ML032340720
| ML032340720 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/16/2003 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Scalice J Tennessee Valley Authority |
| Shared Package | |
| ML032380265 | List: |
| References | |
| 50-259/02-301, 50-260/02-301, 50-296/02-301 50-259/02-301, 50-260/02-301, 50-296/02-301 | |
| Download: ML032340720 (104) | |
See also: IR 05000259/2002301
Text
Draft Submittal
BROWNS FERRY
EXAM 2002-301
50-259, 50-260, & 50-296
DECEMBER 13,16-19,2002
1.
Senior Reactor Operator Written Exam
QUESTIONS REPORT
for Browns Ferry Questions
1. 201001A2.01 001
While operating at 25% power the Unit Operator reports the following:
- CRD Pump A Breaker Disagreement White Light.
- Motor Trip Out Annunciator and Horn Received.
- 1 B CRD Pump in Standby.
Which ONE of the following describes the IMMEDIATE actions to be taken for the
above conditions?
A. Start CRD pump 1 B and open the CRD PUMP DISH TO UNIT 2. Adjust the CRD
SYS FLOW CONTROLLER tapeset to adjust CRD cooling water header
differential pressure to 20 psid and CRD system flow to approximately 60 gpm.
B. Place CRD SYS FLOW CONTROLLER in MAN at MAXIMUM setting. Start CRD
pump 1 B. Open CRD PUMP DISCH TO UNIT 2. When CRD cooling water header
differential pressure reaches 20 psid, and CRD system flow reaches between 45
and 75 gpm, balance CRD SYS FLOW CONTROLLER and place in AUTO.
C. Start CRD pump 1B. Place CRD SYS FLOW CONTROLLER in MAN at MINIMUM
setting. Open CRD PUMP DISCH TO UNIT 2. Adjust CRD SYS FLOW
CONTROLLER to establish 20 psid cooling water header differential pressure.
Balance CRD SYS FLOW CONTROLLER and place in AUTO.
D? Place CRD SYS FLOW CONTROLLER in MAN at MINIMUM setting. Start CRD
pump 1 B. Open CRD PUMP DISCH TO UNIT 2. Adjust CRD SYS FLOW
CONTROLLER to establish 20 psid CRD cooling water header differential pressure
and CRD system flow between 40 and 65 gpm. Balance CRD SYS FLOW
CONTROLLER and place in AUTO.
References: 2-AOl-85-3 Rev. 20 pg 1 and 2
NOTE: Revised some of the distractors to make them more plausible.
Also, revised stem to ensure that it is clear that these are
IMMEDIATE operator actions.
A. Incorrect since flow controller must be adjusted to minimum setting prior to starting
the pump.
B. Incorrect since flow controller must be adjusted to MINIMUM instead of MAXIMUM.
C. Incorrect since flow controller must be adjusted to minimum setting prior to starting
the pump.
Tuesday, January 21,2003 08:41:33 AM
1
ROTier:
T2G1
Keyword
CRD SYSTEM
Source:
B
Test:
C
Tuesday, January 21,2003 08:41:34 AM
QUESTIONS REPORT
for Browns Ferry Questions
SRO Tier:
T2G2
Cog Level: MEM 3.2/3.3
Exam:
BF02301
Misc:
TCK
2
QUESTIONS REPORT
for Browns Ferry Questions
2. 201006K3.01 001
The following conditions exist on Unit 3:
RWM Bypass Switch in Normal.
Core Power level is above the Low Power Setpoint.
The RWM program has NOT been initialized
Control Rod 22-35 at position 18 (group limit 00-12)
-
-
Which ONE of the following is the reason that control rod 22-35 cannot be moved?
A. Withdraw Block is in effect.
B. Insert Block is in effect.
C:' Select Block is in effect.
D. Withdraw Error has occured.
References: OPLl71.024 Rev. 10 pg 13-1 6
A, B and D are incorrect since a Select Block is in effect due to RWM Bypass Switch in
NORMAL and the RWM program has not been initiated.
C. Correct answer.
ROTier:
T2G2
Keyword
Source:
N
Test:
C
SRO Tier:
T2G2
Cog Level: CIA 3.213.5
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:34 AM
3
QUESTIONS REPORT
for Browns Ferry Questions
3. 20200262.2.3 002
Which ONE of the following choices correctly describes the response of the Unit 2 and
Unit 3 reactor recirculation pump (RRP) speed control to an increase in core differential
pressure?
A. On Unit 2 the RRP speed must be manually adjusted by the operator but Unit 3 will
automatically reposition the scoop tube to bring speed back to the setpoint.
B. Both Unit 2 and Unit 3 must be manually adjusted by the operator to bring speed
back to the setpoint.
C. Unit 2 will automatically reposition the scoop tube to bring speed back to the
setpoint but on Unit 3 the RRP speed must be manually adjusted by the operator.
D. Both Unit 2 RRP and Unit 3 will automatically reposition the scoop tube to bring
speed back to the setpoint.
JUSTIFICATION
Unit 2 and 3 speed feedback are enabled.
REF: OPL171.007, Rev. 15, Page 36
OPL171 R007, Rev. 0, Page 11
ROTier:
T2G1
SRO Tier:
T2G1
Keyword
RECIRC SYSTEM
Cog Level: MEM 3.113.3
Source:
B
Exam:
BF02301
Test:
C
Misc:
Tuesday, January 21,2003 08:41:34 AM
4
QUESTIONS REPORT
for Browns Ferry Questions
4. 203000A4.01 001
During a level transient on Unit 2 the following events occurred:
- RPV water level decreased to -125 inches during the transient
- ADS actuated
- RHR Pump 2A and 2B started and injected to the reactor vessel
- RPV water level is now +25 inches and increasing
- No operator actions have been taken
Which ONE of the following statements describes the RHR system response if RHR
Pump 2A control switch is placed to the STOP position?
A.' RHR Pump 2A will stop and the amber auto-start lockout light will light.
8. RHR Pump 2A will stop and the amber auto-start lockout light will extinguish.
C. No change; RHR Pump 2A will continue to run until the LOCA initiation signal is
reset.
D. RHR Pump 2A will stop and then restart when the switch is released. The amber
auto-start lockout light will not change indication.
References: OPLl71.044 Rev. 10 pg 61
Enabling Objective #I3
2-01-74 Rev. 0107 pg 8
A. Correct answer.
B. Incorrect since the RHR system is designed to allow a pump to be secured and
auto-initiation lock-out.
C.lncorrect since the amber light is the auto-init. lockout indication and will not
extinguish until the LOCA signal is reset.
D. Incorrect since both sentences are incorrect.
ROTier:
T2G1
Keyword
Source:
B
Test:
C
SRO Tier:
T2G1
Cog Level: CIA 4.314.1
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 0841 :34 AM
5
QUESTIONS REPORT
for Browns Ferry Questions
5. 203000K3.02 001
Gross fuel failure is suspected on Unit 3. The crew is in 3-EO/ Appendix 18 -
Suppression Pool water Inventory Removal and Makeup and have just closed
3-FCV-74-63, RHR RADWASTE SYS FLUSH VALVE. Suppression Pool level is -2.5
inches and steady.
Which ONE ofthe~following-are the ~appropriate~actions?
~ ~.~
~~~
-~~
A:
Exit 3-EO1 Appendix 18 - Suppression Pool water Inventory Removal and Makeup
since Suppression Pool water level is within acceptable limits.
B. Open 3-FCV-74-63, RHR RADWASTE SYS FLUSH VALVE and direct Suppression
Pool water to Radwaste ONLY.
C. Open 3-FCV-74-62, RHR MAIN CNDR FLUSH VALVE and direct Suppression Pool
water to the Main Condenser ONLY.
D. Open 3-FCV-74-62, RHR MAIN CNDR FLUSH VALVE and direct Suppression Pool
water to the Main Conderser or open 3-FCV-74-63, RHR RADWASTE SYS FLUSH
VALVE and direct Suppression Pool water to Radwaste.
References: 3-EO1 Appendix 18
WHEN Suppression Pool level can be maintained between -1 in. and -5.5 in. THEN
EXIT this procedure.
ROTier:
T2G1
SRO Tier:
T2G1
Keyword
SUPPRESSION CHAMBER
Cog Level: CIA 3.513.5
Source:
B
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:34 AM
6
QUESTIONS REPORT
for Browns Ferry Questions
6. 204000K5.05 001
I
Which ONE of the following describes the signals that will close the RWCU Blowdown
Valve (FCV 69-15)?
A. Low Reactor Water Level +2, Standby Liquid Control initiation.
BY High downstream pressure 140 psig, low upstream pressure 5 psig.
C. High RWCU Pump Rm temp 140°F, high temp on outlet of NRHX 140°F.
D. High flow 250 gpm, high differential pressure across valve 25 psid.
~
References: OPL171.013 Rev.12 pg 22-24
A,C and D Incorrect since these signals do not close the blowdown valve.
B. Correct answer.
ROTier:
T2G2
Keyword
RWCU SYSTEM
Source:
N
Test:
C
SRO Tier:
T2G2
Cog Level: MEM 2.612.6
Exam:
BF02301
Misc:
TCK
Tuesday, Janualy 21,2003 0841 :34 AM
7
QUESTIONS REPORT
for Browns Ferry Questions
7. 205000A4.05 001
Unit 2 is in a refueling outage with Loop II of RHR in shutdown cooling. The RHR
SYSTEM II MIN FLOW INHIBIT switch is in the INHIBIT position. The Unit Operator
then places the RHR Loop II Minimum Flow Valve (2-FCV-74-30) Control Switch to the
OPEN position.
Which ONE of the following describes the effect on the Minimum Flow Valve?
A. Valve would not open.
B. Valve would open then immediately go back closed.
C. Valve would open regardless of RHR flow and remain open.
D. Valve would open only if RHR flow was less than min flow closing setpoint.
I
References: OPL171.044 Rev. 10 pg 33 and 34
2-01-74 Rev. 107 pg 73
Enabling Objective OPL171.044 #IO
A. Incorrect since valve would open and immediately close.
B. Correct answer.
C. Incorrect since valve would not remain open.
D. Incorrect since valve would open regardless of min flow signal.
ROTier:
T2G2
SRO Tier:
T2G2
Keyword
RHR SYSTEM
Cog Level: MEM 3.213.2
Source:
B
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, Janualy 21,2003 08:41:34 AM
8
QUESTIONS REPORT
for Browns Ferry Questions
8. 2o6000~3.05 001
HPCl is operating in the pressure control mode (suction from the CST and return to the
CST through FCV 73-35 and 36) when reactor water level lowers to -50.
Which ONE of the following describes HPCl response?
A. HPCl will be unaffected and continue to operate in the pressure control mode.
B. FCV 73-44 (inboard injection valve) opens; FCVs 73-35 and 36 remain open; HPCl
does not inject to the reactor.
C:' FCV 73-44 (inboard injection valve) opens: FCVs 73-35 and 36 close; HPCl injects
to the reactor.
D. FCV 73-44 (inboard injection valve) opens; FCV 73-35 closes; FCV 73-36 remains
open; HPCl injects to the reactor.
Reference: OPL171.042 Rev. 16 pg 42
A. Incorrect since HPCl has received an initiation signal from low water level. Setpoint
is -45.
B. Incorrect since FCV's 73-35 and 36 receive a closed signal if they were open.
C. Correct answer.
D. Incorrect since both FCV's 73-35 and 36 receive a closed signal.
ROTier:
T2G1
SRO Tier:
T2G1
Keyword
Cog Level: CIA4.314.3
Source:
B
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:34 AM
9
QUESTIONS REPORT
for Browns Ferry Questions
9.
209001K5.05 001
Unit 3 has been at 100% RTP for the last 6 months. The Flow Rate test for HPCl is in
progress to verify OPERABILITY after maintenance was performed on the system.
2-SR-3.5.1.1-(CS I), Core Spraysystem Venting Loop 1 was last performed on
November 15th, 2002. The UO was sent out to perform the surveillance on December
16th, 2002 and reported back that he was unable to open the High Point Vent valve
(2-SHV-075-0071).-
Which ONE of the following describes the consequences to Unit 3 of not being able to
perform this surveillance?
A. Loop 1 Core Spray must be declared INOPERABLE immediately and Unit 3 enters
a 7 day LCO.
B. Loop 1 Core Spray venting must be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the system
declared INOPERABLE which would place Unit 3 in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO.
C. Loop 1 Core Spray venting must be performed within 7.75 days or the system
declared INOPERABLE which would place Unit 3 in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO.
D? Loop 1 Core Spray venting must be performed within 7.75 days or the system
declared INOPERABLE which would place Unit 3 in a 7 day LCO.
References: Tech Spec 3.5.1, ECCS-Operating
2-SR-3.5.1.1 (CS 1) Rev. 1 pg 4 and 6
A. Incorrect since the grace period for the surveillance hasnt expired.
B. Incorrect since the grace period for the surveillance is 7.75 days and not 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C. Incorrect since by the time that the 7.75 days expire then HPCl must be OPERABLE
or the unit is already shutdown.
D. Incorrect since HPCI will be OPERABLE by the time the 7.75 days has expired.
ROTier:
T2Gl
SRO Tier:
T2G1
Keyword
Cog Level: CIA2.512.5
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:34 AM
10
QUESTIONS REPORT
for Browns Ferry Questions
10. 211000K1.01001
Which ONE of the following describes the relationship between the SLC System and
the Core Spray System?
A:' The SLC sparger provides a sensing point for the Core Spray Break Detection
logic.
.
.~
~
.
.
.
.
.
j ._;
.
. , , . . .
-
.~~
, .
~~
.. .
. ~ .
. .
.
_.
B. The SLC sparger provides a sensing point for the Core Spray flow indication.
C. The Core Spray System is totally independent of the SLC System.
D. The same Shutdown Board powers the 2B SLC Pump and the 28 Core Spray
Pump.
References: OPL171.045 Rev.11 pg 13
OPL171.039 Rev.13 pg 14,26 and 27
Enabling Objective OPL171.039 #4
A. Correct answer.
B. Incorrect since the sparger has no input to Core Spray flow.
C. Incorrect since Core Spray does interact with SLC through the sparger.
D. Incorrect since 2B Core Spray is powered from SD BD " C and 2B SLC pump is
powered from SD BD "B.
ROTier:
T2G1
SRO Tier:
T2G1
Keyword
Cog Level: MEM 3.0/3.3
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:35 AM
11
QUESTIONS REPORT
for Browns Ferry Questions
11. 211000K6.03001
Which ONE of the following describes the power supply and interlocks of the SLC
pumps?
A. One pump is powered from 250V RMOV Board A and one from 480V Shutdown
-
- ._
Board B. The pumps are electrically interlocked so that both pumps run, if
-available.
BY One pump is powered from 480V Shutdown Board A and one from 480V Shutdown
Board B. The pumps are electrically interlocked so that only one pump will run at a
time.
C. One pump is powered from 250V RMOV Board A and one from 480V Shutdown
Board B. The pumps are electrically interlocked so that only one pump will run at a
time.
D. One pump is powered from 480V Shutdown Board A and one from 480V Shutdown
Board B. The pumps are electrically interlocked so that both pumps run, if
available.
250 VDC is control power for the valves.
Two 100% capacity, triplex, positive displacement piston pumps powered from 480V
Shutdown Bds A and B respectively are installed in parallel. The pumps are electrically
interlocked so that only one pump can be run at a time to prevent overpressurization of
the system.. This is accomplished by B-finger contacts in the start circuit of the running
pump, opening contacts in the start circuit of the idle pump.
ROTier:
T2G1
SRO Tier:
T2G1
Keyword:
SBLC
Cog Level: MEM 3.213.3
Source:
B
Exam:
BF02301
Test:
C
Misc:
Tuesday, January 21,2003 08:41:35 AM
12
QUESTIONS REPORT
for Browns Ferry Questions
12. 212000A1.08 001
Unit 3 scrammed due to a spurious Group 1 isolation. The Mode Switch is in
Shutdown and all rods are inserted. Reactor water level has been restored to the
normal operating band. The Unit Supervisor has ordered the Reactor Operator to rese
the scram.
Which ONE of the following describes the status of the Backup Scram Valves when tht
Reactor Operator moves the "Reset" switch to the right?
Both Backup Scram Valves should be ...
-
A. energized and OPEN.
B! de-energized and CLOSED.
C. energized and CLOSED.
D. de-energized and OPEN.
References: OPL171.028 Rev.13 pg 22
A,C and D are incorrect since the Backup Scram Valves should be de-energized and
CLOSED.
B. Correct answer.
ROTier:
T2G1
Keyword
Source:
N
Test:
C
SRO Tier:
T2G1
Cog Level: MEM 3.4/3.4
Exam:
BF02301
Mix:
TCK
Tuesday, Janualy 21,2003 08:41:35 AM
13
QUESTIONS REPORT
for Browns Ferry Questions
13. 214000K4.01001
Which ONE of the following statements is describes the operation of the Rod Position
Information System (RPIS)?
A! If both of the S52 and SO0 normal full-in reed switches are closed the full core
display will be backlit green and display 00.
B. The S48 full-out digital display reed switches also supply rod position input signals
to the "CONTROL ROD OVERTRAVEL" alarm.
C. On an uncoupled control rod, the full core display will show position 49 and no red
backlight if the rod is withdrawn to the overtravel position.
D. When a CRD is driven beyond the full-in position the S51 over-travel reed switch
will be actuated. The full-core digital display for that rod will display 00 and be
backlit green.
References: OPLl71.029 Rev. 9 pg 19 and 20.
A. Correct answer.
B. Incorrect since the S50 switch provided indication for Rod Overtravel.
C. Incorrect since there is no position indication for an uncoupled control rod.
D. Incorrect since overtravel beyond full-in is --.
ROTier:
T2G2
SRO Tier:
T2G2
Keyword
RF'IS SYSTEM
Cog Level: MEM 3.0/3.1
Source:
B
Exam:
BF02301
Test:
C
Misc:
Tuesday, January 21,2003 08:41:35 AM
14
QUESTIONS REPORT
for Browns Ferry Questions
14. 215004K4.01 001
I
A reactor startup is in progress on Unit 2 with the following conditions:
Mode Switch is in START/HOT STBY
IRM A is on range 2 with all other IRMs on range 3
The SRMs are partially withdrawn
SRM count rate ranges between 80 and 90 cps
~
-
The Reactor Operator attempts to withdraw control rod 24-33 but it will not move.
Which ONE of the following is the reason why the rod cannot be withdrawn?
A. SRM Downscale rod block.
BY Detector Wrong Position rod block.
C. SRM Hi rod block.
D. SRM hop rod block.
L
References: OPL171.019 Rev.6 pg 21 and 22
Enabling Objective OPL171.019 #8
A. Incorrect since the SRM downscale rod block is <5 cps.
B. Correct answer.
C. Incorrect since the SRM Hi rod block is 6.8 X I O 4
D. Incorrect since SRMs are not INOP.
ROTier:
T2Gl
SRO Tier:
T2G1
Keyword
Cog Level: CIA 3.713.7
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:35 AM
15
QUESTIONS REPORT
for Browns Ferry Questions
15. 215005K3.01001
Which ONE of the following Mode Switch position and Nuclear Instrumentation signal
combinations will cause ONLY a REACTOR CHANNEL "A" AUTO SCRAM?
A.* RUN; 2/4 Voter A I in TEST.
B. STARTUP; 2/4 Voter B2 in TEST.
C. RUN; IRM "G" Upscale.
D. STARTUP; Channel 2 OPRM PBA Trip and Channel 4 OPRM GBA Trip.
I
References: Tech Specs 3.3.1.1-1 pg 3.3-7 and 3.3-8
OPL171.148 Rev.7 pg 24-56
A. Correct answer.
B. Only required in Mode 1.
C. Incorrect since IRM Hi does not generate trip with Mode Switch in Run.
D. Only required in Mode 1.
ROTier:
T2G1
SRO Tier:
T2G1
Keyword
Cog Level: MEM 4.014.0
Source:
B
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:35 AM
16
QUESTIONS REPORT
for Browns Ferry Questions
16. 216000A2.14 001
During a startup the operators begin to raise recirculation pump flow.
How does raising recirc flow from 50% to 65% affect the Panel 9-5 RPV level
indicators?
A,' Emergency range indicated level will trend downward.
8. Narrow range indicated level will trend upward.
C. Emergency range indicated level will trend upward.
D. Narrow range indicated level will trend downward.
U-068-NO-03
ROTier:
T2G1
SRO Tier:
T2G1
Keyword
LEVEL INSTRUMENTS
Cog Level: CIA2.912.9
Source:
B
Exam:
BF02301
Test:
C
Misc:
Tuesday, Janualy 21,2003 08:41:35 AM
17
QUESTIONS REPORT
for Browns Ferry Questions
17. 217000K2.02 001
Unit 2 is operating at 100% RTP when the 250VDC Reactor MOV Board B Logic Bus A
de-energizes. An operator has been sent to investigate and reports that the feed
breaker has failed.
Which ONE of the following describes the operation of HPCl and RClC if reactor water
level decreases to - 4 5 under these conditions?
A. HPCl and RClC will both automatically initiate but will not auto isolate if needed.
B! HPCl will automatically initiate but will not auto isolate if needed and RClC will not
automatically initiate.
C. Both HPCl and RClC will not initiate automatically but may be operated manually.
D. HPCl will not automatically initiate and RClC will automatically initiate but will not
auto isolate if needed.
References: 2-ARP-9-3F pg 4
2-ARP-9-3C pg 2
A. Incorrect since RClC initiation logic will not work.
B. Correct answer.
C. Incorrect since HPCl will still initiate automatically.
D. Incorrect since HPCl will automatically initiate and RClC will NOT automatically
initiate.
NOTE: RClC and HPCl recieve an initiation signal when RWL reaches -45.
ROTier:
T2G1
SRO Tier:
T2G1
Keyword
RCIC SYSTEM
Cog Level: CIA 2.812.9
Source:
N
Exam:
BF02301
Test:
C
Mix:
TCK
Tuesday, January 21,2003 08:41:35 AM
18
QUESTIONS REPORT
for Browns Ferry Questions
18. 218000K6.06 001
I
Various electrical malfunctions have occurred on Unit 2. Existing conditions are as
noted:
- 480V S/D Bd 2A deenergized
- 480V RMOV Bd 2C deenergized
- 250V RMOV Bd 28 deenergized
Which ONE of the following identifies the systems that are still available?
D I CS Loop 11, RHR Loop 11, HPCI
ROTier:
TZGI
SRO Tier:
T2G1
Keyword
480V DISTRIBUTION
Cog Level: CIA 3.413.6
Source:
B
Exam:
BF02301
Test:
C
Misc:
Tuesday, January 21,2003 0841:35 AM
19
QUESTIONS REPORT
for Browns Ferry Questions
19. 223001A2.11001
Unit 3 is being shutdown due to Suppression Chamber water level outside the Tech
Spec operating band. The following conditions exist for Unit 3:
Reactor Power
23% RTP
Suppression Chamber level
Current Time
0800
Drywell Pressure
1.5 psig (venting)
15 feet increasing at 1 ft/15 minutes
Predict which ONE of the following actions will be required per EOI-2 Primary
Containment Control.
(Refer to EOI-2 Primary Containment Control)
A. Be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Mode 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
B. Scram the reactor and lower RPV pressure e900 psig by 0830.
C. Commence Emergency Depressurization when Suppression Chamber level
exceeds 18 feet.
D. Scram the reactor and secure venting the containment.
References: EOI-2 Primary Containment Control Rev.6
A. Incorrect since EOI-2 doesnt direct when to be in Mode 3 or Mode 4.
B. Correct answer.
C. Incorrect since when the 18 ft level is reached then EOI-2 directs you to determine if
the Curve 4 parameters can be maintained in the safe region.
D. Incorrect since EOI-2 doesnt direct securing containment venting.
ROTier:
T2G1
SRO Tier:
T2G1
Keyword:
SUPPRESSION CHAMBER
Cog Level: CIA 3.613.8
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 06:41:36 AM
20
QUESTIONS REPORT
for Browns Ferry Questions
20. 223002K3.16 001
Unit 3 is in a refueling outage with Shutdown Cooling in operation on RHR Sys II. A
spurious Group II isolation is initiated by the Instrument Techs while performing a
surveillance. All isolation actions operate as designed.
Which ONE of the following describes the actions to take to allow re-opening
3-FCV-74-67, RHR SYS 11 LPCl INBD INJECT VLV?
A. Isolation signal has been reset AND either Shutdown Cooling Suction Valve is fully
closed.
B. RHR SYS II SD CLG INBD INJECT ISOL RESET pushbutton is depressed followed
by the group II isolation signal being reset.
CY Either Shutdown Cooling Suction Valve fully closed followed by the RHR SYS II SD
CLG INBD INJECT ISOL RESET pushbutton being depressed.
D. RHR SYS II SD CLG INBD INJECT ISOL RESET pushbutton is depressed followed
by either Shutdown Cooling Suction Valve being fully closed.
References: 3-01-74 Rev.52 pf 12
Enabling Objective OPL171.044 Rev.10 #B10
A. Incorrect since RHR SYS II SD CLG INBD INJECT ISOL RESET pushbutton must
be depressed after either of the listed conditions clears.
B. Incorrect since RHR SYS II SD CLG INBD INJECT ISOL RESET pushbutton must
be depressed AFTER the condition clears.
C. Correct answer.
D. Incorrect since RHR SYS II SD CLG INBD INJECT ISOL RESET pushbutton must
be depressed AFTER the condition clears.
ROTier:
T2G1
Keyword
RHR SYSTEM
Source:
N
Test:
C
SRO Tier:
T2G1
Cog Level: CIA 3.213.3
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:36 AM
21
QUESTIONS REPORT
for Browns Ferry Questions
21. 226001K1.09 001
Unit 3 is at 90% RTP when a LOCA occurs. The following conditions are present in thf
Containment:
Drywell Pressure
12.5 psig
Drywell Temperature
260°F
Suppression Pool Level
16 ft
Suppression Pool Temperature 150°F
The Unit Supervisor has ordered Drywell Sprays to be initiated per EO/-2, Primary
Confainment Control.
Which ONE of the following describes the affect on Containment when Drywell Sprays
are initiated? (Assume Suppression Chamber sprays have been initiated)
A. A large rapid reduction in Drywell pressure followed by the opening of the Reactor
Building to Suppression Chamber vacuum breakers followed by the opening of the
Suppression Chamber to Drywell vacuum breakers.
9. A slow reduction in Drywell pressure followed by the opening of the Reactor
Building to Suppression Chamber vacuum breakers followed by the opening of the
Suppression Chamber to Drywell vacuum breakers.
C. A slow reduction in Drywell pressure followed by the opening of the Suppression
Chamber to Drywell vacuum breakers followed by the opening of the Reactor
Building to Suppression Chamber vacuum breakers.
DY A large rapid reduction in Drywell pressure followed by the opening of the
Suppression Chamber to Drywell vacuum breakers followed by the opening of the
Reactor Building to Suppression Chamber vacuum breakers.
References: OPL171.044 Rev.10 pg 59
A. Incorrect since the Suppression Chamber to Drywell vacuum breakers open first.
9. Incorrect since the pressure reduction is rapid due to mainly steam in the Drywell.
C. Incorrect since the pressure reduction is rapid due to mainly steam in the Drywell.
D. Correct answer.
Tuesday, January 21.2003 08:41:36
22
RO Tier:
Keyword:
Source:
Test:
QUESTIONS REPORT
for Browns Ferry Questions
T2G2
SUPPRESSION CHAMBER
N
C
SRO Tier:
T2G1
Cog Level: CIA 3.0/3.1
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:36 AM
23
QUESTIONS REPORT
for Browns Ferry Questions
22. 233000K1.02 001
Which ONE of the following is CORRECT regarding RHR Supplemental Fuel Pool
Cooling?
A. The RHR pumps are preferred for use in this mode over the RHR drain pumps.
B. RHR Drain Pump B cannot be used to provide flow.
CY Should only be used when required to maintain Fuel Pool temperature below
-
.-
125°F.
D. RHR pump suction is taken from the fuel pool cooling pump discharge line.
References: OPLI 71.052 page 25
2-01-74 Rev. 107 pg 94
Enabling Objective #6
A. Incorrect since the drain pumps are preferred for use over the RHR pumps.
B. Incorrect since RHR Drain Pump B can be used for this function.
C. Correct answer.
D. Incorrect since the suction is taken from the Skimmer Surge Tank outlet.
Changed the correct answer to a totally different answer.
ROTier:
T2G3
SRO Tier:
T2G3
Keyword
FUEL POOL COOLING
Cog Level: MEM 2.9/3.0
Source:
M
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:36 AM
24
QUESTIONS REPORT
for Browns Ferry Questions
23. 239001K5 08 001
DC power has been lost to a MSIV solenoid valve.
Which ONE of the following describes the effect on the MSIV?
A. The valve will close if open.
B.' The valve will remain open if open.
C. The valve cannot be opened if closed.
D. The slow closure capability of the valve is lost.
~
References: OPLl71.009 Rev.8 pg 26
NOTE: Modified the stem slightly and reordered answers.
A. Incorrect since the AC and DC solenoids must de-energize to close the valve.
B. Correct answer.
C. Incorrect since only ONE of the solenoid valves must be energized to operate the
valve.
D. Incorrect since the solenoid valves do not affect the testing circuit.
ROTier:
T2G2
Keyword
Source:
B
Test:
C
SRO Tier:
T2G3
Cog Level: MEM 2612.7
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:36 AM
25
QUESTIONS REPORT
for Browns Ferry Questions
24. 239002K5.04 001
The following plant conditions exist:
Reactor Power
100% RTP
Reactor Pressure
1000 psig
Safety Relief Valve (SRV) 1-4 has lifted and failed to reseat.
Which ONE of the following SRV tailpipe temperatures would you expect to see on the
SRV that failed to close? (References attached)
A. 212°F
B. 290°F
C. 345°F
D. 545°F
JUSTIFICATION
A. Incorrect since this is saturation temperature for steam at tailpipe pressure
(atmospheric).
B. Correct answer. This is a throttling process and is therefore isenthalpic.
C. 340°F would be incorrectly determined if the candidate considered the process to be
isenthalpic to the saturation line, then followed the constant superheat line to
atmospheric pressure.
D. Incorrect since this is saturation temperature for reactor pressure.
ROTier:
T2G1
Keyword
RELIEF VALVE
Source:
B
Test:
C
SRO Tier:
T2G1
Cog Level: CIA 3.313.5
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 0841 :36 AM
26
QUESTIONS REPORT
for Browns Ferry Questions
25. 241000A4.11001
Which ONE of the following is the controlling parameter that is illuminated on the
Turbine Control Panel during a turbine roll to 1800 rpm?
A. Valve position.
~
~
~
~~~~~~
~~
~
.
~
~~
~~~~
~
~~
~
B. Pressure.
C.' Speed.
D. Load.
-
References: OPLl71.228 Rev. 0 pg
Enabling Objective OPL171.228 #9
A, B and D are incorrect since SPEED is the controlling parameter until the turbine
reaches "AT SET SPEED".
C. Correct answer.
ROTier:
T2G1
Keyword:
EHC SYSTEM
Source:
B
Test:
C
SRO Tier:
T2G1
Cog Level: CIA 3.113.1
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:36 AM
27
QUESTIONS REPORT
for Browns Ferry Questions
26. 245000K5.03 001
The main turbine shell is being warmed in accordance with GOI-100-IA, Unit Startup
and Power Operation and 01-47, Turbine Generator System.
Which one of the following is the correct turbine valve configuration?
CONTROL VALVES
STOP VALVES
INTRCPT STOPS
INTRCPT CONTROL
A. Fullopen
1,3 & 4 closed
Full closed
Full open
(# 2 BP open)
BY Full open
1,3 & 4 closed
Full closed
Full closed
(#2 BP open)
C. Full closed
Full closed
Full open
Full open
D. Fullopen
Full open
Full open
Full closed
Taskno: U-047-NO-02
ROTier:
T2G2
SRO Tier:
T2G2
Keyword
TURBINE CONTROLS
Cog Level: CIA2.612.6
Source:
B
Exam:
BF02301
Test:
C
Misc:
Tuesday, January 21,2003 06:41:36 AM
28
QUESTIONS REPORT
for Browns Ferry Questions
27. 259001A1.01 001
Unit 2 is at 100% RTP. A heater tube leak activates alarm 2-LA-6-4, HEATER A2
LEVEL HIGH. The Operator checks the ICs screen and verifies a valid HIGH HIGH
(Red) level. Heater level continues to rise.
Whigh ONE of the following describes the required Operator action and the response
of the plant?
A? The Operator should be directed reduce Core Thermal Power and verify 2A2 heatei
high level dump valve to the main condenser OPENS.
6. The Operator should be directed to hold power constant and verify the 2A2 high
level dump valve to the heater drain cooler OPENS.
C. The Operator should be directed to reduce Core Thermal Power and verify HP
Heater 2A1 extraction isolation valve is OPEN.
D. The Operator should be directed to hold power constant and verify the drain inle
flow from the 2A2 heater to the 2A1 heater is isolated.
References: 2-ARP-9-6A Rev.16 pg 10
Note: Modified from a question on the last exam.
A. Correct answer.
B. Incorrect since core thermal power should be lowered.
C. Incorrect since the drain for the 2A2 heater to the 2A1 heater should be open.
D. Incorrect since core thermal power should be lowered.
ROTier:
T2G1
Keyword
Source:
M
Test:
C
SRO Tier:
T2G2
Cog Level: CIA 3.313.3
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 0841:37 AM
29
QUESTIONS REPORT
for Browns Ferry Questions
28. 262001K4.06 001
Unit 2 is operating at 100% RTP.
-A combination of errors cause an inadvertent Group 1 and Group 4 isolation.
-A loss of I&C 2A also occurs. Panel 9-9 cabinet 2 does not transfer.
-Reactor Water Level is currently at 22".
-The causing event for the group isolations is-quickly corrected, however I&C
-cannot be restored.
Which ONE of the following lists the systems that can be utilized immediately to restore
reactor water level?
A. RClC and CRD only.
B.' HPCl , RClC and CRD.
C. Core Spray, HPCI, and RCIC.
D. Reactor Feed Pumps, RClC and CRD.
References: 2-AOI-57-5A, Rev. 37 pg 2 and 3
Bank question - Revised answers slightly and reworded last portion of
stem.
A. Incorrect since HPCl is also available for injection since the Group 4 isolation is able
to be reset even with a loss of I&C A.
B. Correct answer.
C. Incorrect since Core Spray cannot be used with reactor at normal operating
pressure.
D. Incorrect since Reactor Feedwater Pumps are not available due to Group 1 isolation
not being able to be reset until I&C A is restored.
ROTier:
T2G2
SRO Tier:
T2G1
Keyword
AC DISTRIBUTION
Cog Level: CIA 3.613.9
Source:
B
Exam:
BF02301
Test:
C
Mix:
TCK
Tuesday, Janualy 21,2003 08:41:37 AM
30
QUESTIONS REPORT
for Browns Ferry Questions
29. 262002K6.02 001
Unit 2 UPS Distribution Bus Battery Board 2 Panel 11 has just de-energized.
Which ONE of the following-describes the effect this has on the equipment that is
supplied by Panel 9-9 Cabinet 6?
A. The equipment is de-energized until power to Panel 9-9 Cabinet 6 is manually
transferred to Batt Bd 3 Panel 11.
B. The equipment is de-energized until power is restored to Batt Bd 2 Panel 11.
Cy The equipment remains energized due to power supply to Panel 9-9 Cabinet 6 auto
transfers to Batt Bd 3 Panel 11.
D. The equipment remains energized due to MMG power supply automatically
transferring to its 250VDC supply.
References: OPL171 .I02 Rev.4 pg 14 and 15
Enabling Objective OPL171.102 #2a and 2b
A. Incorrect since the equipment remains energized due to auto transfer.
B. Incorrect since the equipment remains energized due to auto transfer.
C. Correct answer.
d. Incorrect since the MMG set power supply does not affect the power to Panel 9-9.
ROTier:
T2G2
Keyword
480V DISTRIBUTION
Source:
N
Test:
C
SRO Tier:
T2G2
Cog Level: MEM 2.813.1
Exam:
BF02301
Mix:
TCK
Tuesday, January 21,2003
08:41:37 AM
31
QUESTIONS REPORT
for Browns Ferry Questions
30. 263000K1.04 001
The Unit 2 Unit Operator receives alarm BATBD 2 BKR TR/POUT/FUSE BLOWN OR
GROUND.
Which ONE of the following describes where the Field Operator would be sent to check
for a ground?
A. Battery Board Room No. 2,250V Charger 2A panel.
B. 250V DC Distribution Panel SBA.
CY Battery Board Room No. 2, Panel 1.
D. 4KV Shutdown Bd 250V DC Distribution Panel SD9EB.
References: 2-ARP-9-8C Page 8 Tile #7
0-01-57D Rev.62 Pg 42,46 and 47.
C. Correct answer.
A, B and D. Plausible distractors.
ROTier:
T2G2
SRO Tier:
T2G2
Keyword
GROUND DETECTION
Cog Level MEM 2.6/2.9
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:37 AM
32
QUESTIONS REPORT
for Browns Ferry Questions
31. 264000A1.03 001
Diesel Generator 3A is synchronized to 4KV Shut Down Board 3A. The
instrumentation readings for the diesel generator are as follows:
~
.
~
~~~~~
~~~~
~~~~
.
~
.~
~
~
voltage: 41 60 VAC
frequency = 59.8
vars = 1600 Kvars
watts = 2585 KW
oil temp = 145°F
.~
~
. .
. . , ,
..
. .
current = 340 amps
. .>.
I.
... . .
-
~
.
.
.~
Which ONE of the following actions are required if the diesel is expected to be
operated for an extended period?
A. The operator must take the voltage regulator control switch to raise to avoid
excessive stator currents.
B. The operator must take the voltage regulator control switch to lower to avoid
excessive stator currents.
C. The operator must take the governor control switch to lower to avoid excessive field
current.
DY The operator must take the governor control switch to raise to avoid excessive field
current.
References: 01-82
OPL171.038 Rev. 9, page 31
ROTier:
T2G1
SRO Tier: '1'2G1
Keyword
DIESEL GENERATOR
Cog Level: CIA2.8I2.9
Source:
B
Exam:
BF02301
Test:
C
Misc:
Tuesday, January 21,2003 08:42:37 AM
33
QUESTIONS REPORT
for Browns Ferry Questions
32. 268000A4.01001
Given the following information along with 2-SR-2, lnsfrumenf Checks and Observation
Rev.29 pg 20:
Unit 2 has been at 100% RTP for 3 weeks.
Current 2-FQ-77-6 Reading at 0800
Previous Days 2-FQ-77-6 Reading at 0800
Previous Days Leakrate
-
.34 gpm
Which ONE of the following describes the status of the LEAKAGE limits?
A. No limits are being exceeded.
B.* Increase in unidentified LEAKAGE limit is being exceeded.
63624.3
63125.4
C. Unidentified LEAKAGE limit is being exceeded.
D. Increase in unidentifed LEAKAGE and unidentified LEAKAGE limit are both being
exceeded.
References: 2-SR-2 Rev.29 pg 20
A. Incorrect since increase in LEAKAGE limit is being exceeded at 3.12 gpm. Limit is
- 2 gpm. If use decimal point when subtracting readings then this would be the answer
that the student would get. Procedure says to ignore decimal point.
B. Correct answer. Increase in LEAKAGE is at 3.12 gpm and limit is 5 2 gpm.
C. Incorrect since the increase in LEAKAGE is the only limit not met.
D. Incorrect since the increase in LEAKAGE is the only limit not met.
ROTier:
T2G3
SRO Tier:
T2G3
Keyword
LEAKAGE LIMITS
Cog Level: CIA 3.413.6
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21.2003 08:41:37 AM
34
QUESTIONS REPORT
for Browns Ferry Questions
33. 271000K3.02 001
Which ONE of the following describes the effect on Offsite Release Rates and the
reason why if the Off-Gas System Glycol pumps fail?
A.' Offsite Release Rates will INCREASE due to the Charcoal Adsorbers becor
less efficient.
B. Offsite Release Rates will DECREASE due to better H202 Recombination.
C. Offsite Release Rates will INCREASE due to the Off-Gas Condenser becon
efficient.
'C
lg .2ss
D. Offsite Release Rates will DECREASE due to the Charcoal Adsorbers becoming
more efficient.
References: OPL171.030 Rev. 13 Pg 29 and 31
A. Correct answer. The glycol cools the Cooler Condenser which is used to remove
moisture from the gases entering the Charcoal Adsorbers. Water is a poison to the
adsorbers so if the gases contain more moisture then the adsorbers are less efficient.
B. Incorrect since the glycol system has no affect on the Recombiners.
C. Incorrect since the Condensate System supplies cooling to the Off-Gas condenser.
D. Incorrect since the Charcoal Adsorbers become less efficient.
ROTier:
T2G2
Keyword
OFF-GAS SYSTEM
Source:
N
Test:
C
SRO Tier:
T2G2
Cog Level: CIA 3.313.9
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:37 AM
35
QUESTIONS REPORT
for Browns Ferry Questions
3 4 . 2 8
The following conditions currently exist on Unit 2:
- A fire at one station service transformer has actuated the water spray system.
- Fire header pressure has been 11 5 psig for 35 seconds after the spray system
actuated.
-All system controls are in a normal lineup.
.
Based on these conditions, the diesel fire pump ....
A. and all three electric fire pumps are operating.
B. and two of the three electric fire pumps are operating.
CY is in standby and all three electric fire pumps are operating.
D. and two electric fire pumps are in standby; the selected electric fire pump is
operating.
References: OPL171.049 Rev. 12 pg 43
Enabling Objective (HLT) 5
0-01-26 Rev. 55 pg 10
A. Incorrect since the diesel fire pump doesn't start until 45 seconds after pressure is
below 120#.
B. Incorrect since the diesel fire pump doesn't start until 45 seconds after pressure is
below 120#.
C. Correct answer.
D. Incorrect since all of the electric fire pumps should be running.
ROTier:
T2G2
SRO Tier:
T2G2
Keyword
FIRE PROTECTION
Cog Level: CIA 3.413.4
Source:
M
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:37 AM
36
QUESTIONS REPORT
for Browns Ferry Questions
35. 290001A3.01001
Which ONE of the following conditions will cause the Reactor Bldg ventilation fans to
trip and isolate?
A. Reactor water level reaches +I4 inches on a scram.
~~
~
B. Drywell pressure reaches 2.3 psig before the Drywell can be vented.
Cy Reactor Bldg static pressure reaches +.6 inches of water due to high winds.
D. Reactor Zone exhaust duct radiation level reaches 62 mWhr due to a steam leak.
~
~
~
References: OPL171.016 Rev.12 pg 62 and 63
A. Incorrect since the isolation setpoint for RWL is +I
1.2".
B. Incorrect since the isolation setpoint for Drywell High pressure is +2.45 psig.
C. Correct answer.
D. Incorrect since the isolation setpoint for exhaust duct hi rads is 72 mWhr.
ROTier:
T2G2
SRO Tier:
T2G1
Keyword
SECONDARY CONTAINMEN
Cog Level: MEM 3.914.0
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, Janualy 21,2003 08:41:37 AM
37
QUESTIONS REPORT
for Browns Ferry Questions
36. 290002K4.03 001
Which ONE of the following describes the design and purpose of the orificing in the
lower section of the reactor core?
A. All orifices are the same size to ensure all bundles have the same flow.
B. The interior bundles have more orifices to ensure equalized core flow at high power
levels.
C. Center portions of the core have smaller orifices to ensure the neutron
thermalization is equalized across the core.
D. The outer portions of the core have smaller orifices to ensure adequate cooling in
the interior fuel bundles at high power levels.
References: OPLl71.002 Rev5 pg 24-26
Enabling Objective OPL171.002 #2
A. Incorrect since all orifices are not the same size.
B. Incorrect since more orifices are not provided but larger orifices are provided.
C. Incorrect since center orifices are larger than outer orifices.
D. Correct answer.
ROTier:
T2G3
Keyword
VESSEL INTERNALS
Source:
B
Test:
C
SRO Tier:
T2G3
Cog Level: MEM 3.2/3.3
Exam:
BF02301
Misc:
TCK
Tuesday, Janualy 21,2003 08:41:38 AM
38
QUESTIONS REPORT
for Browns Ferry Questions
37. 295002AA1.05 001
The following plant conditions exist on Unit 2:
- Reactor mode switch:
STARTUPlHOT STANDBY
- Main turbine:
Shell warming
- Feedwater lineup:
RFP A maintaining level in single element
7
Which ONE of the following statements describes the expected sequence of actions as
a condensate system leak causes condenser vacuum to decrease from 24 inches Hg
Vacuum to atmospheric pressure?
A. The RFP turbine trips, then later, the turbine bypass valves close, followed by a
reactor scram on low condenser vacuum.
B. The RFP turbine trips and the main turbine bypass valves close at the same time,
then later, the Main Turbine trips.
C! The Main Turbine trips, then later, the RFP turbine trips and the main turbine
bypass valves close at the same time.
D. The Main Turbine trips and the reactor scrams in response to the turbine trip, then
later, the RFP turbine trips and Main Turbine bypass valves close at the same time.
JUSTIFICATION
a.
b.
C.
Correct answer.
d.
There is no reactor scram on low main condenser vacuum.
A true statement at 7" Hg Vac; however, this is preceded by a main turbine trip at 21" Hg
Vac.
The reactor won't trip on a turbine trip below 30% RTP.
ROTier:
T1G2
Keyword
Source:
B
Test:
C
SROTier:
T1G2
Cog Level: CIA 3.213.2
Exam:
BF02301
Misc:
Tuesday, January 21,2003 08:41:38 AM
39
QUESTIONS REPORT
for Browns Ferry Questions
38. 295003AK1.02 001
Unit 2 is at 100% power and has a special test in progress with the C DIG tied to 4KV
SD Bd C as the sole source. The following occurs:
MSlVs go closed due to high steam tunnel temperature.
All rods do not insert.
Reactor pressure is 800 psig.
Reactor power is 2.5%.
Reactor level is -45".
If reactor water level decreased to -122 inches, which ONE of the following describes
the effect this would have on the RBCCW system?
A:
Both pumps trip, 2A will auto restart in 40 seconds.
B. RBCCW pump 2B will trip, pump 2A not effected.
C. Both pumps trip and auto restart in 40 seconds.
D. No effect on the system,
References: OPL171.072 Rev. 8 pg 7 & 15
Enabling Objective OPL171.072 #4
Bank Question - Comment: 480V load shed will occur due to C diesel,
only 2A pump auto restarts.
A. Correct answer since the D/G is the sole power supply to the Shutdown Board and
water level reaches 122".
B. Incorrect since both pumps trip and the 2A restarts after 40 seconds.
C. Incorrect since the 2B pump restarts automatically only if the 2A pump fails to start.
D. Incorrect since the RBCCW pumps trip due to D/G tied to the Shutdown Board and
water level reaches -122".
ROTier:
T1G2
SROTier:
TlGl
Keyword
LOAD SHED
Cog Level: CIA 3.113.2
Source:
B
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:38 AM
40
QUESTIONS REPORT
for Browns Ferry Questions
39. 295004AA1.03 001
Unit 2 was operating at 100% power when a reactor scram occurrs. The following
plant conditions exist:
Main turbine is tripped.
Main generator PCBs are closed.
Position indication for DC powered RClC valves is out.
CORE SPRAY SYS I LOGIC POWER FAILURE annunciator is lit.
Which ONE of the following is the likely cause of this event?
A. Loss of 250 VDC RMOV Bd "A.
BY Loss of 250 VDC RMOV Bd "B".
C. Loss of 250 VDC RMOV Bd "c".
D. Loss of 250 VDC Turb Bldg Dist. Bd 2.
References: 2-ARP-9-8C #I
1
0-01-57D Rev.
This is a bank question. B is the correct answer. Not verified yet.
ROTier:
T1G2
SRO Tier:
T1G2
Keyword
250 VDC
Cog Level: MEM 3.2V3.5
Source:
B
Exam:
BF02301
Test:
C
Mix:
Tuesday, January 21,2003 08:41:38 AM
41
QUESTIONS REPORT
for Browns Ferry Questions
40. 295007AK1.01 001
Unit 2 has scrammed with the following conditions present:
All rods inserted.
Reactor pressure
475 psig
Reactor water level
+53"
Shutdown Board " A de-energized
MSIV's open
Which ONE of the following lists the systems able to inject at this time?
B. Reactor Feedwater Pumps, 1 B CRD Pump, SLC.
CY SLC, Reactor Feedwater Pumps, 2A CRD Pump.
D. Core Spray, RHR, HPCI.
References: OPL171.026 Rev.11 pg 25
OPLl71.040 Rev.18 pg 27
OPL171.042 Rev.16 pg 41
OPL171.044 Rev.10 pg 26
OPL171.045 Rev.11 pg 15
A. Incorrect since HPCl and RCIC are isolated due to reactor high water level.
B. Incorrect since 1B CRD Pp does not have power.
C. Correct answer,
D. Incorrect since Core Spray and RHR injection permissive is 450# and HPCl is
isolated due to high reactor water level.
ROTier:
TlGl
SROTier:
TlGl
Keyword
REACTOR LEVEL
Cog Level: CIA 2.913.2
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:38 AM
42
QUESTIONS REPORT
for Browns Ferry Questions
41. 295008AK1.02 001
The Unit 3 reactor has received a spurious scram signal. During recovery actions the
crew identifies that reactor water level is + I 17 inches. Reactor pressure is stable at
780 psig.
Based on this condition, which ONE of the following actions should the operators
immediately perform?
-
A. Reduce reactor water level using RWCU.
B. Trip any operating CRD pump.
D: Close the MSIVs.
I
References: 3-01-1 Rev. 0017 pg 6
Added reactor pressure in the stem for clarification.
A. Incorrect since this does not need to be performed immediately. Throttle
condensate or trip RFPs as necessary to control RWL.
B. Incorrect since CRD mechanisms still need to be cooled. Procedures direct to
secure feedwater along with other injection systems.
C. Incorrect since these systems should have isolated on Hi water level.
D. Correct answer since the water level is above the main steam lines and reactor
pressure is greater than 50 psig.
ROTier:
T1G2
Keyword
Source:
B
Test:
C
SRO Tier:
T1G2
Cog Level: CIA 2.812.8
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:38 AM
43
QUESTIONS REPORT
for Browns Ferry Questions
42. 295009AK2.01001
Unit 2 is making preparations to perform a startup after a maintenance outage.
Reactor vessel level is being maintained at +33" with Shutdown Cooling still in service.
Both Recirc Pumps are on at minimum speed.
Which ONE of the following is the most accurate level indicator under these
conditions?
A. LI 3-53 (0 to +60) on the 9-5 panel.
B. LI 3-58A (-155 to +60) on the 9-5 panel.
C.' LI 3-55 (0 to +400) on the 9-3 panel.
D. LI 3-52 (-268 to +32) on the 9-3 panel.
References: OPL171.003 Rev. 15 pg 19-21
A. Incorrect since instrument is calibrated at normal operating temperatures and
pressures.
8. Incorrect since instrument is calibrated at normal operating temperatures and
pressures.
C. Correct answer since the instrument is calibrated under cold conditions.
D. Incorrect since level band does not reach +33 inches.
ROTier:
TlGl
SRO Tier:
TlGl
Keyword
LEVEL INSTRUMENTS
Cog Level: CIA 3.914.0
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, Janualy 21,2003 08:41:39 AM
44
QUESTIONS REPORT
for Browns Ferry Questions
43. 295010AA1.01 001
Which ONE of the following conditions would prevent the Drywell Air Cooler fans from
operating?
A. Drywell pressure at 2.25 psig with reactor pressure at 435 psig.
B. Reactor water level at -1 10" with reactor pressure at 425 psig.
C. Reactor water level at +I"
with reactor pressure at 475 psig.
D.' Drywell pressure at 2.55 psig with reactor pressure at 440 psig.
References: OPL171.016 Rev.12 pg 70
OPLl71.045 Rev.11 pg 12
A. Incorrect since Drywell pressure is below 2.45 psig.
B. Incorrect since Reactor water level is greater than -122".
C. Incorrect since Reactor water level is greater than -122" and pressure is greater than
450 psig.
D. Correct answer since Drywell pressure is greater than 2.45 psig and Reactor
pressure is less than 450 psig.
ROTier:
TlGl
SROTier:
TlGl
Keyword:
DRYWELL COOLING
Cog Level: MEM 3N4.0
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:39 AM
45
QUESTIONS REPORT
for Browns Ferry Questions
44. 295012AK2.01 001
The Unit 2 Reactor Operator notices that the Drywell Temperature is increasing slowly
as reactor power is increased. He verifies the normal Drywell Cooling Units are in
operation on Panel 2-9-25.
Which ONE of the following indicates the normal lineup of the Drywell Cooler Fans and
the Drywell temperature that should be maintained?
A. 3 of 5 cooling units in each train should be operating and attempting to maintain
B: 4 of 5 cooling units in each train should be operating and attempting to maintain
Drywell temperature less than or equal to 150°F.
Drywell temperature less than or equal to 135°F.
C. All the Drywell cooling units should be in operation and attempting to maintain
Drywell temperature less than or equal to 135°F.
D. 4 of 5 cooling units in each train should be operating and attempting to maintain
Drywell temperature less than or equal to 150°F.
References: 2-01-64 Rev.74 pg 13
A. Incorrect since 4 of 5 coolers should be operating in each train trying to maintain
temp less than 135°F.
B. Correct answer.
C. Incorrect since 4 of 5 coolers should be operating in each train trying to maintain
temp less than 135°F.
D. Incorrect since the coolers should be trying to maintain temp less than 135°F.
ROTier:
T1G2
SRO Tier:
T1G2
Keyword
DRYWELL COOLING
Cog Level: MEM 3.413.5
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, Janualy 21,2003 08:41:40 AM
46
QUESTIONS REPORT
for Browns Ferry Questions
45. 295013AK3.02 001
Which ONE of the following describes why the reactor must be shutdown immediately i
the Suppression Pool temperature reaches >I
1 O"F?
A. To ensure that the design pressure of 56 psig is not reached during a Design Basis
Accident.
-
B:' To ensure that the pool is not heated beyond design limits by the steam generated
if the reactor is not shutdown.
C. To maintain HPCl and RCIC OPERABLE since they exhaust into the suppression
pool.
D. This ensures that the non-condensibles will remain in the suppression pool air
space following a Design Basis Accident.
References: Tech Spec Bases 3.6.2.1, Suppression Pool Average Temperature
pg B 3.6-57.
A. Incorrect since the design pressure that is being protected is 62 psig.
B. Correct answer.
C. Incorrect since pool temperature does not affect the operation of HPCl and RCIC.
D. Incorrect since the temperature limit also ensures that complete steam condensation
occurs.
ROTier:
TIG2
SROTier:
TlGl
Keyword
SUPPRESSION CHAMBER
Cog Level: MEM 3.613.8
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, Janualy 21,2003 08:41:40 AM
47
QUESTIONS REPORT
for Browns Ferry Questions
46. 295014AA1.03 001
A startup is in progress with the RWM bypassed. A shift turnover has just been
completed when the on coming peer check notices that two rods in RWM Group 6
(16-48) are at position 16 and the operator is pulling rods in Group 16.
Which ONE of the following describes the proper action to take?
~
A. Insert a manual scram.
B. Verify no indications of fuel damage and continue withdrawal of rods.
C.' Stop rod withdrawal and notify the Shift Manager, Shift Technical Advisor,
-
.- ___
Operations Superintendent, and Reactor Engineer.
D. With the concurrence of the Reactor Engineer and Shift Manager withdraw the
control rods to their required position and continue the startup.
References: 2-AOl-85-7, Section 4.2.1-4.2.3, rev. 14
A. Incorrect since this is not a required action.
6. Incorrect since must recover mispositioned control rods prior to normal rod
withdrawal.
C. Correct answer. Operator must determine that control rod is mispositioned
otherwise he doesn't notify the Operations Superintendent.
D. Incorrect since must notify other individuals prior to withdrawing mispositioned
control rods to their correct position.
Note: Reworded stem slightly and reordered answers.
ROTier:
TlGl
SROTier:
TlGl
Keyword:
REACTIVITY ADDITION
Cog Level: MEM 3.513.5
Source:
B
Exam:
BF02301
Test:
C
Mix:
TCK
Tuesday, January 21,2003 08:41:40 AM
48
QUESTIONS REPORT
for Browns Ferry Questions
47. 295015AK2.09 001
Unit 3 has received a Scram signal and all of the control rods fully inserted except one
rod is still at position 48.
.
~ ~ ~ . . . ~
~~ ~
.
~
~
-
~~.~
_.
~
~
~~
~~~~
~~
~
A. Verifying the "ONE ROD PERMISSIVE light is lit with the Mode Switch in
Shutdown.
B.' Verifying the "ONE ROD PERMISSIVE" light is out with the Mode Switch in Refuel.
C. Pausing in START/HOT STBY for 5 seconds when moving the Mode Switch to
Refuel.
D. Move the Mode Switch to Shutdown and back to Refuel to look for the "ONE ROD
PERMISSIVE" light to be lit.
References: 3-AOI-100-1 Rev.29 pg 2
A. Incorrect since the ONE ROD PERMISSIVE light should only light with all rods in
and the Mode Switch in Refuel.
B. Correct answer.
C. Incorrect since this action is taken if the scram is due to a loss of RPS.
D. Incorrect since there is no direction to move the Mode Switch back to Refuel once it
is in Shutdown.
ROTier:
TlGl
Keyword
REACTOR SCRAM
Source:
N
Test:
C
SRO Tier:
TlGl
Cog Level MEM 3.5/3.6
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003
0841 :40 AM
49
QUESTIONS REPORT
for Browns Ferry Questions
48. 295016AA1.08 002
The control room has been abandoned.
All MSRV transfer switches at panel 25-32 have been placed in EMERGENCY.
All MSRV control switches at panel 25-32 have been checked in CLOSE.
Which ONE of the following statements below describes the operation of these
MS RVs?
A. The associated ADS valves will open upon receipt of an ADS initiation signal.
B. Any associated ADS valve will open only when its control switch is placed in OPEN.
CY The associated ADS valves will open if their respective pressure relief setpoints are
exceeded.
D. The associated ADS valves will open if their respective control switches on panel
9-3 are placed in OPEN.
References: OPLl71.009 Rev.8 pg 22
Enabling Objective OPLl71.009 #3
A. Incorrect since automatic operation of ADS is prevented with transfer switches in
EMERGENCY.
B. Incorrect since valves will open when the pressure setpoint is reached.
C. Correct answer.
D. Incorrect since function from the 9-3 Panel is prevented with transfer switches in
EMERGENCY.
ROTier:
T1G2
SROTier:
TlGl
Keyword
Cog Level: MEM 4.014.0
Source:
B
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, Janualy 22,2003 08:41:40 AM
50
QUESTIONS REPORT
for Browns Ferry Questions
49. 295018AK3.03 001
Unit 2 is operating at 100% RTP. Alarm "RECIRC PUMP A COOLING WATER FLOW
LOW is received at 8:07 am on 10/22/02. It is confirmed that RBCCW Seal Cooling is
lost to the 2A Recirc Pump but CRD seal purge is still in operation.
Which ONE of the following describes the actions that should be taken and the reason
for that action?
A!
Monitor seal temperatures and no further action is required; the Recirc Pump can
~
-
be operated indefinitely under these conditions.
B. Restore RBCCW seal cooling by 8:14 am or Trip the 2A Recirc Pump; Recirc seal
temperatures will exceed 200°F after 7 minutes.
C. Trip the 2A Recirc Pump immediately; Recirc seal temperatures will exceed 200°F
in a short period of time.
D. Reduce 2A Recirc Pump speed to minimum by 8:14 am; the Recirc Pump can be
operated indefinitely at minimum speed under these conditions.
References: 2-01-68 Rev 91 pg 11
2-ARP-9-4A Rev. 18 pg 37
A. Correct answer.
B. Incorrect since the 7 minute time frame is when both CRD and RBCCW are lost to
the Recirc Pump seals.
C. Incorrect since the Recirc Pump only needs to be tripped if seal cavity temperatures
exceed 200°F.
D. Incorrect since the speed of the Recirc Pump doesn't need to be reduced.
ROTier:
TlGZ
SROTier:
TlGZ
Keyword
RECIRC SYSTEM
Cog Level: CIA 3.113.3
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 0841:40 AM
51
QUESTIONS REPORT
for Browns Ferry Questions
50. 295020AA1.03 001
Unit 2 is holding load at 24% RTP after starting up from a refueling outage. Drywell
inerting is in progress per 2-01-76, Containment Inerfing System. A Scram occurs from
Scram Air Header Low Pressure with the following conditions present:
- Oxygen concentration at 7% by volume and decreasing.
- Leak has been isolated.
- Mode Switch is in Shutdown.
- All rods are inserted.
- No entry conditions have been met for the EOl's.
Concerning the Drywell, which ONE of the following describes the status of inerting the
containment?
A. Drywell inerting has been isolated due to a containment isolation when reactor
water level decreased to +O" on the scram.
B. Drywell inerting has been isolated due to the Mode Switch being taken out of Run
on the scram.
C.' Drywell inerting is still in progress since there has not been an isolation signal
processed for this event.
D. Drywell inerting is still in progress but will isolate when the PC PURGE DIV I AND II
RUN MODE BYPASS switches are taken to NORMAL.
References: OPL171.032 Rev.10 pg 14-17
Enabling Objective OPLl71.032 #4
2-01-76 Rev.46 pg 10
A. Incorrect since reactor water level did not reach 0". Stem says no EOl's have been
entered.
B. Incorrect since valves do not close when Mode Switch is taken out of Run.
C. Correct answer.
D. Incorrect since Mode Switch is no longer in Run.
ROTier:
T1G2
SROTier:
T1G2
Keyword
CONTAINMENT
Cog Level: C/A 2.9/3.1
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:40 AM
52
QUESTIONS REPORT
for Browns Ferry Questions
51. 295023AK3.02 001
Interlocks or limit switches on the refueling equipment are provided for specific
protective functions.
Which ONE of the following describes these protection devices?
A. The Refueling Interlocks are not required during fuel handling as long as there is a
.~~
.
~~~
~~
.. ~ ~~-
~
..
~
~.~
~
~
. ~~-
~
~~~~
~
~
~
~
~~~~
~
~~~
~
~~~~
,
second qualified individual performing the functions of the interlocks.
B. Jumpering a refueling interlock should not cause the refuel bridge operator any
concern as long as a TACF tag is clearly visible at the controls.
CY Switches and interlocks act as a backup protection rather than principle means for
stopping travel of the refueling equipment.
D. Fuel handlers may rely on limits and interlocks to terminate refuel equipment travel,
as long as they are within their surveillance frequency.
References: 0-GOI-100-3A Rev. 29 pg 14
A. Incorrect because Tech Specs do not allow for a second qualified individual to take
the place of the refueling interlocks.
B. Incorrect since jumpering interlocks is a concern.
C. Correct answer.
D. Incorrect since the operators should not rely on the interlocks.
ROTier:
T1G3
SRO Tier:
TlGl
Keyword
REFUELING
Cog Level: MEM 3.4/3.8
Source:
B
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:40
53
QUESTIONS REPORT
for Browns Ferry Questions
52. 295024EK1.01 001
Given the following conditions:
~ -- Suppression-Chamberpessure
- 53.0 psig
-
~
-
- Drywell temperature
350°F
- RPV pressure
425 psig
Which ONE of the following is the reason why the Drywell or the Suppression Chambei
is vented under these conditions irrespective of offsite release rates?
A. Pressure capability of the containment will be reached if Suppression Chamber
pressure reaches 55 psig.
BY The maximum containment pressure that the vent valves can be opened and
closed to reject decay heat will be reached at 55 psig.
C. The maximum containment pressure that the MSRV's can be opened and remain
open will be reached at 55 psig.
D. Chugging is prevented if the containment is vented prior to reaching 55 psig.
References: OPLl71.203 Rev. 5 pg 29 and 36
Enabling Objective OPL171.203 #8
A. Incorrect since the pressure capability of the containment is approx. 100 psig.
B. Correct answer.
C. Incorrect since the pressure limit for the MSRV's is 65 psig.
D. Incorrect since chugging depends on the amount of non condensibles in the
containment.
ROTier:
TlGl
SRO Tier:
TlGl
Keyword
CONTAINMENT
Cog Level: MEM 4.U4.2
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, Janualy 21,2003 0841 :41 AM
54
QUESTIONS REPORT
for Browns Ferry Questions
53. 295025EK1.06 001
The Unit 2 Mode Switch is in the S/U position with the Unit at normal operating
pressure and temperature following a short maintenance outage. The RVLIS system is
out-of-service at this time. The Wide Range level instruments (+60 to -155) are
reading approximately +34 at this time.
Which ONE of the following describes the accuracy of the instruments under these
conditions?
A: The instruments are showing accurate level indication due to being calibrated for
normal operating pressure and temperature.
B. The instruments are NOT showing accurate level indication due to being calibrated
for cold shutdown conditions.
C. The instruments are showing accurate level indication because they are within the
level range of the instruments.
D. The instruments are NOT showing accurate level indication because the RVLIS
system is not providing flow to the reference leg fill lines.
Reference: OPLl71.003 Rev. 15 pg 20
A. Correct answer.
B. Incorrect since the instruments are calibrated for hot conditions.
C. Incorrect since being within the indicated range doesnt mean that the instrument is
accurate.
D. Incorrect since RVLIS has no affect on how the instrument reads. It does have an
affect on the indication when a rapid depressurization occurs.
ROTier:
TlGl
SRO Tier:
TlGl
Keyword
LEVEL INSTRUMENTS
Cog Level: CIA 3.914.0
Source:
N
Exam:
BF02301
Test
C
Misc:
TCK
Tuesday, Janualy 21,2003 08:41:41 AM
55
QUESTIONS REPORT
for Browns Ferry Questions
54. 295028EK3.01001
Which ONE of the following describes the reason why Emergency Depressurization is
required if Drywell Temperature cannot be maintained below 280°F?
A. At this temperature all of the RPV level instruments are affected such that there is
no reliable level indication and RPV flooding is required.
6.' Primary Containment has reached the structural design limit and actions are
required to minimize further release of energy from the RPV.
C. Ensures the equipment in the Drywell that is required to reach cold shutdown
conditions remains operable by terminating heat input into the containment.
D. Above 280°F containment failure is emminent which would cause the release rates
at the site boundary to reach 10 CFR 100 limits.
References: OPL171.203 Rev.5 pg 26
A. Incorrect since these conditions do not make all of the level instruments unreliable.
B. Correct answer.
C. Incorrect since the containment is threatened and not the EQ equipment.
D. Incorrect since containment failure is not emminent and it would not cause the 10
CFR limits to be exceeded.
ROTier:
T1G2
Keyword
EO1 INSTRUCTIONS
Source:
N
Test:
C
SROTier:
T1G2
Cog Level: MEM 3.613.9
Exam:
BF02301
Mi%:
TCK
Tuesday, January 21,2003 08:41:41 AM
56
QUESTIONS REPORT
for Browns Ferry Questions
55. 295029EK1.01001
Unit 2 is operating at 100% RTP. The Suppression Pool water level is required to be
maintained at 2 -6.25 inches and 5 1 .O inches per Tech Specs.
Which ONE of the following is available to protect the containment against
overpressurization if Suppression Pool water level is allowed to go above the maximum
level?
I
A. Suppression Chamber-to-Drywell Vacuum Breakers.
B. Reactor Building-to-Suppression Chamber Vacuum Breakers.
C. Drywell Spray system.
D. Residual Heat Removal (RHR) Suppression Pool Cooling System.
~~
. - .-
~
~
~~
.
References: Tech Spec Bases Section B 3.6.2.2 pg B 3.6-66
A. Incorrect since these valves protect the Drywell from negative pressure upon
inadvertent operation of the Drywell Spray system.
B. Incorrect since these valves protect the Suppression Chamber from negative
pressure upon inadvertent operation of the Suppression Pool Spray system.
C. Correct answer.
D. Incorrect since this system is needed to maintain the containment within design
temperature limitations.
ROTier:
T1G2
SRO Tier:
T1G2
Keyword
Cog Level: CIA 3.413.7
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 0841:41 AM
57
QUESTIONS REPORT
for Browns Ferry Questions
56. 295030EA1.02 002
Unit 2 has had an event with the following conditions present:
Reactor Water Level
Reactor Pressure
920 psig
Drywell Pressure
1.3 psig
Suppression Pool Temperature
98°F
RClC Pump Room Temperature
150°F
Operator reports leak on suction header of Torus.
-60" and steady
Suppression Chamber Level
9ft
The Unit 2 Reactor Operator reports that the RClC turbine has tripped.
Which ONE of the following is the most likely cause of the turbine trip?
A. High RClC Pump room temperature
B. High RClC exhaust pressure.
C! Low suction pressure.
D. High Reactor Water Level.
References: OPL171.040 Rev.18 pg 29 and 30
Enabling Objective OPL171.040 #5
A. Incorrect since the High RClC Room Temperature isolation is at 160°F.
B. Incorrect since high exhaust pressure can't happen if Drywell pressure is low.
C. Correct answer based on low Drywell pressure and low torus level.
D. Incorrect since the High Reactor Water Level trip is +51".
ROTier:
TlG2
SRO Tier:
TlGl
Keyword
RCIC SYSTEM
Cog Level: CIA 3.413.5
Source:
N
Exam:
BF02301
Test:
C
Misc:
Tuesday, January 21,2003 08:41:41 AM
58
QUESTIONS REPORT
for Browns Ferry Questions
57. 295030EK2.01001
Unit 3 EOI-2, "Primary Containment Control", has the operators perform the following
action if suppression pool water level CANNOT be maintained above 12.75 feet.
Secure HPCl irrespective of adequate core cooling.
Which ONE of the following HPCl system responses will this action prevent?
A,* Overpressurization of the primary containment.
B. Loss of back pressure on the exhaust line.
C. HPCl exhaust check valve chatter.
D. Unstable HPCl operation.
References: OPL171.203 Rev 5 pg 50 & 51
Enabling Objective OPL171.203 #7
A. Correct answer.
B. Incorrect since the exhaust line will still have the backpressure from the torus
airspace.
C. Incorrect since water level in the torus doesn't affect the HPCl exhaust check valve.
D. Incorrect since torus water level doesn't affect HPCl operation.
Note: Reordered answers.
ROTier:
T1G2
Keyword
Source:
B
Test:
C
SRO Tier:
TlGl
Cog Level: MEM 3.813.9
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:41 AM
59
QUESTIONS REPORT
for Browns Ferry Questions
58. 295031EK3.05 001
A loss of all high pressure injection systems has resulted in RPV level lowering to TAF.
An emergency RPV depressurization has been directed.
Which ONE of the following states the reason that a minimum of 4 MSRVs must be
opened?
A.' Ensures that sufficient steam flow will exist to remove decay heat at low enough
pressure for the lowest head ECCS pump to make up for steam flow.
B. Ensures that at the worst case in core life, the APLHGR thermal limit will not be
exceeded and inhibit adequate radiant heat transfer.
C. Ensures that the reactor will be depressurized to below ECCS shut off head before
the RPV level reaches two thirds core height.
D. Prevents exceeding 1 % plastic strain on the hottest fuel pin in the core allowing fuel
cladding failure to release radioactive fission products.
References: OPL171.205 Rev. 4 pg 29
A. Correct answer.
B,C and D are incorrect since 4 relief valves open do not affect these conditions.
ROTier:
TlGl
SROTier:
TlGl
Keyword
EMERG DEPRESS
Cog Level: MEM 4.2/4.3
Source:
B
Exam:
BF02301
Test:
C
Mix:
Tuesday, Janualy 21,2003 08:41:41 AM
60
QUESTIONS REPORT
for Browns Ferry Questions
59. 295032EK3.03 001
Which ONE of the following is the basis for the Main Steam Line (MSL) Tunnel high
temperature isolation?
A. Protect the integrity of the secondary containment and ensure the continued
operability of safe shutdown equipment.
8. Prevent exceeding the Environmental Qualification temperature limits on the MSlV
control air solenoids.
CY Minimize radioactive releases to the environment and limit the inventory loss from
the reactor under all accident conditions.
D. Limit the escape of radioactivity from the MSL Tunnel to the Reactor Building HVAC
system.
PClS purpose
BSEP BANK LOI-CLS-LP-O12A*017001
ROTier:
T1G3
SRO Tier:
T1G2
Keyword
Cog Level: MEM EK3.03
Source:
B
Exam:
BF02301
Test:
C
Misc:
Tuesday, Januaty 21,2003 08:41:41 AM
61
QUESTIONS REPORT
for Browns Ferry Questions
60. 295033EK2.01002
Unit 2 is in a Refueling outage with work in progress on the Turbine Floor. When the
High Pressure Turbine casing is removed the radiation levels increase significantly.
Which ONE of the following describes the indications available to the Control Room
Operator and the actions required to be taken?
A. Turbine Bldg ventilation trips and isolates. The Control Room Operator announces
evacuation of turbine floor and contacts RADCON.
B. Reactor Bldg ventilation trips and isolates. SGT starts automatically. The Control
Room Operator announces evacuation of the turbine floor and contacts RADCON.
C. Turbine Operating Floor High Radiation Alarm sounds. The Control Room Operator
announces evacuation of the turbine floor, contacts RADCON and monitors other
alarms with inputs to this annunciator.
D. Turbine Operating Floor High Radiation Alarm sounds. The Control Room Operator
notifies Unit Supervisor this is an expected alarm since the turbine casing is being
removed.
References: OPL171.034 Rev.&? pg 16
2-ARP-9-3A Rev.18 pg 31
Enabiling Objective OPL171.034 85
A. Incorrect since Turbine Building vents do not trip.
B. Incorrect since Reactor Building vents do not trip.
C. Correct answer.
0. Incorrect since this is not an expected alarm. The ARP actions should be followed.
ROTier:
T1G2
SROTier:
T1G2
Keyword
RAD MONITORS
Cog Level: C/A 3.W4.0
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:41 AM
62
QUESTIONS REPORT
for Browns Ferry Questions
61. 295034EK1.01001
Which ONE of the following describes why the Reactor Zone and Refueling Floor
Exhaust Radiation - High allowable values are set at their current levels?
A? They provide timely detection of system process barrier leaks inside containment
but they are far enough background levels to avoid spurious isolations.
B. They provide positive indication of system leaks but they are low enough to ensure
proper instrument indications.
C. The values are set to ensure the isolation function is fast enough to prevent
exceeding the 10 CFR 100 exposure limits at the site boundary.
D. The values are set such that trends are able to be determined before the isolations
occur.
References: Tech Spec Section 3.3 Bases pg B 3.3-251
A. Correct answer.
B,C and D. Incorrect per Bases statement.
ROTier:
TlG2
SRO Tier:
T1G2
Keyword
SECONDARY CONTAINMEN
Cog Level: MEM 3.W4.1
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, Janualy 21,2003 08:41:42 AM
63
QUESTIONS REPORT
for Browns Ferry Questions
62. 295036EK2.03 001
A relief valve is leaking on the Unit 2 RBCCW system which is causing the Reactor
Building Equipment Drain Tank to fill up. The Reactor Building Equipment Drain Sump
Pump has started and is pumping to Radwaste.
Which ONE of the following identifies the first indication that Radwaste will see due to
the increased leakage?
A. Chemical Waste Tank level will increase.
B. Floor Drain Collector Tank level will increase.
C! Waste Collector Tank level will increase.
D. Waste Surge Tank level will increase.
References: OPLI 71 .OB4 Rev.3 pg 17
A. Incorrect since the water from the Reactor Bldg Equipment Drain Sump goes to the
Waste Collector Tank first.
B. Incorrect since the water from the Reactor Bldg Equipment Drain Sump goes to the
Waste Collector Tank first.
C. Correct answer.
D. Incorrect since the water from the Reactor Bldg Equipment Drain Sump goes to the
Waste Collector Tank first.
ROTier:
T1G3
SRO Tier:
T1G2
Keyword:
RADWASTE
Cog Level: C/A 2.8/3.1
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:42 AM
64
QUESTIONS REPORT
for Browns Ferry Questions
63. 295037EA1.04 001
The reactor has experienced an ATWS and you have been directed to initiate SLC
injection. SLC Pump A was started at 0700 with the boron concentration at 8.5% and
the tank level at 85%. The following conditions exist at 0730 for SLC Pump A:
- Red Light On
- Squib Continuity Lights Off
- SLC Pressure 1200 psig
- Reactor Pressure 1000 psig
- Tank Level 70%, lowering
- * Flow Light On
Alarm "SLC Injection Flow to Reactor"
Alarm "SLC Squib Valve Continuity Lost"
Which ONE of the following is the appropriate action to take?
A. Start SLC Pump B and continue running SLC Pump A.
6:' Stop SLC Pump A and start SLC Pump B.
c. Initiate Alternate SLC Injection.
D. Continue running SLC Pump A.
References: OPL171.039 Rev. 13 pg 17,26 and 27
2-01-63 Rev. 26 pg 4
Enabling Objective OPL171.039 # 4
A. Incorrect since an interlock is installed to prevent running both pumps at the same
time.
B. Correct answer since tank level should be down to 55% if SLC Pump A was
operating properly.
C. Incorrect since B SLC Pump should be started first.
D. Incorrect since A SLC Pump is pumping at a degraded rate.
ROTier:
TlGl
SROTier:
TlGl
Keyword
Cog Level: CIA 4.514.5
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, January 21,2003 08:41:42 AM
65
QUESTIONS REPORT
for Browns Ferry Questions
64. 295038EK3.01001
An accicent has happened on Unit 2 which causes radiation levels at the site boundary
to reach 11 mRemlHr gamma. An ALERT has been declared by the Shift Manager.
Which ONE of the following describes why the Emergency Plan was implemented for
this condition?
A. Ensures that all individuals are accounted for at the time of the accident.
B. Provides protective measures for TVA employees and contractors located on the
site at the time of the accident.
C. Ensures lines of communication are established between the site and the NRC.
D. Provides protective measures for TVA employees and the public.
References: OPL171.075 Rev.17 pg 9
Enabling Objective OPLl71.075 #B1
A. Incorrect since implementing the Emergency Plan does not ensure all people are
accounted for.
B. Incorrect since it also provides protective measures for the public.
C. Incorrect since implementing the Emergency Plan does not mean that
communication lines are open with the NRC.
D. Correct answer.
ROTier:
T1G2
Keyword
Source:
N
Test:
C
SROTier:
TlGl
Cog Level: MEM 3.614.5
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:42 AM
66
QUESTIONS REPORT
for Browns Ferry Questions
65. 300000K4.03 001
The Raw Cooling Water regulating valve to the "A" Control Air Compressor has failed
closed.
Which ONE of the following conditions would trip the "A" Control Air Compressor?
A,* Air discharge temperature reading 312°F.
B. Air discharge temperature reading 128°F.
C. Lube oil temperature reading 175°F.
I
D. Seal Air Pressure reading 8 psig.
References: OPLI 71.054 Rev.4 pg 13,41 and 45
Learning Objective OPLl71.054 #2
A. Correct answer.
6.
Incorrect but it is correct for the G Compressor.
C. Incorrect since Lube Oil Hi Temp trip is 180°F.
D. Incorrect but it is correct for the G Compressor.
ROTier:
T2G2
Keyword
CONTROL AIR
Source:
N
Test:
C
SRO Tier:
T2G2
Cog Level: MEM 23/23
Exam:
BF02301
Mix:
TCK
Tuesday, Janualy 21,2003 08:41:42 AM
67
QUESTIONS REPORT
for Browns Ferry Questions
66.
500000~~2.07
001
1
An event has occurred on Unit 3 with the following conditions present:
Drywell Pressure
30 psig
Drywell Temperature
275°F
SGT Systems
SGT Inlet pressure
+0.5 psig
CAD System
Shutdown
" A out of service, " 6
and "C" fail to start
The Unit Supervisor has ordered the Drywell to be vented due to high H2
concentrations.
Which ONE of the following describes the reason why the Drywell CANNOT be vented
at this time?
A.' SGT System "6"
and "C" failed to start.
6. SGT Ssytem inlet pressure is too high.
C. Drywell pressure is too high.
D. Drywell temperature is too high.
References: 3-01-83 Rev. 17 pg 5
OPL171.032 Rev.10 pg 21
Enabling Objective OPLl71.032 #B.4
A. Correct answer.
B. Incorrect since the pressure for the SGT inlet is .79 psig.
C. Incorrect since High Drywell pressure prevents nitrogen purge.
D. Incorrect since Drywell Temp does not affect venting the containment.
ROTier:
TlGl
SRO Tier:
TlGl
Keyword
DRYWELL VENTING
Cog Level: CIA 3.213.7
Source:
N
Exam:
BF02301
Test:
C
Mix:
TCK
Tuesday, January 21,2003 08:41:42 AM
68
QUESTIONS REPORT
for Browns Ferry Questions
67. G2.1.28 001
According to SPP-7.2, Outage Management, which ONE of the following defines a
FUNCTIONAL system?
A. A system, structure or component that is in service or can be placed in service in
OPERABLE state by immediate manual or automatic actuation.
B. A system that has the ability to perform its intended function with considerations
that applicable technical specifications or licensing/design basis assumptions ma
not be maintained.
C. A system that had PERs generated during the previous operating cycle that hav
been evaluated as operable but degraded / non-conforming conditions, have not
been justified for resolution in the future and have a specified required completioi
date that is the current outage which has been agreed to by outage managemen
D. A System that is capable of performing its specified safety function(s). Implicit in
this definition shall be the assumption that all necessary attendant instrurnentatio
controls, normal or emergency electrical power sources, cooling or seal water,
lubrication or other auxiliary equipment that are required for the system, subsystc
train, component, or device to perform its specified safety function(s) are also
capable of performing their related support function(s).
Tuesday, Januaiy 21,2003 08:41:42 AM
69
QUESTIONS REPORT
for Browns Ferry Questions
A. AVAILABLE (Availability)- The status of a system, structure or component that is in
service or can be placed in service in a FUNCTIONAL or OPERABLE state by
immediate manual or automatic actuation.
B. FUNCTIONAL -The ability of a system or component to perform its intended
function with considerations that applicable technical specifications or licensingldesign
basis assumptions may not be maintained.
.
C. (SPP 3.1) Operable - Operability - A system, subsystem, train, component, or
device shall be operable or have operability when it is capable of performing its
specified safety function(s). Implicit in this definition shall be the assumption that all
necessary attendant instrumentation, controls, normal or emergency electrical power
sources, cooling or seal water, lubrication or other auxiliary equipment that are required
for the system, subsystem, train, component, or device to perform its specified safety
function(s) are also capable of performing their related support function(s).
D. OPERABLE BUT DEGRADED - PERs generated during the previous operating
cycle that have been evaluated as operable but degraded / non-conforming conditions,
have not been justified for resolution in the future, (i.e., more than one refueling cycle)
in accordance with SPP-3.1, Corrective Action Program, and have a specified
required completion date that is the current outage which has been agreed to by
outage management.
ROTier:
T3
SROTier:
T3
Keyword
SYSTEM STATUS
Cog Level: MEM 3.213.3
Source:
B
Exam:
BF02301
Test:
C
Mix:
Tuesday, January 21,2003 0841:42 AM
70
QUESTIONS REPORT
for Browns Ferry Questions
68. G2.1.3 001
The on-coming Unit 3 Board Unit Operator (BUO) has been on vacation for 7 days.
The BUO is preparing to assume shift at 0700 on 12/30/2002.
Which ONE of the following is the date, at a minimum, that the BUO must review back
to concerning the Unit 3 Narrative Log?
A. 0700 on 12/29/2002.
B. 1500 on 12/27/2002.
C. 0700 on 12/25/2002.
D. 1500 on 12/23/2002.
References: SSP-12.1, Section 3.12.2, page 64
C. Correct answer.
A, B and D are incorrect since the operator must only review the previous 5 days in the
narrative log.
Note: Did not have a copy of the procedure to verify answer.
ROTier:
T3
SROTier:
T3
Keyword
ADMIN
Cog Level: CIA 3.013.4
Source:
M
Exam:
BF02301
Test:
C
Misc:
Tuesday, January 21,2003 08:41:42 AM
71
QUESTIONS REPORT
for Browns Ferry Questions
69. G2.2.12 001
The Unit Operator has just completed the required readings for his shift and
documented them in 2-SR-2, Instrument Checks and Observations.
Which ONE of the following lists the individuals that are qualified to perform an
independent review?
~
A. ROorSRO.
B. ROorSTA.
C. Ops Manager or SRO.
References: 2-SR-2, Rev.29 pg 8
A. Incorrect since RO cannot perform independent review.
B. Incorrect since RO cannot perform independent review.
C. Incorrect since Ops Manager cannot perform independent review unless he is an
D. Correct answer.
ROTier:
T3
SROTier:
T3
Keyword
SURVEILLANCE REQUIRE
Cog Level: MEM 3.0/3.4
Source:
N
Exam:
BF02301
Test:
C
Misc:
TCK
Tuesday, Janualy 21,2003 0841:43 AM
72
QUESTIONS REPORT
for Browns Ferry Questions
70. G2.2.3 001
Assume that one of the 48V DC inverters that supplies 120V AC to the Control Room
annunciators has failed.
Which ONE of the following describes the effects this will have?
A? If the failure is on Unit 1 a buzzer will sound and a white light will illuminate.
B. If the failure is on Unit 1,2 or 3 a buzzer will sound and a red light will illuminate.
C. If the failure is on Unit 2 the power supply will auto swap to Battery Board 2.
D. If the failure is on Unit 3 the power supply will auto swap to Battery Board 3.
References: OPLl71.037 Rev.8 pg 16
Enabling Objective OPL171.037 #B8
Note: Taken from 2001 Exam.
A. Correct answer.
B. Incorrect since a red light will not illuminate on Unit 1 but it will illuminate on Units 2
and 3.
C. Incorrect since the power supply does not swap.
D. Incorrect since the power supply does not swap.
ROTier:
T3
Keyword
DC SYSTEMS
Source:
B
Test:
C
Tuesday, January 21,2003 08:41:43 AM
SROTier:
T3
Cog Level: MEM 3.113.3
Exam:
BF02301
Misc:
TCK
73
QUESTIONS REPORT
for Browns Ferry Questions
71. G2.3.1 001
You are called at home and directed to go to the Hatch Facility to assist in the recovery
efforts following a refueling accident. You are informed that you will require a TLD
during the assist visit.
Which ONE of the following describes the dosimetry requirement for this emergency
visit per SPP-5. I, RADIOLOGICAL CONTROLS?
A. You must obtain your BFN dosimetry and wear it along with the dosimetry provided
by Hatch. Following your return you must report to RADCON to obtain any required
bioassay and update your exposure records.
B. You must inform RADCON of your intended visit and obtain your BFN dosimetry to
wear with the dosimetry provided by Hatch. Upon your return you must present
copies of your dose records from Hatch.
C. You must turn in your dosimetry and check out prior to leaving BFN, unless
exempted by the Shift Manager or Operations Manager.
D. You must turn in your dosimetry and check out prior to leaving BFN, unless
exempted by RADCON.
References: SPP-5.1, Radiological Controls Rev.3 pg 9
A. Incorrect since a bioassay is not required and you must also turn in your BFN
dosimetry.
B. Incorrect since you must turn in your BFN dosimetry.
C. Incorrect since you can only get exemption from RADCON.
D. Correct answer.
ROTier:
T3
Keyword
RADIATION CONTROL
Source:
B
Test:
C
SROTier:
T3
Cog Level: MEM 2.613.0
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 0841 :43 AM
74
QUESTIONS REPORT
for Browns Ferry Questions
Which ONE of the following is NOT an immediate action of 2-AOI-1-1, Relief Valve
Stuck Open?
A:' Inhibit MSRV Auto Actuation Logic on Panel 2-9-3.
72. G2.4.1 001
B. PLACE affected relief valve control switch from CLOSE to OPEN to CLOSE
several times, and OBSERVE indications to see whether valve closes.
C. IDENTIFY stuck open relief valve by OBSERVING SRV TAILPIPE FLOW
MONITOR, 2-FMT-1-4, on Panel 2-9-3.
D. IDENTIFY stuck open relief valve by OBSERVING MSRV DISCHARGE TAILPIPE
TEMPERATURE recorder, 2-TR-1-1 on Panel 2-9-47.
4.1
Immediate actions:
4.1.1 IDENTIFY stuck open relief valve by OBSERVING following:
4.1.1.1
SRV TAILPIPE FLOW MONITOR, 2-FMT-1-4, on Panel 293, or
4.1.1.2
MSRV DISCHARGE TAILPIPE TEMPERATURE recorder, 2TR11
on Panel 2947.
4.1.2 PLACE affected relief valve control switch from CLOSE to OPEN to CLOSE
several times, and OBSERVE indications to see whether valve closes.
4.2
Subsequent Action
4.2.1 IF ANY EO1 entry condition is met, THEN
ENTER the appropriate EOl(s).
ROTier:
T3
SROTier:
T3
Keyword
RELIEF VALVE
Cog Level: CIA4.314.6
Source:
B
Exam:
BF02301
Test:
C
Misc:
Tuesday, Janualy 21,2003 08:41:43
75
QUESTIONS REPORT
for Browns Ferry Questions
73. G2.4.10001
Alarm tile "MSIV ISOL SCRAM BYPASS" on the Unit 2 9-5 Panel is illuminated. No
other alarms are illuminated.
Which ONE of the following identifies which Scram signals are not active?
A. MSlV closure scram and Turbine Stop Valve closure scram.
B. Generator Load Reject Scram and Condenser low vacuum scram.
C." MSlV closure scram and Condenser low vacuum scram.
D. MSlV closure scram and Generator Load Reject Scram.
References: 2-ARP-9-5B Rev.12
A. Incorrect since the Turbine Stop Valve closure scram is still active.
B. Incorrect since the Generator Load Reject scram is still active.
C. Correct answer.
D. Incorrect since the Generator Load Reject scram is still active.
ROTier:
T3
Keyword
Source:
N
Test:
C
SROTier:
T3
Cog Level: MEM 3.0/3.1
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 0841:43 AM
76
QUESTIONS REPORT
for Browns Ferry Questions
74. G2.4.11 001
A diesel fuel oil spill has occurred in the Diesel Generator Building. The On Scene
Coordinator requests that absorbent material be delivered to the scene.
Which ONE of the following contains a list of the locations of stored absorbent
material?
~
A. MSDS for diesel fuel oil.
B. Emergency Plan Implementing Procedure.
CY Spill Prevention Control and Countermeasures Plan.
D. Browns Ferry Master Materials Index Data Base (MMIDB).
Reference: OPL171.068 Rev. 4 pg 10
Enabling Objective #5
C is the only answer that provides a table for location of spill cleanup material therefore
answers A.B and C are incorrect.
Note: Reordered answers.
ROTier:
T3
Keyword:
ADMIN
Source:
B
Test:
C
SROTier:
T3
Cog Level: MEM 3.413.6
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:43 AM
77
QUESTIONS REPORT
for Browns Ferry Questions
75. G2.4.3 001
Per Regulatory Guide 1.97 post accident instrumentation must be appropriately
identified in control rooms to provide information required by the control room operators
during accident conditions.
Which ONE of the following describes how RPV level instruments are designated as
post accident monitoring and which instruments are used?
A. Black labels are placed on the Emergency Systems Range instruments only.
B. Blue labels are placed on the Post Accident Flood Range instruments only.
CY Black labels are placed on both the Emergency Systems Range and Post Accident
Flood range instruments.
D. Blue labels are placed on both the Post Accident Flood Range and the Shutdown
Vessel Flood Range instruments.
References: OPL171.003 Rev.15 pg 24 and 26
Tech Spec Bases B 3.3.3.1 pg B 3.3-84
Note: Modified stem and answers slightly. On last exam.
A. Incorrect since on more than the instruments listed.
B. Incorrect since wrong color and on more than the instruments listed.
C. Correct answer.
D. Incorrect since wrong color and wrong instruments listed.
ROTier:
T3
Keyword
POST ACCIDENT
Source:
B
Test:
C
SROTier:
T3
Cog Level: MEM 3.513.8
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:43 AM
78
QUESTIONS REPORT
for Browns Ferry Questions
76. 259002G2.2.22 001
Unit 2 experienced a Group 1 isolation with a failure to scram. Rx steam dome
pressure increased to 1320 psig which caused a break in the Recirc Suction piping.
The following conditions exist at this time:
Rx Power
8% RTP
Reactor Water Level -
-155 inches
Reactor Pressure
185 psig
Core Flow
5% of rated
Drywell Pressure
13 psig
Which ONE of the following describes the Safety Limit violated and the corrective
action?
A. Reactor steam dome pressure; insert all insertable control rods within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
B. Core Flow vs. Thermal Power; insert all insertable control rods and restore Thermal
Power to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Cy Reactor Vessel Water Level; restore level above -151" and insert all insertable
control rods within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
D. Drywell Pressure; restore to within limits and be in Mode 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
References: Tech Spec Section 2.0, Safety Limits
Tech Spec Bases pg B 2.0-6
A. Incorrect since Reactor steam dome safety limit was not exceeded (limit is 1325
P
m
B. Incorrect since the safety limit is 2 25% RTP and core flow < 10% rated.
C. Correct answer.
D. Incorrect since Drywell Pressure is not a safety limit.
RO Tier:
SRO Tier:
T2G1
Keyword
SAFETY LIMIT
Cog Level: ClA3.414.1
Source:
N
Exam:
BF02301
Test:
s
Misc:
TCK
Tuesday, January 21,2003 08:41:43 AM
79
QUESTIONS REPORT
for Browns Ferry Questions
77. 261000K2.03 001
The SGT "A" master control switch (HS-65-18A on Unit 1) is in the pull-to-lock position.
Which one of the following conditions would still cause the SGT "A" to start even
though the control switch is in the pull-to-lock position?
A. Unit 3 SGT " A start pushbutton is depressed.
B. Unit 2 drywell pressure rises to 2.5 psig and continues to rise.
C.' The local (SGT Building) SGT "A" start pushbutton is depressed.
D. SGT TRAIN "A" INBD ISOL TEST SIG keylock switch (HS-65-48A) is placed in the
TEST position.
RO Tier:
SRO Tier:
T2G1
Keyword
Cog Level: CIA 2.312.5
Source:
B
Exam:
BF02301
Test:
S
Misc:
Tuesday, January 21,2003 08:41:44 AM
80
QUESTIONS REPORT
for Browns Ferry Questions
78. 290003G2.1.12 001
Unit 2 is at 100% power. Two Unit 1 & 2 Control Room Air Conditioning Subsystems
are inoperable. Actions to restore one subsystem to OPERABLE status is in progress.
Which ONE of the following states the actionsllimitations imposed by Tech Specs?
A. Unit 2 must be in MODE 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
B.' Place an alternate method of cooling in service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and restore one
~
subsystem to OPERABLE status within 7 days.
C. Restore one subsystem to OPERABLE status within 30 days.
D. Place an alternate method of cooling in service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and restore one
subsystem to OPERABLE status within 30 days.
References: Tech Spec 3.7.4 Condition B
correct answer since you are in Condition A until you return BOTH systems to
OPERABLE status.
Revised answers from Bank question to prevent having more than one
A. Incorrect since this is the action to take if Condition B completion time cannot be
met.
B. Correct answer.
C. Incorrect since at least ONE subsystem must be restored to OPERABLE status
within 7 days along with other actions.
D. Incorrect since one subsystem must be returned to operable status within 7 days.
RO Tier:
SRO Tier:
T2G2
Keyword
TECH SPECS
Cog Level: ClA2.914.0
Source:
B
Exam:
BF02301
Test:
S
Misc:
TCK
Tuesday, January 21,2003 08:41:44 AM
81
QUESTIONS REPORT
for Browns Ferry Questions
79. 295001AA2.01 001
Unit 3 is in the process of starting up
A 100% rod line has been established
Currently raising recirc flow- - -
A fault in the 3B Recirc MG set occurs causing a trip of the MG set.
The operator notes the following conditions after the pump trip:
- MWE = 560
- MWT = 1745
- Core Flow = 32%
Using the attached Illustration 1 from 3-01-68 determine which ONE of the following
describes the appropriate action to take.
A. Region 2 has been entered, scram the reactor immediately.
B.* Region 1 has been entered, scram the reactor immediately.
c. Region 2 has been entered, and must be exited within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
D. Region 1 has been entered, insert control rods to less than a 95.2% rod line.
Task no: U-068-AB-01
RO Tier:
Keyword
PWR/FLOW MAP
Source:
B
Test:
S
SROTier:
TlG2
Cog Level: C/A 333.8
Exam:
BF02301
Misc:
Tuesday, Janualy 21,2003 08:41:44 AM
82
QUESTIONS REPORT
for Browns Ferry Questions
80. 295003G2.1.12 001
Core Spray Pump 2B has just been tagged for maintenance when 250V DC Reactor
MOV Board 2B trips.
Which ONE of the following describes the Tech Spec required actions for Unit 2?
A.' Enter LCO 3.0.3 immediately.
-
B. Restore the 250V DC Reactor MOV Board 2B
OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Core Spray Pump 2B to
C. Restore Core Spray Pump 2B AND 250V DC Reactor MOV Board 26 to
OPERABLE status within 7 days.
D. 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 be in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
References: Tech Spec 3.5.1
Refer to OPDP-8. The 250V Board is a support system for Core Spray, and there is a
LOSF since the 250V Board is Division I logic. Therefore both Core Spray systems are
inoperable, requiring entering LCO 3.0.3 per 3.5.1 .H. If 250V Rx MOV Board 2B is
placed on its alternate supply the board is still considered inoperable per BASES B
3.8.7.
A. Correct answer since two low pressure ECCS spray subsystems are INOPERABLE.
LCO 3.0.3 is entered per 3.5.1 .G.
B. Incorrect since this assumes that HPCl is also INOPERABLE.
C. Incorrect since the 7 day clock is for 1 low pressure spray subsystem being
D. Incorrect since this action is required only if the required actions or completion time
for Condition A is not met.
RO Tier:
SROTier:
TlGl
Keyword
Cog Level: CIA 2.914.0
Source:
B
Exam:
BF02301
Test:
S
Misc:
TCK
Tuesday, January 21,2003 08:41:44 AM
83
QUESTIONS REPORT
for Browns Ferry Questions
81. 295005AA2.02 001
Unit 3 is at 27% RTP during a startup from a refueling outage. The Control Room
Operator reports that the vibrations for the turbine are at 12 mils and continuing to
increase slowly.
Which ONE of the following describes the actions you should take as Control Room
Supervisor?
A. Order the Control Room Operator to Trip the Tubine immediately and verify a
reactor scram.
6. Order the Control Room Operator to monitor the Turbine vibrations and to Trip the
Turbine if the vibrations continue for greater than 15 minutes.
C. Enter EOI-1 since a scram should have occured due to Turbine Trip from High
vibrations.
D.' Order the Control Room Operator to Trip the Turbine immediately. Verify Generator
trips and loads transfer properly.
References: OPL171.147 Rev. 3 pg 10, 19,22
A. Incorrect since a reactor scram should not occur from the turbine trip due to Rx
power ~30%.
6. Incorrect since the turbine must be tripped immediately if vibrations reach 12 mils.
C. Incorrect since an entry condition does not exist at this time.
D. Correct answer.
RO Tier:
Keyword
TURBINE CONTROLS
Source:
N
Test:
S
SRO Tier:
T1G2
Cog Level: CIA 2.412.7
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:44 AM
84
QUESTIONS REPORT
for Browns Ferry Questions
82. 295006AA2.03 001
Unit 3 is operating at 100% RTP when the unit scrams. The following conditions exist
after the scram:
All rods are in
Reactor Pressure
Reactor Water Level
Drywell Pressure
11 psig
All systems operating as designed.
510 psig lowering slowly
-1 55 steady
Which ONE of the following the systems that are allowed, and are able, to be in
operation to maintain vessel level greater than -1 62?
A!
Feedwater, HPCI, RCIC, CRD and SLC.
B. Feedwater, HPCI, CRD and Core Spray.
C. Feedwater, HPCI, RCIC, and CRD.
D. Feedwater, HPCI, RCIC, CRD, SLC, Core Spray and RHR.
References: EOI-1 Rev 5
A. Correct answer.
B. Incorrect since Core Spray is not able to inject at this pressure.
C. Incorrect since SLC is also able to be used to maintain level >-162.
D. Incorrect since Core Spray and RHR cannot inject at this time.
RO Tier:
SRO Tier:
TlGl
Keyword
LEVEL CONTROL
Cog Level: CIA 4.014.2
Source:
N
Exam:
BF02301
Test:
S
Mix:
TCK
Tuesday, January 21,2003 08:41:44 AM
85
QUESTIONS REPORT
for Browns Ferry Questions
83. 295014AA2.03 001
Unit 3 is at 100% power. Which ONE of the following plant conditions is a symptom of
an inadvertent HPCI injection?
A. APRM flow comparator alarm.
B. Decrease in reactor pressure.
C. Recirc pump runback.
D.' Positive reactor period.
RO Tier:
Keyword
Source:
B
Test:
S
SROTier:
TlGl
Cog Level: CIA 4.014.3
Exam:
BF02301
Misc:
Tuesday, January 21,2003 08:41:44 AM
86
QUESTIONS REPORT
for Browns Ferry Questions
84. 29501662.2.3 001
There has been a Toxic Gas spill on site which has caused Unit 2 and Unit 3 Control
Rooms to be abandoned. AOI-100-2, Control Room Abandonment has been
implemented for both units and RClC is injecting to maintain Reactor Water Level
within a certain band.
Which ONE of the following describes the appropriate level band for each unit?
A. Unit2
Unit 3
B. Unit2
Unit 3
C I Unit 2
Unit 3
D. Unit 2
Unit 3
+2" to +50
+12" to +51"
+ I 2" to +50"
+2" to +51"
+12" to +51"
+2" to +50
+2" to +51"
+I 2" to +50
References: OPLl71-208 Rev.4 pg 22
A,B and D are incorrect since they show the wrong level bands.
C. Correct answer.
RO Tier:
Keyword
CONTROL ROOM
Source:
N
Test:
S
SROTier:
TlGl
Cog Level: MEM 3.113.3
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:44 AM
87
QUESTIONS REPORT
for Browns Ferry Questions
85. 295017AA2.04 001
A release of radioactivity is in progress. The following radiological conditions are
present:
Stack Gas Rad Monitors RM-90-147 & 148
Reactor BldglRefuel Zone Rad Monitors
Turbine Bldg Exhaust Rad Monitor RM 90-250
Drywell Rad Monitors
Torus Rad Monitors
rising radiation levels
reading normal levels
rising radiation levels
rising radiation levels
reading normal levels
Which ONE of the following describes the probable source of the release?
A. Main Steam leakage outside the Primary Containment.
B. Reactor Water Cleanup leakage outside the Primary Containment.
C.' Fuel clad failure release thru the Offgas System.
D. Major airborne activity in the Radwaste Bldg.
References: OPL171.067 Rev.10 pg 19 - 22
A. Incorrect since the steam release is only through Primary Containment. Secondary
Containment is still in tact.
B. Incorrect since the RWCU leak is through Primary Containment.
C. Correct answer. Turbine Bldg Vents take a suction from the Offgas Areas and the
offgas also goes to the main stack. These are the only areas with increased rad levels
other than the Drywell.
D. Incorrect since the Radwaste Bldg Ventilation has its own exhaust stack.
RO Tier:
Keyword
OFF SlTE RELEASE
Source:
M
Test:
S
SRO Tier:
TlGl
Cog Level: CIA 3.614.3
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:44 AM
88
QUESTIONS REPORT
for Browns Ferry Questions
86. 295021~~2.04
001
The following conditions exist on Unit 3:
Reactor Water Level
+46"
Reactor Coolant Temp.
185°F
Reactor Pressure
0 psig
Rx Vessel Head bolted and torqued
RHR loop 1 in shutdown cooling
Both Recirculation Pumps off
.
Which ONE of the following describes the operational consequence of the Inboard
Shutdown Cooling Valve (FCV 74-48) failing closed?
A. Transition boiling will occur at the reduced reactor pressure causing fuel cladding
damage.
B. Damage could occur to the running RHR pump since it no longer has a suction
path.
Cy Coolant temperature may rise unmonitored and change the reactor condition from
MODE 4 to MODE 3.
D. Since the valve is a failed PCiV then the Outboard Shutdown Cooling Valve (FCV
74-47) must be closed and deactivated.
References: 3-AOl-74-1 Rev. 25 pg 1 and 4
Tech Specs 3.6.1.3, Primary Containment Isolation Valves (PCIVs)
A. incorrect since transition boiling may not occur for a long period of time.
B. Incorrect since the RHR pump will trip if it loses its suction path.
C. Correct answer.
D. Incorrect since the outboard isolation valve does not need to be closed. The failed
valve can be used as the isolation valve.
RO Tier:
SRO Tier:
T1G2
Keyword:
Cog Level: CIA 3213.3
Source:
B
Exam:
BF02301
Test:
S
Misc:
TCK
Tuesday, Januaty 21,2003 08:41:45 AM
89
QUESTIONS REPORT
for Browns Ferry Questions
87. 295022G2.1.20 001
Unit 2 is in the process of heating up with the Mode Switch in START/HOT STBY. The
following conditions exist when the 2A CRD Pump trips on overcurrent:
Reactor Pressure
800 psig
Reactor Temperature
485°F
1B CRD Pp
Out-of-Service
-
Which ONE of the following should the Unit Supervisor direct the Reactor Operator to
perform ?
A. If receive 2 or more scram accumulator alarms AND charging water pressure
cannot be restored to 940 psig within 20 minutes THEN Scram the reactor.
B. Monitor CRD temps and attempt to return 1 B CRD Pp to service. Scram the reactoi
if CRD temps exceed 350°F.
C.' Manually Scram the reactor and place the Mode Switch in Shutdown immediately.
D. Attempt to restart the 2A CRD Pump. If fails to start then commence a shutdown.
References: 2-AOl-85-3 Rev.20 pg 3 and 4
A. Incorrect since these actions are taken if Rx pressure is >900 psig.
B. Incorrect since you do not wait to return a CRD Pp to service.
C. Correct answer.
D. Incorrect since you do not perform a normal shutdown and you do not try to restart a
pump on overcurrent.
RO Tier:
SRO Tier:
T1G2
Keyword
CRD SYSTEM
Cog Level: CIA4.314.2
Source:
N
Exam:
BF02301
Test:
S
Misc:
TCK
Tuesday, January 21,2003 0841 :45 AM
90
QUESTIONS REPORT
for Browns Ferry Questions
8 8 . 2 9 5 0 2 5 ~ ~ 2 . 0 3
001
The following conditions exist on Unit 3:
Reactor Scrammed due to stuck open relief valve.
Reactor pressure
700 psig
Suppression Pool level
15 FT
Suppression Pool temperature
200°F
-
Which ONE of the following actions should the Unit Supervisor direct to be performed?
(Refer to 3-EOI-1)
A. Emergency Depressurize the reactor.
B. Lower reactor pressure to 500 psig without exceeding 100°F cooldown rate.
C. Exit pressure control and enter steam cooling.
D? Lower reactor pressure to 500 psig irrespective of cooldown rate.
References: 3-EOI-1 Rev5
A. Incorrect since procedure directs lowering reactor pressure to within curve 3 limits
irrespective of cooldown rates.
B. Incorrect since procedure directs lowering reactor pressure to within curve 3 limits
irrespective of cooldown rates.
C. Incorrect since steam cooling is not required.
D. Correct answer per Curve 3 and overide RCIP-7.
RO Tier:
SRO Tier:
TlGl
Keyword
HEAT CAPACITY
Cog Level: CIA 3.914.1
Source:
N
Exam:
BF02301
Test:
S
Misc:
TCK
Tuesday, January 21,2003 08:41:45 AM
91
QUESTIONS REPORT
for Browns Ferry Questions
89. 29502602.1.12 001
Unit 2 is conducting a plant startup per 2-GOI-100-1A, "Unit Startup and Power
Operation", and surveillance 2-SR-3.5.1.8, "HPCI Main and Booster Pump Set
Developed Head and Flow Rate Test at 150 psig" is in progress. The following
conditions exist:
Suppression Pool water temperature is 98°F and rising.
Both loops of Suppression Pool cooling are in service.
The Unit Supervisor is implementing the actions of EOl-2,"Primary Containment
Control".
In accordance with Unit 2 Technical Specifications, which ONE of the following actions
is required once Suppression Pool temperature exceeds 105"F?
A. Place the Reactor Mode Switch in SHUTDOWN.
BY Suspend all testing that adds heat to the Suppression Pool.
C. Reduce THERMAL POWER to range 7 on IRM's within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D. Depressurize the reactor vessel to less than 200 psig within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
References: Tech Specs 3.6.2.1, Suppression Pool Average Temperature
A. Incorrect since the Mode Switch doesn't need to be placed in Shutdown until
average Suppression Pool temperature exceeds 11 0°F.
B. Correct answer.
C. Incorrect since this is done if cannot meet Required Action and associated
Completion time of Condition A.
D. Incorrect since this is performed if average Suppression Pool temperature exceeds
120°F.
RO Tier:
SRO Tier:
TlGl
Keyword
SUPPRESSION CHAMBER
Cog Level: MEM 2.813.1
Source:
B
Exam:
BF02301
Test:
S
Misc:
Tuesday, January 21,2003 08:41:45 AM
92
QUESTIONS REPORT
for Browns Ferry Questions
90. 295031EA2.04 001
The following conditions exist on Unit 2 after a scram from 100% power:
Reactor Power
6%
INJECTING
Reactor Water level
UNKNOWN
Suppression pool temp
Suppression Pool Pressure 3.0 psig
Drywell Pressure
3.0 psig
Six ADS valves
OPEN
RPV injection
105 degrees F
Stopped and Prevented per Appx. 4
Which ONE of the following indicates the reactor pressure at which injection to thw
vessel should be reestablished?
(Supply copy of EOI-1 and C-4)
A. When reactor pressure is below 65 psig.
B. When reactor pressure is below 68 psig.
C.' When reactor pressure is below 180 psig.
D. When reactor pressure is below 220 psig.
References: 2-EOI-1 Rev. 8
C-4 Rev. 6
A. Incorrect since this is the pressure that needs to be above Suppression Chamber if
the reactor will stay shutdown under all conditions.
B. Incorrect since this pressure added to Suppression Chamber pressure is the
pressure required to be maintained if the reactor will stay shutdown under all
conditions.
C. Correct answer with 6 or more MSRV's open.
D. Incorrect since this is the pressure with only 5 MSRV's open.
RO Tier:
SRO Tier:
TlGl
Keyword
RPV FLOODING
Cog Level: CIA 4.6143
Source:
B
Exam:
BF02301
Test:
S
Misc:
TCK
Tuesday, Janualy 21,2003 08:41:45 AM
93
QUESTIONS REPORT
for Browns Ferry Questions
91. 29503862.3.4 001
Unit 2 has experienced a severe accident.
Which ONE of the following conditions would require EMERGENCY
DEPRESSURIZATION per EO/-4, Radioactivity Release Control?
A. Release rates above an ALERT due to fuel failure and a leak from the suppression
pool.
B. Release rates exceeding an Unusual Event classification and an unisolable leak on
the HPCl steam line.
C I Release rates approaching a General Emergency and leakage past the MSlVs to a
steam leak in the turbine building.
D. Release rates exceeding a General Emergency but no indications of a primary
system discharging outside of containment.
References: EOI-4, Radioactive Release Control, Rev5
A. Incorrect since lowering reactor pressure would not slow down the leak.
B. Incorrect since release rate is below the alert level and not approaching the General
Emergency level.
C. Correct answer.
D. Incorrect since nothing is being discharged outside of primary or secondary
containment.
RO Tier:
Keyword
RADIATION CONTROL
Source:
B
Test:
S
SRO Tier:
TlGl
Cog Level: MEM 2.513.1
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:45 AM
94
QUESTIONS REPORT
for Browns Ferry Questions
92. 600000G2.4.27 001
A fire rated door listed in Table 9.3.1 1 .E of the BFNP FIRE PROTECTION PLAN is
about to be propped open while work is in progress on one side of the door. There is
no fire detection equipment available to protect either side of the fire door. The door is
located in a contamination zone.
Which ONE of the following is the MINIMUM action that must be taken to compensate
for having the fire door propped open?
A. Establish a roving hourly fire watch to monitor the both areas until the door is
restored to an operable status.
B. If hot work is to be performed in either of the adjacent rooms, establish a
continuous fire watch on either side of the open door.
C. No compensatory actions are required as long as the fire door is verified to be
closed at least one time daily.
D I Establish a continuous/dedicated fire watch to monitor the impaired fire door area
until the door is restored to an operable status.
References: Fire Protection Plan Vol.1 Rev.17 pg 25
Modified so that the examinee must determine that the door is inoperable.
A. Incorrect since a continuous/dedicated fire watch is required until the door is
restored to operable status.
B. Incorrect since a continuousldedicated fire watch is required until the door is
restored to operable status.
C. Incorrect since the fire door is inoperable and compensatory actions are required.
D. Correct answer
RO Tier:
Keyword:
FIRE PROTECTION
Source:
M
Test:
S
SROTier:
TlG2
Cog Level: C/A 3.0/3.5
Exam:
BF02301
Mix:
TCK
Tuesday, January 21,2003 0841 :45 AM
95
QUESTIONS REPORT
for Browns Ferry Questions
93. G2 1.10001
You are in the position of SM. There are several NRC personnel in the control area
conducting initial reactor operator examinations. You feel these activities are interfering
with daily plant activities, you are concerned with the number of people in the control
room. According to SSP10.0, Plant Operations, which ONE of the following actions
should be taken?
A. Ask the NRC personnel to leave the control room.
B. Contact the NRC Senior Resident Inspector for resolution.
C:' Contact the Plant Manager for resolution.
D. Nothing. NRC personnel shall be allowed to enter or be present in the control room
for any activity.
SSP10.0, Plant Operations:
3.6
Control Room Activities
The SM, US and the UO have the authority to restrict access to or remove personnel
from the control room. NRC personnel shall be allowed to enter or be present in the
control room. If the SM has concern over the number or activities of NRC personnel,
he shall contact the Plant Manager for resolution.
RO Tier:
SROTier:
T3
Keyword
COMMAND AND CONTROL
Cog Level: MEM 2.713.9
Source:
B
Exam:
BF02301
Test:
S
Mix:
Tuesday, Janualy 21,2003 08:41:45 AM
96
QUESTIONS REPORT
for Browns Ferry Questions
94. G2.1.12 001
The following plant conditions exist on U-2.
-1 Mode 5
- Reactor Mode Switch REFUEL
- Spent Fuel Pool Shuffle in progress
The following plant conditions exist on U-3.
- Mode 4
- Reactor Mode Switch SHUTDOWN
- Preparations for startup underway
In accordance with Tech Specs the Standby Gas Treatment is ...
A. NOT required to be operable
B? required to be operable for U-2.
C. required to be operable for U-3.
D. required to be operable for both units.
References: Technical Specification 3.7.B
RO Tier:
SROTier: T3
Keyword:
Cog Level: CIA 2.914.0
Source:
B
Exam:
BF02301
Test:
S
Misc:
Tuesday, January 21,2003 08:41:46 AM
97
QUESTIONS REPORT
for Browns Ferry Questions
95. G2.2.14 001
Unit 3 is in a Refueling Outage with a 24 month Group 2 surveillance in progress. The
Test Director assigned to coordinate the surveillance is in the control room monitoring
the test when the SGT system receives an actual Auto Start signal. The Test Director
stops the surveillance until the conditions that caused SGT to auto start are corrected.
Which ONE of the following describes the actions the Test Director must perform to
restart the surveillance?
A.' Re-verify the Initial conditions and ensure equipment performance will not be
jeopardized by completing the remainder of the procedure.
B. Discard the surveillance test that was interupted and repeat the surveillance from
the beginning.
C. Verify with Operations that they are able to support the remainder of the
surveillance test and continue where the procedure was interupted.
D. The Test Director and Operations can review the procedure to see if all of the
Acceptance Criteria is met. If it is then the surveillance can be signed off as
complete.
Reference: SPP-8.1 Rev.2 Pg 9
OPL171.078 Rev.11 Pg 14
Enabling Objective OPL171.078 #B11
A. Correct answer,
B. Incorrect since the previous procedure is not discarded.
C. Incorrect since the Test Director and Operations must re-verify the initial conditions
prior to restarting the test.
D. Incorrect since the surveillance cannot be signed off as complete until all steps are
completed or N/A'd.
RO Tier:
Keyword
TESTING
Source:
N
Test:
S
SROTier: T3
Cog Level: MEM 2.U3.0
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:46 AM
98
QUESTIONS REPORT
for Browns Ferry Questions
96.
G2.2.5 001
The System Engineer for the RHR System has performed an Evaluation for a
Temporary Alteration to the system. The temp alt is not Quality Related. The Systems
Engineering Manager has approved the temp alt.
Which ONE of the following lists the individuals that are required to give approval prior
to installing the temp alt?
A. Shift Manager, PORC, and Plant Manager.
B. Regulatory Assurance Manager and Plant Manager.
Cy Shift Manager and Plant Manager.
D. Shift Manager, Regulatory Assurance Manager, and PORC.
References: OPL171.079 Rev.11 pg 9
A. Incorrect since PORC is not required since the temp alt is not quality related.
B. Incorrect since the Regulatory Assurance Manager is not a required signature.
C. Correct answer since temp alt is not Quality related.
D. Incorrect since Regulatory Assurance Manager and PORC are not required
signatures.
RO Tier:
Keyword
TEMP AL'I
Source:
N
Test:
S
SROTier:
T3
Cog Level: CIA 1.612.1
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003 08:41:46 AM
99
QUESTIONS REPORT
for Browns Ferry Questions
97. G2.3.4 001
Given the following exposure history data for an individual:
~
Lifetime Exposure:
19500 mrem TEDE (NRC form 4 on file)
Annual Exposure:
4600 mrern TEDE
Quarterly Exposure: 600 mrem TEDE
Sex:
Male
Age:
22
Which ONE of the following is the maximum additional whole body exposure the
individual is allowed to receive in the current calender quarter under Federal (IO CFR
20) exposure limits? (Not a planned special exposure)
A:' 400 mrem TEDE.
B. 600 mrem TEDE.
C. 800 mrem TEDE.
D. 1400 mrem TEDE.
References: 10 CFR 20 Subpart C 20.1201
A. Correct answer.
B, C and D. Incorrect since worker is limited to 5000 mRem annually.
Note: Changed annual dose in stem to 4600 instead of 4300. This changed the correct answer.
RO Tier:
SROTier:
T3
Keyword
RADIATION CONTROL
Cog Level: CIA 2.513.1
Source:
B
Exam:
BF02301
Test:
S
Misc:
TCK
Tuesday, January 21,2003 08:41:46 AM
100
QUESTIONS REPORT
for Browns Ferry Questions
98. G2.3.9 001
Unit 2 startup is in progress with the following conditions existing:
Reactor Power
10% RTP
Reactor Pressure
920 psig
Mode Switch Position
START/HOT STBY
Containment is being inerted with purge filter fan in service.
Which ONE of the following describes the results of taking the action specified under
these plant conditions?
A. Placing the Reactor Mode Switch in RUN will initiate a Group 6 PClS isolation
unless Bypass switches are placed in BYPASS on panel 9-3.
BY Placing the Reactor Mode Switch in RUN will automatically close all valves required
for inerting with the purge filter fan unless Bypass switches are placed in BYPASS
on panel 9-3.
C. Turning the purge filter fan off will automatically close the drywell and suppression
chamber exhaust valves.
D. Placing the Reactor Mode Switch in RUN will automatically close the drywell and
suppression chamber exhaust isolation valves unless the Drywell/Suppression
Chamber Train N B Vent keylock switches are positioned to DRYWELL.
References: OPL171.032 Rev.10 pg 14 and 15
A. Incorrect since placing the Mode Switch in RUN will not initiate a Group 6 isolation.
B. Correct answer.
C. Incorrect since turning off the purge fan will not close the valves.
D. Incorrect since placing the DrywelllSuppression Chamber Train N B Vent keylock
switches to the DRYWELL position does not prevent valve movement.
RO Tier:
Keyword
CONTAINMENT
Source:
B
Test:
S
SROTier:
T3
Cog Level: CAI 233.4
Exam:
BF02301
Misc:
TCK
Tuesday, January 21,2003
08:41:46 AM
101
QUESTIONS REPORT
for Browns Ferry Questions
99. G2.4.29 001
It is noted by the Unit 2 Supervisor that a Site Area Emergency classification level was
exceeded but the present situation indicates that only an Alert classification level is
being exceeded ,..........
Which ONE (1) of the following is correct concerning the Radiological Emergency
Plan?
-
.__
. .
A. the higher classification should be reported to CECC, if staffed, or ODs, if the
CECC is not staffed, and the lower classification reported to NRC.
B.' the higher classification shall be reported to NRC and the CECC if staffed, or the
ODs, if the CECC is not staffed, but the higher classification should not be
declared.
C. only the lower classification should be reported to NRC and the CECC if staffed, or
the ODs, if the CECC is not staffed.
D. the higher classification shall be declared.
References: EPIP-1 Rev.29 Pg 3
A. Incorrect since the higher classification should be reported to the NRC.
B. Correct answer.
C. Incorrect since the higher classification should be reported to the NRC.
D. Incorrect since the higher classification should not be declared but should be
reported to everyone.
RO Tier:
Keyword
Source:
B
Test:
S
SROTier: T3
Cog Level: MEM 2.614.0
Exam:
BF02301
Misc:
Tuesday, Janualy 21,2003 08:41:46 AM
102
QUESTIONS REPORT
for Browns Ferry Questions
100. G2.4.41 001
Units 1 and 2 Control Room has become engulfed with smoke and at 1415 the SM
orders the control room abandoned. The status of the Units is as follows:
Unit 1 is defueled.
Unit 2 is in Mode 1.
-Unit 3 control room is unaffected.
At 1438 control of Unit 2 is established from Panel 2-25-32.
Which ONE of the following describes the Emergency Classification and who is
responsible for EPIP implementation?
A. SM declares an ALERT and he implements EPIP.
B. SM declares an ALERT and Unit 1 US implements EPIP.
C. SM declares a SITE AREA EMERGENCY and SSS implements EPIP.
D.' SM declares a SITE AREA EMERGENCY and Unit 3 US implements EPIP.
References: 2-AOI-100-2 Rev. 47 pg 3
Enabling Objective OPL171.208 #4
A. Incorrect since this is classified as a Site Emergency due to backup control from
Panel 2-25-32 is NOT established within 20 minutes.
B. Incorrect since this is classified as a Site Emergency due to backup control from
Panel 2-25-32 is NOT established within 20 minutes.
C. lncorrec since Unit 3 US assumes responsibility for EPIP implementation.
D. Correct answer since control from Panel 2-25-32 is NOT established within 20
minutes.
Note: Changed stem as far as time it takes to establish control from Panel 2-25-32
which changes the answer.
RO Tier:
SROTier:
T3
Keyword
CONTROL ROOM
Cog Level: CIA2.3t4.1
Source:
M
Exam:
BF02301
Test:
S
Misc:
TCK
Tuesday, January 21,2003 08:41:46 AM
103