indicated on ERFIS?
-REFERENCES. STEAM TABL~r
A. 212°F
Bf 300OF
C. 350°F
D. 545 0 F
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*03A002
Notes
Response form
Categories
Keyword: SRV Cog Level: C/A 3.3/3.4
Source: B Exam: BSEP 2003
Test: C Misc: LSM/R/C
Thursday, February 06, 2003 03:05:47 PM 46
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
39. 239002K6.05 001
During normal power operation of Unit 1, SRV F013H lifted.
Which ONE of the following describes the consequences of SRV F013H tailpipe
vacuum breaker (F037H) failing open prior to the SRV actuation?
A. Steam will discharge directly to the suppression pool airspace.
B.f 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.
Feedback
REFERENCES: SD-20
163.
LOl-CLS-LP-02O-A*O7DO01
Notes
Response form
Categories
Keyword: VACUUM BRKR Cog Level: C/A 3.0/3.2
Source: M Exam: BSEP 2003
Test: R Misc: LSM/TCK/R/C
Thursday, February 06, 2003 03:05:47 PM 49
QUESTIONS REPORT
for BSEP 2003 Final Draft CR
40. 241000K6.05 001
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?
., 1st - Main Turbine trips.
S2nd - Main Turbine Bypass Valves close.
3rd - MSIV's close.
st - Main Turbine tripsý
2nd - Main Turbine Byphss Valves close.
3rd - MSIV's close1
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.
Feedback
Feedback
Reference: SI-LP-02501-00 Rev. SI-00 Pg 7 of 13.
EO 200.087.a.01
A. Incorrect since,,Ps and Main Turbine trip at the same time at 22.3" Hg Vac.
B. Incorrect since MSIV's close at 10" Hg Vac and Bypass valves close at 7" Hg Vac.
C. Correct answserG4ROe-R7ýPand Main Turbine trip at the same time 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.
Notes
removed reference to,,
100 degre es per hour, but required pressure band is 150-300 psig and the cooldown should be stopped. Notes Response form Categories RO Tier: SRO Tier: TIGI Keyword: LOSS OF ALL AC Cog Level: MEM 2.7/3.9 Source: B Exam: BSEP 2003 Test: S Misc: LSM/R/C Thursday, February 06, 2003 03:05:49 PM 69 QUESTIONS REPORT for BSEP 2003 Final Draft CR 60. 295004AA2.02 001 60 295004AA2 02 001 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. IXDB. Feedback BSEP REVIEWER - PLEASE ADD ACTUAL CONTROL ROOM INDICATIONS TO STEM 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. Notes Response form Categories RO Tier: T1G2 SRO Tier: TIG2 Keyword: DC SYSTEMS Cog Level: MEM 3.5/3.9 Source: N Exam: BSEP 2003 Test: C Misc: TCK/C Thursday, February 06, 2003 03:05:49 PM 70 QUESTIONS REPORT for BSEP 2003 Final Draft CR 61. 295005AA1.05 001 Unit 2 was operating at 100% RTP when the reactor scrammed due to a turbine trip. In addition to-the Turbine-Stop Valves closingi 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 DW Turbine Control Valves - Closed Intercept Valves - Closed Intermediate Stop Valves - Closed Bypass Valves - All open initially; throttle closed to control Rx pressure. Feedback Re ferences: 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 from Hi vibes. B. Incorrect since all valves close except bypass valves on a turbine trip from Hi vibes. C. Incorrect since all valves close except bypass valves on a turbine trip from Hi vibes. D. Correct answer. Notes removed auto vibration trip reference from stem since vibration trip disabled Response form Thursday, February 06, 2003 03:05:49 PM 71 QUESTIONS REPORT for BSEP 2003 Final Draft CR Categories RO Tier: TIGI SRO Tier: TIG2 Keyword: TURBINE TRIP Cog Level: MEM 3.6/3.6 Source: B Exam: BSEP 2003 Test: C Misc: LSM/R/C Thursday, February 06, 2003 03:05:49 PM 72 QUESTIONS REPORT for BSEP 2003 Final Draft CR 62. 295006AA2.05 001 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 0 F Reactor Bldg Vent Exhaust Rad Monitor 2.5 mR/hr Main Steam Line Rad Monitor 1.3 times normal full power reading Which ONE of the following indicates which EOP's should be entered at this time? A. EOP-01-LPC, Level/Power Control; EOP-03-SCCP, Secondary Containment Control Procedure. Bf 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. Feedback References: APP-UA-23 Annunciator EOP's A. Incorrect since entry into EOP-03 is 3 mR/hr for Rx bldg vents and&ESF04 is 1.4 times normal rad levels for MSIV's. B. Correct answer since scram should have occurred due to low water level and reactor power is still above 3%. C. Incorrect since EOP-02 entry conditions not met for Drywell pressure (1.7 psig) and Drywell temperature (1500F) and entry into EOP-03 is 3 mR/hr for Rx bldg vents. D. Incorrect since entry into EOP-04 is 1.4 times normal rad levels for MSIV's. Notes modified distractor since no correct answer existed L/PC only required to be enterred under stated conditions Response form Thursday, February 06, 2003 03:05:50 PM 73 QUESTIONS REPORT for BSEP 2003 Final Draft CR Categories RO Tier: SRO Tier: TIGI Keyword: EOP ENTRY Cog Level: C/A 4.6/4.6 Source: N Exam: BSEP 2003 Test: S Misc: TCK/R/C Thursday, February 06, 2003 03:05:50 PM 74 QUESTIONS REPORT for BSEP 2003 Final Draft CR 63. 295006AA2.06 001 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. Bf 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. Feedback Feedback 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". Notes Response form Categories RO Tier: TIGI SRO Tier: Keyword: REACTOR SCRAM Cog Level: C/A 3.5/3.8 Source: N Exam: BSEP 2003 Test: R Misc: TCK!R/C Thursday, February 06, 2003 03:05:50 PM 75 QUESTIONS REPORT for BSEP 2003 Final Draft CR 64. 295006G2.2.20 001 Unit Two has inserted a manual Reactor scram due to lowering condenser vacuum. Control rods failed to insert on the scram. Plant conditions: Reactor power 31% Steam flow 3.2 Mlbm/hr. Reactor pressure 960 psig, controlled by EHC Drywell pressure 0.6 psig Mode Switch RUN Main Turbine Tripped on low vacuum The operator is performing LEP-02, Section 3 to reset and scram the Reactor. Jumpers to bypass RPS trip signals have been requested but NOT yet installed. Which ONE of the following would prevent the operator from resetting RPS prior to jumper installation? Af 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. Notes Response form Categories RO Tier: SRO Tier: TIGI Keyword: SCRAM Cog Level: C/A 2.2/3.3 Source: B Exam: BSEP 2003 Test: S Misc: LSM/R/C Thursday, February 06, 2003 03:05:50 PM 76 QUESTIONS REPORT for BSEP 2003 Final Draft CR 65. 295007AK3.06 001 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 increasded. fe B. Reactor pressure would have remained the same, and PAM Pressure would hav increased. Cr Reactor pressure would have increased, and PAM Pressure would have remain( .d the same. D. Reactor pressure would have remained the same, and PAM Pressure would hav e remained the same. Feedback A. Incorrect B. Incorrect C. Correct D. Incorrect Notes changed Turbine Throttle Pressure to PAM pressure Resnonse form Response form Categories TIGI SRO Tier: TIGI RO Tier: Keyword: REACTOR PRESSURE Cog Level: C/A 3.7/3.8 Source: B Exam: BSEP 2003 Test: C Misc: TCK/R Thursday, February 06, 2003 03:05:50 PM 77 QUESTIONS REPORT for BSEP 2003 Final Draft CR 66. 295008AK3.04 001 66 295008A 04001 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 pumrp turbines by limiting water addition to the vessel. Cf 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. 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. Notes Added clarification to the stem regarding the event reference in the applicable safety analysis in Tech Specs. "A Digital Feedwater Control System failure has caused excessive feed flow." Response form Categories RO Tier: T1G2 SRO Tier: TIG2 Keyword: MAIN TURBINE Cog Level: MEM 3.3/3.5 Source: N Exam: BSEP 2003 Test: C Misc: TCK/R Thursday, February 06, 2003 03:05:50 PM 78 QUESTIONS REPORT for BSEP 2003 Final Draft CR 67. 295009AK1.05 002 Which ONE of the following is the basis for lowering RPV water level during an ATWS condition? Af 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. Feedback 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. Notes Response form Categories RO Tier: TIGI SRO Tier: TIGI Keyword: RPV Cog Level: MEM 3.3/3.4 Source: B Exam: BSEP 2003 Test: C Misc: LSM/R/C Thursday, February 06, 2003 03:05:50 PM 79 QUESTIONS REPORT for BSEP 2003 Final Draft CR 68. 29500902.4.1 001 CO,4 sý">er -MG Reactor water level has just dropped main co)ntro-~boaf-d-min-dc-atimn suddenly tod- 158 inches. hecr-ew--ca-nnforer " " Due- t' ^afalur r ca~n o Az 3 _mnintain*c;l *h.ritical withnot thp itraduction of BoPr.- Which one of the following " describes correct EOP pathway(s) that must be executed? ro 5ee -. Etr /-RVCthn A. Enter..~ihenZ~iL aji OP ocrrnl. B.f 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. Feedback Per 1-EOP-UG B is the correct answer If any of the RVCP entry conditions are met and the it cannot be determine if the reactor can be maintained subcritical without the introduction of Boron. The the crew must exit RVCP and enter L/PC Notes modified distractor B, Correct answer is to enter L/PC from RSP. Response form Categories RO Tier: SRO Tier: TIGI Keyword: EOP ENTRY Cog Level: C/A 4.3/4.6 Source: N Exam: BSEP 2003 Test: S Misc: LSM/R/C Thursday, February 06, 2003 03:05:50 PM 80 QUESTIONS REPORT for BSEP 2003 Final Draft CR 69. 295010AAI.01 002 The following conditions exist on Unit 1: Drywell pressure 2.0 psig Drywell temperature 180OF Reactor water level +55 inches Reactor pressure 400 psig Drywell Cooler Overide Switch position NORMAL Which ONE of the following describes the condition of thte Drywell Cooler fans? A' All cooling fans are tripped. B. Div I cooling fans tripped, Div IIcooling fans running. C. Div I cooling fans running, Div IIcooling 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. Notes Response form Categories RO Tier: TIGI SRO Tier: TIGI Keyword: DRYWELL VENTILATION Cog Level: C/A 3.4/3.5 Source: N Exam: BSEP 2003 Test: C Misc: TCK/R/C Thursday, February 06, 2003 03:05:50 PM 81 QUESTIONS REPORT for BSEP 2003 Final Draft CR 70. 295010AA2.06 001 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 280OF PC Water Level 20 ft and increasing slowly Which ONE of the following should be ordered by the Shift Supervisor? A. Vent th Do not exceed ODCM limits for radiological release rates. b Bf Vent the Drywell IRRESPECTIVE of offsite radioligical release rates. C. Spray the Drywell after verifying within Drywell Spray Initiation Limit. D. Enter the Severe Accident Guidelines (SAG's). Feedback Reference: PC-1 Primary Containment Control Drywell Spray Initiation Limit (Graph 8) (Consider providing PC-1 and Grapl}8) A. Incorrect since T-em water level is t B. Correct answer. C. Incorrect since spraying the Drywell is not allowed sinco RL :. ... FMi and RHR pumps arc roguirod to maintain adequate uviE cooling. D. Incorrect since EOP's have direction to cover this situation. Notes changed Bulk to Average and Torus to Drywell in distractor B changed 10 CFR to ODCM to match PCCP Response form Categories RO Tier: SRO Tier: TIGI Keyword: DRYWELL PRESSURE Cog Level: C/A 3.6/3.6 Source: M Exam: BSEP 2003 Test: S Misc: LSM/TCK/C Thursday, February 06, 2003 03:05:50 PM 82 QUESTIONS REPORT for BSEP 2003 Final Draft CR 71. 295012AA1.02 001 Following a reactor scram, drywell temperature is 225 degrees. Which ONE of the following describes the position of the MIN/MAX control switch on Panel XU-3 for the Drywell Lower Vent dampers, the reason it is in that position, and the actual damper position? Assume NO operator actions: A. MIN position so that the Reactor Building Closed Cooling Water system is not overloaded. Dampers will actually be in the MIN position. B. MAX position to minimize DP between the torus and the drywell. Dampers will actually be in the MIN position. C' MIN position to prevent extreme temperature excursions in the upper drywell regions during normal operation. Dampers will actually be in the MAX position. D. MAX position to maximize drywell cooling AND to distribute the air flow in all portions of the drywell evenly. Dampers will actually be in the MAX position. 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. Notes Response form Categories RO Tier: TIG2 SRO Tier: TIG2 Keyword: DRYWELL TEMPERATURE Cog Level: MEM 3.8/3.8 Source: N Exam: BSEP 2003 Test: C Misc: TCK/R/C Thursday, February 06, 2003 03:05:50 PM 83 QUESTIONS REPORT for BSEP 2003 Final Draft CR 72. 295013AA2.02 001 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 930 F 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 11 0°F. 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. Feedback LESSON 2: LOI-CLS-LP-302-M LESSON 2 OBJECTIVES: 03c LESSON 3: LOI-CLS-LP-302-D LESSON 3 OBJECTIVES: 02 LOI-CLS-LP-004-A*1 5M001 Notes changed CLOSED to OPEN in stem added immediately to question. Response form Categories RO Tier: SRO Tier: TIGI Keyword: TORUS TEMP Cog Level: MEM 3.2/3.5 Source: M Exam: BSEP 2003 Test: S Misc: LSM/R/C Thursday, February 06, 2003 03:05:50 PM 84 QUESTIONS REPORT for BSEP 2003 Final Draft CR 73. 295013AK1.03 001 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-I 110 F.:-The-average Suppression-Pool temperature is steady at 93 0 F. Which ONE of the following describes the effect, if any, on continued plant operation? A. The Tech Spec limit for Suppression Pool average temperature has been exceeded. Average temperature must be lowered to < 90OF 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 1 10OF has been exceeded. The reactor must be scrammed immediately. DW No TS limit has been exceeded. Feedback References: Tech Spec section 3.6.2.1 A. Incorrect since the Tech Spec limit for Suppression Pool temperature is 95 0 F 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. Notes rearranged distractor C to make grammatically correct Response form Categories RO Tier: TIG2 SRO Tier: TIGI Keyword: SUPPRESSION POOL TEM Cog Level: C/A 3.0/3.3 Source: N Exam: BSEP 2003 Test: C Misc: TCK/R/C Thursday, February 06, 2003 03:05:51 PM 85 QUESTIONS REPORT for BSEP 2003 Final Draft CR 74. 295014AA2.03 001 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? Af 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. Feedback Answer: A 63. LOl-CLS-LP-O02-A*1 61001 Notes rilr~ocr~liefn 1.A snil to exnced 1137 8 ns*in ATWS trio setpoint. Response form Categories RO Tier: SRO Tier: TIGI Keyword: REACTIVITY Cog Level: C/A4.0/4.3 Source: M Exam: BSEP 2003 Test: S Misc: LSM/R/C Thursday, February 06, 2003 03:05:51 PM 86 QUESTIONS REPORT for BSEP 2003 Final Draft CR 75. 295014AK2.03 001 03001 75 295014A Which ONE of the following describes the Abnormal Operating Occurances (Plant Tran-sients)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. 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. Notes Response form Categories RO Tier: TIGI SRO Tier: TIGI Keyword: FUEL TEMPERATURE Cog Level: C/A 3.3/3.4 Source: B Exam: BSEP 2003 Test: C Misc: LSM/R/C Thursday, February 06, 2003 03:05:51 PM 87 QUESTIONS REPORT for BSEP 2003 Final Draft CR 76. 295015AK1.02 001 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. Co 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 ofinjection from Condensate and ECCS during an ATWS condition. Notes added "in a partially borated core" to distractor C to match 01-37.5 wording Response form Categories RO Tier: TIG1 SRO Tier: TIGI Keyword: ATWS Cog Level: MEM 3.9/4.1 Source: N Exam: BSEP 2003 Test: C Misc: TCK/R/C Thursday, February 06, 2003 03:05:51 PM 88 QUESTIONS REPORT for BSEP 2003 Final Draft CR 77. 295016AK3.01 001 77 295016AK3 01001 A chlorine tank car rupture has made the Control Room inaccessable. If possible, prior to leaving the-Control Room the-ControlOperator-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. 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. Notes Fire would require ASSD procedure not AOP-32, replaced with chlorine. Response form Categories RO Tier: TiG2 SROTier: TIGI Keyword: REMOTE SHUTDOWN Cog Level: MEM 4.1/4.2 Source: B Exam: BSEP 2003 Test: C Misc: TCK/R/C Thursday, February 06, 2003 03:05:51 PM 89 QUESTIONS REPORT for BSEP 2003 Final Draft CR 78. 295017G2.1.2 001 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. Feedback Reference: OOAP-05.0 Rev. 14 A. Correct answer. B, C and D. Incorrect since these actions are all subsequent actions. Notes changed vents to ventilation Response form Categories RO Tier: TIG2 SRO Tier: TIGI Keyword: OFFSITE RELEASE Cog Level: MEM 3.0/4.0 Source: N Exam: BSEP 2003 Test: C Misc: TCK/R/C Thursday, February 06, 2003 03:05:51 PM 90 QUESTIONS REPORT for BSEP 2003 Final Draft CR 79. 295019AA1.01 001 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 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. Notes Response form Categories RO Tier: T1G2 SRO Tier: TIG2 Keyword: INSTRUMENT AIR Cog Level: MEM 3.5/3.3 Source: N Exam: BSEP 2003 Test: C Misc: TCK/R/C Thursday, February 06, 2003 03:05:51 PM 91 QUESTIONS REPORT for BSEP 2003 Final Draft CR 80. 295020AA2.06 001 A partial Group 2 isolation has just occurred on Unit 2. Which ONE-ofthefollowing 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. Cf A variable leg leak that lowers variable leg pressure for Reactor Vessel Water Level LL#1 transmitters, LT-NO17A-1 and LT-NO1 7B-1. D. Drywell temperature at 155 0 F. Feedback References: SD-01.2 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. Notes Partial GP 2 can only occur with 2 instrument failures. Reworded stem for partial. N017C-1 and D-1 have different reference legs so reworded for plural. N017A-1 and B-1 do have a common variable leg tap from nozzle N1IA and would result in an inboard GP 2. Response form Categories RO Tier: T1G2 SRO Tier: TIG2 Keyword: CONTAINMENT ISOL Cog Level: C/A 3.4/3.8 Source: N Exam: BSEP 2003 Test: C Misc: TCK/R/C Thursday, February 06, 2003 03:05:51 PM 92 QUESTIONS REPORT for BSEP 2003 Final Draft CR 81. 295021AA2.01 001 Which ONE of the following indications is used to monitor plant heatup/cooldown rate -while hnAlternate Shutdown Cooling with the SRVs? A. Recirculation loop suction line temperature. Bf Safety relief valve tailpipe temperature. C. Steam dome pressure using steam table conversion. D. The running ECCS pump local suction temperature. Feedback 53. Correct SRO ONLY Notes Response form Categories RO Tier: SRO Tier: TIG2 Keyword: SHUTDOWN COOL Cog Level: MEM 3.5/3.6 Source: B Exam: BSEP 2003 Test: S Misc: LSM/R/C Thursday, February 06, 2003 03:05:51 PM 93 QUESTIONS REPORT for BSEP 2003 Final Draft CR 82. 295021AK2.01 001 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 bottom3. head temperature is less than 212OF ensures the Unit has not entered Mode B. Verifying that the recirc loop suction temperatures are less than 212OF 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. 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. Ifan 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. Notes Response form Categories RO Tier: TIG3 SRO Tier: TIG2 Keyword: SHUTDOWN COOL Cog Level: C/A 3.6/3.7 Source: N Exam: BSEP 2003 Test: C Misc: TCK/R/C Thursday, February 06, 2003 03:05:51 PM 94 QUESTIONS REPORT for BSEP 2003 Final Draft CR 83. 295022G2.1.30 001 The Unit 1 Control Operator is walking down his panels when he notices that the CRD Flow Control Valve controller,C1 1-FC-R600 haslfailed such that the demand is 0 gpm. -Flow Control Valve Cl 1-F002A was in automatic at 60-gpm prior to the failure. Which ONE of the following describes how Flow Control Valve C1 1-F002A 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. Bf The Flow Control Valve will close until local controller C1 1-FK-DO09A is taken to manual and adjusted as necessary. C. The Flow Control Valve will fully open until local controller C1 1-FK-DO09A is taken to manual and adjusted as necessary. D. The Flow Control Valve will close and cannot be operated until controller C1 1-FC-R600 is repaired. 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 C1 1/C1 2-FC-R600. D. Incorrect since the valve can be operated in the manual mode locally. Notes C12 removed for Unit I question Response form Categories RO Tier: TIG2 SRO Tier: TiG2 Keyword: CRD SYSTEM Cog Level: MEM 3.9/3.4 Source: N Exam: BSEP 2003 Test: C Misc: TCK/R/C Thursday, February 06, 2003 03:05:51 PM 95 QUESTIONS REPORT for BSEP 2003 Final Draft CR 84. 295023AA2.02 001 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. Cý 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. 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. Notes Response form Categories RO Tier: TIG3 SRO Tier: T1GI Keyword: FUEL POOL Cog Level: C/A 3.4/3.7 Source: N Exam: BSEP 2003 Test: C Misc: TCK/R/C Thursday, February 06, 2003 03:05:52 PM 96 QUESTIONS REPORT for BSEP 2003 Final Draft CR 85. 295024EK3.01 001 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. Feedback References: CLS-LP-300-L Rev.1 pg 21,22,27-30 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. Notes Response form Categories RO Tier: TIGI SRO Tier: TIGI Keyword: DRYWELL SPRAYS Cog Level: MEM 3.6/4.0 Source: N Exam: BSEP 2003 Test: C Misc: TCK/R/C Thursday, February 06, 2003 03:05:52 PM 97 QUESTIONS REPORT for BSEP 2003 Final Draft CR 86. 295025EA1.02 001 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 Bf 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. Notes removed down from stem Response form Categories ROTier: TIGl SROTier: TIGI Keyword: MAIN TURBINE Cog Level: C/A 3.8/3.8 Source: N Exam: BSEP 2003 Test: C Misc: TCK/R/C Ih..U ,=* rh.,I k, 2W3 0:t5:5 P 98 , i ursuay, r~ul aly u.,, u'. .,v.,.. v QUESTIONS REPORT for BSEP 2003 Final Draft CR 87. 295025G2.1.20 001 Unit 2 is operating at 75% RTP when alarm APP A-05 3-5, RA.C.JQOR VESS HI PRESS-ts receivedAft-r verifying that pressure peaked at psig you note that "C" Main Steam Line Flow indicates downscale. No other abnormal indications exist. Which ONE of the following describes th q0act ion that should be taken for this condition? Cl4 LlieTvltlV'8tb duLidated with i'iLe bluukId ,ii". "I-,L A. CGse 0.21- F022C and B...F.... B. Immediately SCRAM the reactor. j030 ________ C. Reduce reactor pressure toJD4 psigwt'H- 30 rinutes. D. Initiate a WR/JO for the Main Steam Line Flow indicator. Feedback References: APP A-05 3-5 Rev.43 A. Correct answer. B. Incorrect since a scram condition does not exist. C. Incorrect since you only have 15 minutes to reduce reactor pressure to < 1045 psig per T.S. 3.4.10. D. Incorrect since you only initiate a WR/JO for the indicator if it is suspected that it malfunctioned. Notes Reworded distractor A so it would not be a direct lookup and recommend supplying APP as reference. Response form Categories Categories Response SRO Tier: RO Tier: TIGI Keyword: REACTOR PRESSURE Cog Level: 4.3/4.2 Source: N Exam: BSEP 2003 Test: R Misc: TCK/R Thursday, February 06, 2003 03:05:52 PM 99 QUESTIONS REPORT for BSEP 2003 Final Draft CR 88. 295025G2.4.4 001 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. 0 B. Unit 2 HPCI flow rate test in progress and Suppression Pool temperature at 102 F. Cf Unit 1 Reactor Pressure at 1065 psig following a spurious Group 1 isolation. D. Units I and 2 in Mode 4 with new fuel being moved into Unit 2 fuel pool and Reactor Building pressure cannot be maintained negative. 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 105 0 F. 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. Notes removed following a scram from A since RSP is part of EOP-01. Response form Categories RO Tier: SRO Tier: TIGi Keyword: EOP ENTRY Cog Level: C/A 4.0/4.3 Source: N Exam: BSEP 2003 Test: S Misc: TCK/R/C Tk,,,eoa., A nhr,,oa, 06 2003 03:05:59 PM 100 ur IU*uay, I UUGly " Itf.V *S*'.vv w QUESTIONS REPORT for BSEP 2003 Final Draft CR 89. 295026EK2.04 001 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 0 Operator notes that Suppression Pool temperature is 96 F. 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. Cf Alarm; Red. D. Inactive; Cyan. Feedback Reference: SD-60 Rev.2, ERFIS DATA ACQUISITION, PROCESSING, AND DISPLAY 0 A. Incorrect since the temperature of the suppression pool is > 92 F. 0 0 B. Correct answer. Temperature of the suppression pool is > 92 F and < 95 F. C. Incorrect since the temperature of the suppression pool is <95 F. 0 D. Incorrect since all of the inputs to SPDS are operable. Notes raised SPT to 96 and changed correct answer to C, better match k/a more operational validity Response form Categories RO Tier: T132 SRO Tier: TI Keyword: SUPPRESSION POOL Cog Level: W 2 -.5/2.8 Source: N Exam: BSEP 2003 Test: C Misc: TCK/R -. . .......... - ... ..... fltA 101 Thursday, F-eDruary u0, zuu0 v3:uo05:54 v QUESTIONS REPORT for BSEP 2003 Final Draft CR 90. 295028EK1.01 001 Unit 2 was operating at 100% RTP when a LOCA occurred. Water level is being maintained above TAF with the HPCI system. The following conditions exist in the Drywell: Drywell pressure 8.0 psig Suppression Chamber pressure 7.5 psig Drywell temperature 275 0 F Reactor pressure 700 psig Suppression Chamber sprays in progress Which ONE of the following describes the effect on the indicated water level? Assume the fuel zone level instrument reference leg piping height is longer than the variable leg piping height in the Drywell. A. Level indication will be reading lower than actual water level due to the reference leg having more water in it. B. Level indication will be reading lower than actual water level due to Drywell temperature being above 212 0 F. C' Level indication will be reading higher than actual water level due to Drywell temperature being above 212 0 F. D. Level indication will still read accurate level since the high Drywell temperature affects both the reference and variable legs equally. Feedback References: SD-011.2 Rev.2 pg 38 and 39, Reactor Vessel Instrumentation CLS-LP-011.2 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. Notes Response form
- ". , ,ay, ..... nu 2M3 030n5 J PMn.J
,, 102 , IlUrsUay, e*l** ruar ,V.OV.,J-L QUESTIONS REPORT for BSEP 2003 Final Draft CR Categories RO Tier: T1G2 SRO Tier: TIG2 Keyword: DRYWELL TEMPERATURE Cog Level: MEM 3.5/3.7 Source: N Exam: BSEP 2003 Test: C Mise: TCK/R Thursday, February 06, 2003 03:05:52 PM 103 QUESTIONS REPORT for BSEP 2003 Final Draft CR 91. 295030EA1.05 001 Unit 2 has developed an unisolable leak on the ECCS Suction header. Suppression Pooltevel c-ontinues 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 Cf -6 feet and 5 inches D. -9.0 feet 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 0-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. Notes Response form Categories RO Tier: TIG2 SRO Tier: TIG1 Keyword: SUPPRESSION POOL Cog Level: MEM 3.5/3.5 Source: N Exam: BSEP 2003 Test: C Misc: TCK/R/C Thursday, February 06, 2003 03:05:52 PM 104 QUESTIONS REPORT for BSEP 2003 Final Draft CR 92. 295031G2.1.1 001 Unit 2 experienced a scram due to the loss of the Reactor Feedwater Pumps. Reactor water level initially dropped to +90 inches and has been restored to +150 inches and increasing slowly. The following conditions are present at this time: HPCI system currently injecting RCIC system in Standy alignment Secondary Containment isolated SBGT system operating normally Group 2 isolated Group 3 RWCU system in operation Group 6 isolated Group 8 isolated Which ONE of the following describes the actions that should be taken at this time? A. Continue to monitor HPCI operation and restore reactor water level to the normal band. RCIC operation is not required. B. Start RCIC manually and then secure HPCI. Increase reactor water level to the normal operating band. All required PCIS Group isolations have occurred. C. Reset the Group 2 isolation immediately to prevent high drywell pressure and continue to monitor HPCI while restoring reactor water level to the normal band. D' Isolate the RWCU System, start RCIC manually, if possible, and continue to monitor reactor water level to ensure the normal operating band is obtained. 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. B. Incorrect since RWCU system should be 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, February 06, 2003 03:05:52 PM 105 QUESTIONS REPORT for BSEP 2003 Final Draft CR Notes Changed complete to isolated. Added "All required PCIS Groups isolations have occurred." to distractor B to make it incorrect, added RCIC operation is not required to distractor A. Response form Categories RO Tier: TIGI SRO Tier: TIGI Keyword: REACTOR WATER LEVEL Cog Level: C/A 3.7/3.8 Source: N Exam: BSEP 2003 Test: C Misc: TCK/RJC Thursday, February 06, 2003 03:05:52 PM 106 QUESTIONS REPORT for BSEP 2003 Final Draft CR 93. 295032EK3.01 001 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. Co 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. Notes Added "personnel access for the safe shutdown of the plant will be precluded." to distractor A to make it incorrect. This applies to MSOR. Response form Categories RO Tier: TIG3 SRO Tier: TIG2 Keyword: SECONDARY CONTAIN Cog Level: MEM 3.5/3.8 Source: B Exam: BSEP 2003 Test: C Misc: LSM/R/C Thursday, February 06, 2003 03:05:52 PM 107 QUESTIONS REPORT for BSEP 2003 Final Draft CR 94. 295033G2.3.10 001 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? Af 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 an entry condition exists for EOP-03-SCCP (>90 mR/HR for ARM channel 30). Notes will provide attachment 10 of EOP-UG Response form Categories RO Tier: SRO Tier: TIG2 Keyword: SECONDARY CONTAIN Cog Level: C/A 2.9/3.3 Source: N Exam: BSEP 2003 Test: S Misc: TCK/R/C Thursday, February 06, 2003 03:05:52 PM 108 QUESTIONS REPORT for BSEP 2003 Final Draft CR 95. 295033G2.3.2 001 Unit I 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 RadiationAreas and Very High RadiationAreas. 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. C. 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. 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. Notes Response form Categories RO Tier: TiG2 SRO Tier: Keyword: RADIATION CONTROL Cog Level: MEM 2.5/2.9 Source: N Exam: BSEP 2003 Test: R Misc: TCK/R/C Thursday, February 06, 2003 03:05:53 PM 109 QUESTIONS REPORT for BSEP 2003 Final Draft CR 96. 295034EK1.02 001 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. o* A ground level release of radioactivity could occur. 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. Notes added (BFIVs) and changed chimney to stack Response form Categories RO Tier: TIG2 SRO Tier: TIG2 Keyword: SECONDARY CONTAIN Cog Level: C/A 4.1/4.4 Source: N Exam: BSEP 2003 Test: C Misc: TCK/R/C Thursday, February 06, 2003 03:05:53 PM 110 QUESTIONS REPORT for BSEP 2003 Final Draft CR 97. 295035EK1.01 001 Unit 1 is in Mode I at 50% RTP. Unit 2 is in Mode 5 with preparations in progress to commence core-offload. Secondarycontainment 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.f 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. Feedback References: Tech Spec Section 3.6.4.1 A. Incorrect since Unit 1 can stay in Mode 1 for 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />. B. Incorrect since Unit 1 is affected by the failure of the Unit 2 blowout panel since the Reactor Buildings are tied together. C. Correct answer. Ifthe blowout panel is repaired and tested within 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> then Unit I does not have to enter Mode 4. D. Incorrect since Unit 2 cannot commence fuel moves until the blowout panel is repaired and tested. Notes B correct - BSEP RX Bldgs. are separate. Response form Categories RO Tier: T1G3 SRO Tier: Keyword: SECONDARY CONTAIN Cog Level: MEM 3.9/4.2 Source: N Exam: BSEP 2003 Test: R Mise: TCK/R/C Thursday, February 06, 2003 03:05:53 PM ill QUESTIONS REPORT for BSEP 2003 Final Draft CR 98. 295037EK2.05 001 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: Af 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. 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. Notes Response form Categiories Cate*,ories Response RO Tier: TIGI SRO Tier: TIGI Keyword: CRD Cog Level: MEM 4.0/4.1 Source: B Exam: BSEP 2003 Test: C Misc: LSM/R/C Thursday, February 06, 2003 03:05:53 PM 112 QUESTIONS REPORT for BSEP 2003 Final Draft CR 99. 295038EA2.03 001 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 Notes Response form Categories RO Tier: SRO Tier: TIGI Keyword: HIGH RAD LEVEL Cog Level: MEM 3.5/4.3 Source: N Exam: BSEP 2003 Test: S Misc: LSM/R/C Thursday, February 06, 2003 03:05:53 PM 113 QUESTIONS REPORT for BSEP 2003 Final Draft CR 100. 300000K3.02 001 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. Feedback 416. LOI-CLS-LP-032-A*09AO03 Notes Response form Categories RO Tier: T2G2 SRO Tier: T2G2 Keyword: INSTRUMENT AIR Cog Level: C/A 3.3/3.4 Source: M Exam: BSEP 2003 Test: C Misc: LSM/R/C Thursday, February 06, 2003 03:05:53 PM 114 QUESTIONS REPORT for BSEP 2003 Final Draft CR 101. 400000G2.2.18 001 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 ControlPanel 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: Af 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. Feedback LOI-CLS-LP-029-A*02H001 Notes Response form Categories RO Tier: SRO Tier: T2G2 Keyword: MAINTENANCE Cog Level: C/A 2.3/3.6 Source: N Exam: BSEP 2003 Test: S Misc: LSM/R/C Thursday, February 06, 2003 03:05:53 PM 115 QUESTIONS REPORT for BSEP 2003 Final Draft CR 102. 500000EA2.01 001 Unit 1 experienced a LOCA with the following conditions present: Drywell pressure - .8.5-psig - - .. . . ... Drywell temperature 255 0 F 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. to the "ON" C. Place CAM Div 1/11 ISOL OVRD switches, CS-2986 and CS-3452, 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. Iicorric c P-02-PCClýs rq d to ter and thiýs cts the CAM syst m to e started. vel for Hydrogten concentration . Notes added noun names to switches, made H2 conc. unknown and changed D distractor to: "The containment is not required to be sampled for Hydrogen concentration unless reactor water level drops below Top of Active Fuel (TAF)." Thursday, February 06, 2003 03:05:53 PM 116 QUESTIONS REPORT for BSEP 2003 Final Draft CR Response form Categories ROTier:_TlG SRO Tier: TIGI Keyword: CONTAINMENT HYDROGEN Cog Level: C/A 3.1/3.5 Exam: BSEP 2003 Test: C Misc: TCK/R/C Thursday, February 06, 2003 03:05:53 PM 117 QUESTIONS REPORT for BSEP 2003 Final Draft CR 103. 600000AA2.02 001 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. D" 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. Notes Response form Categories RO Tier: T1G2 SRO Tier: Keyword: CONTROL ROOM VENTS Cog Level: MEM 2.8/2.9 Source: N Exam: BSEP 2003 Test: R Misc: TCK/R/C Thursday, February 06, 2003 03:05:53 PM 118 QUESTIONS REPORT for BSEP 2003 Final Draft CR 104. 600000AA2.06 001 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.f 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. 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. Notes Reworded stem to read Fire Protection mode and made distractor B tecnically correct. Cable Spread room is zone 9 which trips supply and exhaust fans for the cable spread room. APP UA-27 6-7. For CREV fire operation see AP UA-27 3-7 and 4-7. Response form Categories RO Tier: SRO Tier: TIG2 Keyword: FIRE PROTECTION Cog Level: MEM 2.5/2.8 Source: N Exam: BSEP 2003 Test: S Misc: TCK/R Thursday, February 06, 2003 03:05:53 PM 119 QUESTIONS REPORT for BSEP 2003 Final Draft CR 105. GEN 2.1.1 001 Ifoperating in the Scram Avoidance Region of the Flow Control Operational Map, which one of the following will reduce the likelihood of an instability eventQ A. Control rod withdrawal. B. Reducing recirculation flow. Cf 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 Notes changed stem to read Scram Avoidance Region consistent with PRNM Response form Categories RO Tier: T3 SRO Tier: T3 Keyword: FLOW MAP Cog Level: MEM 3.7/3.8 Source: M Exam: BSEP 2003 Test: C Misc: LSM/R/C Thursday, February 06, 2003 03:05:53 PM 120 QUESTIONS REPORT for BSEP 2003 Final Draft CR 106. GEN 2.1.10 002 Which ONE of the following changes in plant operating conditions will result in a higher MCPR operating limit as specified in the COLR? Af 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. 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. Notes Cde--- - Cc.- S- 7/ Response form Categories RO Tier: T3 SRO Tier: T3 Keyword: COLR Cog Level: C/A 2.7/3.9 Source: Exam: BSEP 2003 Test: C Misc: LSM/R/C Thursday, February 06, 2003 03:05:53 PM 121 QUESTIONS REPORT for BSEP 2003 Final Draft CR 107. GEN 2.1.12 001 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? (Preyide TS Section 3.6,---ý2 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 />. Bf 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 />. 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 />. Notes Response form Categories RO Tier: SRO Tier: T3 Keyword: MAINTENANCE Cog Level: C/A 2.9/4.0 Source: N Exam: BSEP 2003 Test: S Misc: LSM/TCK/R/C Thursday, February 06, 2003 03:05:54 PM 122 QUESTIONS REPORT for BSEP 2003 Final Draft CR 108. GEN 2.1.28 001 Which ONE of the following describes why the plant must be placed in HOT -SHUTDOWNwith 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 inoperable. 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 Notes reworded C to make it correct Response form Categories RO Tier: T3 SRO Tier: T3 Keyword: TS Cog Level: MEM 3.2/3.3 Source: B Exam: BSEP 2003 Test: C Misc: LSM/R/C Thursday, February 06, 2003 03:05:54 PM 123 QUESTIONS REPORT for BSEP 2003 Final Draft CR 109. GEN 2.2.12 001 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? A' 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. Feedback A. This is the correct configuration B. The Walking beam 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. Notes changed walking beam type to mechanical since walking beam is not a familiar term at BSEP. Response form Categories Categories Response SRO Tier: RO Tier: T3 Keyword: SURVEILLANCE Cog Level: MEM 3.0/3.4 Source: N Exam: BSEP 2003 Test: R Misc: LSM/R/C Thursday, February 06, 2003 03:05:54 PM 124 QUESTIONS REPORT for BSEP 2003 Final Draft CR 110. GEN 2.2.13 001 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. Bf Should be monitored for seat leakage. C. Should be monitored for drift. D. A mechanical positioning device or a gag is required. Feedback OPS-NGGC-1 301 rev 10 pages 68 -70 A. Solenoid operating valve B. Correct C. Limitorque valve D. Hydraulic Operated valve Notes specified air operated butterfly valve to make question more specific and modified distractor A to be incorrect. Per OPS-NGGC-1 301 butterfly valves and flow control valves require that you monitor for seat leakage. Response form Categories RO Tier: T3 SRO Tier: Keyword: TAGGING Cog Level: MEM 3.6/3.8 Source: N Exam: BSEP 2003 Test: R Misc: LSM/R/C Thursday, February 06, 2003 03:05:54 PM 125 QUESTIONS REPORT for BSEP 2003 Final Draft CR 111. GEN 2.2.14 001 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. Cf 4 months from the interim approval date. D. 4 months from the procedure's periodic review date. Feedback new procedure PRO-NGGC-0204 r)ev. 2 has 4 months from interrim approval date. J1 Response form Categories RO Tier: SRO Tier: T3 Keyword: ADMIN Cog Level: MEM 2.1/3.0 Source: B Exam: BSEP 2003 Test: S Misc: LSM/R/C Thursday, February 06, 2003 03:05:54 PM 126 QUESTIONS REPORT for BSEP 2003 Final Draft CR 112. GEN 2.2.17 001 You are the Unit 2 SS. During movement of material through the HPCI Room, -insulation has been damaged. -A repair-crew has beewassembled. The wet-bulb temperature is 103.1OF 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 D. 100 minutes Feedback Reference allowed 0AI-1 07 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 I 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 = 1 hour 40 minutes Notes added HPCI Room for location that may be at 103F Response form Categories RO Tier: SRO Tier: T3 Keyword: MAINTENANCE Cog Level: C/A 2.3/3.5 Source: N Exam: BSEP 2003 Test: S Misc: LSM/R/C Thursday, February 06, 2003 03:05:54 PM 127 QUESTIONS REPORT for BSEP 2003 Final Draft CR 113. GEN 2.2.27 001 You are the refueling floor SRO. Unit 1 is in refueling with all but four assemblies off loaded. Supplemental Spent Fuel Pool Cooling System is operating as follows: Primary Pump P-74A and both heat exchangers are in service Secondary pump P-82A and both cooling towers are in service P-82A tripped due to a flexible coupling failure. Following the trip P-74A also tripped. Which ONE of the following conditions must be satisfied prior to restarting P-74A? A' Secondary loop pressure must be restored. B. Primary pump seal water must be restored. C. One heat exchanger must be taken out of service. D. One fire pump must be started and aligned to the supplemental cooling header. Feedback References: based on LOI-CLS-LP-013-A*16B Notes Response form Categories RO Tier: SRO Tier: T3 Keyword: REFUELING Cog Level: C/A 2.6/3.5 Source: M Exam: BSEP 2003 Test: S Mise: LSM/R/C Thursday, February 06, 2003 03:05:54 PM 128 QUESTIONS REPORT for BSEP 2003 Final Draft CR 114. GEN 2.2.3 001 Which one of the following is a feature of Unit 1 only? A. Select Rod Insert may be manually initiated bythe 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. Dý When not in "Run" an IRM upscale will provide an RPS trip. There is no APRM downscale RPS trip. Feedback SD -03 Solution - A, B, and C are Unit 2 only features Notes Response form Categories RO Tier: T3 SRO Tier: T3 Keyword: UNIT DIFFERENCES Cog Level: MEM 3.1/3.3 Source: N Exam: BSEP 2003 Test: C Misc: LSM/R!C Thursday, February 06, 2003 03:05:54 PM 129 QUESTIONS REPORT for BSEP 2003 Final Draft CR 115. GEN 2.3.1 001 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 Notes Response form Categories RO Tier: T3 SRO Tier: T3 Keyword: RADWASTE Cog Level: MEM 2.6/3.0 Source: B Exam: BSEP 2003 Test: C Misc: LSM/R/C Thursday, February 06, 2003 03:05:54 PM 130 QUESTIONS REPORT for BSEP 2003 Final Draft CR 116. GEN 2.3.11 001 Unit 2 is at 89% power when the Reactor Building Vent Exhaust Rad Monitor N01OA fails upscale. Shortly after you override the CAC isolation due to the Rad Monitor N01OA failing upscale, a Unit 1 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. D. All group 6 CAC valves would automatically close. Feedback Notes local to manual Response form Categories RO Tier: T3 SRO Tier: Keyword: RAD RELEASE Cog Level: 2.7/3.2 Source: M Exam: BSEP 2003 Test: R Misc: LSM/R/C Thursday, February 06, 2003 03:05:54 PM 131 QUESTIONS REPORT for BSEP 2003 Final Draft CR 117. GEN 2.3.4 001 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 approximately 7.5 REM TEDE. 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. Thursday, February 06, 2003 03:05:54 PM 132 QUESTIONS REPORT for BSEP 2003 Final Draft CR Feedback SRO ONLY-. Based on a previous bank question LOI-CLS-LP- 102-A* 11 BOO 1 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. 5 Rem TEDE Site Emergency Coordinator (SEC) B. 5 Rem TEDE Emergency Response Manager (ERM) C. 10 Rem TEDE Site Emergency Coordinator (SEC) D. 10 Rem TEDE Emergency Response Manager (ERM) Answer: C LOI-CLS-LP-102-A* 11B001 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. 5 Rem TEDE Site Emergency Coordinator (SEC) B. 5 Rem TEDE Emergency Response Manager (ERM) C. 10 Rem TEDE Site Emergency Coordinator (SEC) D. 10 Rem TEDE Emergency Response Manager (ERM) Answer: C Notes Response form Categories RO Tier: SRO Tier: T3 Keyword: RAD MONITORING Cog Level: CA 2.5/3.1 Source: N Exam: BSEP 2003 Test: S Misc: LSM/R/C Thursday, February 06, 2003 03:05:54 PM 133 QUESTIONS REPORT for BSEP 2003 Final Draft CR 118. GEN 2.4.1 001 Following an incomplete Reactor scram, the operating crew is executing EOP-01-LPC, Level/PowerControl. 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 Notes Response form Categories RO Tier: T3 SRO Tier: T3 Keyword: SHUTDOWN Cog Level: C/A 4.3/4.6 Source: B Exam: BSEP 2003 Test: C Misc: LSM/R/C Thursday, February 06, 2003 03:05:54 PM 134 QUESTIONS REPORT for BSEP 2003 Final Draft CR 119. GEN 2.4.11 001 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? Af 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 A. REFERENCES: AOP-02.0 R7 Answer: A Bank - LOI-CLS-LP-302-B*003001 Notes Response form Categories RO Tier: T3 SRO Tier: Keyword: RPIS Cog Level: MEM 3.4/3.6 Source: B Exam: BSEP 2003 Test: R Misc: LSM/R/C Thursday, February 06, 2003 03:05:55 PM 135 QUESTIONS REPORT for BSEP 2003 Final Draft CR 120. GEN 2.4.11 002 Unit heatup and pressurization is in progress per GP-02. Current plant conditions: Reactor-p-ower- 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? Af 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 Notes Response form Categories RO Tier: SRO Tier: T3 Keyword: CRD Cog Level: C/A 3.4/3.6 Source: N Exam: BSEP 2003 Test: S Misc: LSM/R/C Thursday, February 06, 2003 03:05:55 PM 136 QUESTIONS REPORT for BSEP 2003 Final Draft CR 121. GEN 2.4.18 001 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? Af 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 Notes Response form Categories RO Tier: T3 SRO Tier: T3 Keyword: EOP BASIS Cog Level: C/A 2.7/3.6 Source: B Exam: BSEP 2003 Test: C Misc: LSM/R/C Thursday, February 06, 2003 03:05:55 PM 137 QUESTIONS REPORT for BSEP 2003 Final Draft CR 122. GEN 2.4.2 001 During a Station Blackout on Unit One HPCI, RCIC and LPCI have all become unavailable for injection to the RPV. Plant conditions: RPV water level -55 inches (N036) RPV pressure 300 psig Drywell ref leg temp 3150 F Injection sources None available Which one of the following describes the current RPV water level? A. above the Minimum Steam Cooling Reactor Water Level, adequate core cooling is assured. B" above the Minimum Zero-Injection Reactor Water Level, adequate core cooling is assured. C. below the Minimum Steam Cooling Reactor Water Level, adequate core cooling is NOT assured. D. below the Minimum Zero-Injection Reactor Water Level, adequate core cooling is NOT assured. Feedback BSEP PROVIDE APPROPRIATE REFERENCE IF REQUIRED 5. LOI-CLS-LP-300-B*008004 Notes Response form Categories RO Tier: T3 SRO Tier: T3 Keyword: BLACKOUT Cog Level: C/A 3.9/4.1 Source: B Exam: BSEP 2003 Test: C Misc: LSM/R/C Thursday, February 06, 2003 03:05:55 PM 138 QUESTIONS REPORT for BSEP 2003 Final Draft CR 123. GEN 2.4.27 002 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 Notes Response form Categories RO Tier: SRO Tier: T3 Keyword: SAFE SHUTDOWN Cog Level: C/A 3.0/3.5 Source: N Exam: BSEP 2003 Test: S Misc: LSM/RJC Thursday, February 06, 2003 03:05:55 PM 139 QUESTIONS REPORT for BSEP 2003 Final Draft CR 124. GEN 2.4.3 001 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 0 F Rx Bldg 50' temp 145 0 F 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" N004A/B/C only. B. N004A/B/C and N026A/B only. C. N004A/B/C and N027AIB 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 Notes Response form Categories RO Tier: T3 SRO Tier: T3 Keyword: SCRAM Cog Level: C/A 3.5/3.8 Source: M Exam: BSEP 2003 Test: C Misc: LSM/R/C Thursday, February 06, 2003 03:05:55 PM 140 QUESTIONS REPORT for BSEP 2003 Final Draft CR 125. GEN 2.4.48 001 Unit 1 is operating at 100 % power. The unit receives a Group 6 isolation and did NOT receive a Secondary Containment Isolation. Which ONE of the following may have occurred? A. High Drywell Pressure. B. Rx Bldg Exhaust Radiation High. C. Rx Vessel Water Level Low LL2. oDRx Vessel Water Level Low LLI. Feedback References: LOI-CLS-LP-012-A LOI-CLS-LP-004-B Notes Response form Categories RO Tier: SRO Tier: T3 Keyword: INDICATIONS Cog Level: C/A 3.5/3.8 N Exam: BSEP 2003 Source: S Misc: LSM/R Test: Thursday, February 06, 2003 03:05:55 PM 141