ML041260465
| ML041260465 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/30/2004 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-259/04-301, 50-260/04-301, 50-296/04-301 | |
| Download: ML041260465 (115) | |
See also: IR 05000259/2004301
Text
Final Submittal
BROWNS FERRY EXAM
50-259, 50-260, &
50-296/2004-301
April 23 - 30,2004
I.
Final Submittal
(Blue Paper)
1.
Senior Operator Written Examination
Final Submittal
(Blue Paper)
I. Reactor Operator Written Examination
(Browns Ferry 2004-301)
U.S. Nuclear Regulatory Commission
Site-Specific
SRO Written Examination
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Applicant Information
Instructions
Use the answer sheets provided to document your answers. Staple this cover sheet on
top of the answer sheets. To pass the examination you must achieve a final grade of at
least 80.00 percent overall, with a 70.00 percent or better on the SRO-only items if given
in conjunction with the RQ exam: SR6-only exams given alone require an 80.00 percent
to pass. You have eight hours to complete the combined examination, and three hours if
you are only taking the SRO portion.
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Applicant Certification
All work done on this examination is my own. I have neither given nor received aid
RO I SRO-Only I Examination Vaiues:
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Points
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Points
Applicant's Scores:
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Applicant's Grades:
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Percent
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
testing control rod 30-31,
the operator notes that the CRD is reading 360°F.
Which ONE of the following describes the effect this could have on the scram time
associated with control rod 30-31 and the required action to be taken by Tech Specs?
The scram time may be .....
A. faster than normal; requires the control rod to be declared INOPERABLE.
3.'
slower than normal; requires the control rod to be declared "slow" or an Engineering
Evaluation performed.
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Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
2. 203000KS.01 001;T2GliiRHR SYSTEMiCiA 2.1/3.4~~n'iHF04301/R/TCK
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Unit 3 is in Mode 4 preparing to startup when the Operator notices that the actuator
position indication for the RHR Loop II Testable Check Valve is de-energized. Initial
troubleshooting indicates that there is a short in the circuit.
Which ONE of the following describes the effect on the RHR System and plant startup?
RHR Loop II is ....
A. degraded but OPERABLE, plant startup must be delayed until an evaluation is
Derformed.
B.? fully OPERABLE, plant startup can continue,
C. INOPERABkE, plant startup must be delayed until repairs are complete.
D. INOPERABLE, plant startup can continue.
K/A 203000 K5.01 Knowledge of the operational implications of the following
concepts as they apply to RHR/LPCI: INJECTION MODE: Testable check valve
operation. (233.4)
References: Tech Spec 3.5.1 I ECCS ~ Operating.
Technical Requirements Manual, 3.5.1
~ RHR Cross-Connect.
A. Incorrect since an evaluation does not need to be performed prior to piant startup.
B. Correct answer.
C and B. Incorrect since the RHR system is OPERABLE.
Browns Ferry Nuclear Plant 2004-301
SRQ M a l Exam
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Which ONE ofthe following supplies power to the "1B" RHR Pump rnotur?
A. 4 KV Unit Board "%a".
B. 4 KV Unit Board "2B".
C. 4 KV Shutdown Board "B".
BY 4 KV Shutdown Board "C".
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Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
a 480 Volt power supply?
A. 3-FCV-093-0003, HPCl STEAM LINE OTBD lSOh VALVE
3-FCV-073-0064, HPCI TURB EXHAUST VACUUM RELIEF VALVE
KIA 206000 K2.01 Knowledge of electrical power supplies to the following: System
valves. (3213.3)
References: OPL174.042, Rev.76, pg 32 and 49 of 70
Learning Objective #7
3-01-73, Rev29
A. Incorrect since 3-FCV-093-0003 is powered from 250 VDC.
B. Correct answer.
C. Incorrect since 3-FCV-073-0003 is powered from 250 VBC.
D. Incorrect since 3-FGV-073-0016 is powered from 250 VDC.
Browns Ferry Nuclear Plant 2004-301
SI30 lnital Exam
The 2A Core Spray pump has just been started for performance of the Quarterly Flow
Rate surveillance. The operator notes the following conditions:
- MIN FLOW VALVE, 2-FCV-75-9, indicates closed.
- PEST VALVE, 2-FCV-75-22, indicates dual position.
- INBD INJECT VALVE, 2-FCV-75-25, indicates closed.
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System I Core Spray flow on 9-3 Pnl indicates 275 gpm.
Which ONE of the following actions is in compliance with 2-01-75, Core Spray System,
to prevent pump degradation?
A. 2A Core Spray pump may be operated with no restrictions.
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B.' Continue to operate the 2A Core Spray pump up to 5 minutes at which time the
pump must be tripped.
C. Continue to operate the 2A Core Spray pump up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at which time the pump
must be tripped.
B. Increase flow to at least 500 gpm at which time the 2A Core Spray pump may be
operated without time limitations.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
K/A 209001 A2.06 Ability to (a) predict the impacts of the following on the LOW
PRESSURE CORE SPRAY SYSTEM; and (b) based on those predictions, use
procedures to correct, control, or mitigate the consequences of those abnormal
conditions or operations: Inadequate system flow. (3.2/3.2)
References: OPh171.045, Rev.72, pg 15 of46
Learning Objective #B2
2-01-75, Rev.74, pg 6 Of 60
A. Incorrect answer since flow is ~ 3 0 0
gpm and the min flow valve is closed.
B. Correct answer since flow is <300 gpm which requires the pump to be secured within
5 minutes.
C. incorrect since flow is ~ 3 0 0
gpm but 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is the limit with flow between 300 gpm
and 600 gpm.
B. Incorrect since increasing flow to only 500 gpm does not allow the Core Spray pump
to be ran without limitations. The limit is 600 gpm.
Browns Fer9 Nuclear Plant 2004-301
SRO lnital Exam
Unit 3 is making preparations for startup after a forced outage with the unit in Mode 4.
The RQ is performing prestartup checks for the Standby Liquid Control System in
accordance with 3-01-63, Standby Liquid Control System step 4.1.6, which states "SLC
Storage Tank concentration meets Technical Specification 3.1.7 requirements". The
following conditions are noted by the RQ:
- Tankvolume
3650 gallons
- Tank temperature
55°F:
- Boron Concentration
10%
- Quantity of Boron-IO
190 pounds
Which ONE of the following d scribes the acti
conditions for the SLC system?
(Reference provided)
b taken to meet the prestartup
A. Place tank heaters in service and raise tank temperature to > 65°F.
B.' Verify the conditions above have not changed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and then the unit is
ailowed to transition to Mode 2.
C. The unit is allowed to go to Mode 2 because the Tech Spec requirements for the
SLC System are acceptable. No further actions are required.
B. Increase tank volume to > 3785 gallons and then sample the tank to verify
conditions above have not changed and then the unit is allowed to transition to
Mode 2.
Browns Ferry Nuclear Plant 2004-301
SR0 M a l Exam
KIA 22 1000 G2.2.1 Ability to perform pre-startup procedures for the facilitylincluding
operating those controls associated with plant equipment that could affect reactivity.
(3.7/3.6)
Provide TS 3.1.7 with Table.
References: 3-01-63, Standby Liquid Control System, Rev.16, pg 6 of 27
Tech Spec Table 3.1.7-1
A. Incorrect since Boron Concentration does not have to be lowered to < 9.2% prior to
going into Mode 2. SR 3.1.7.3 allows the concentration to be
met.
9.2% if the Table is
B. Correct answer. See SR 3.1.7.3 OR statement.
C. Incorrect since there is a requirement to check the Table prior to entering Mode 2.
69. Incorrect since the tank volume only ha5 to be greater than 3007 gallons, not 3700
gallons.
Browns Feny Nuclear Plant 2004-301
SRO lnital Exam
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7. 212000A2.03 001i1'2Gl/iRPS/C/A 3.li3.5/NiBF04301/lUTCK
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Unit 2 is operating at 85% power. RPS "B" has been placed in the tripped condition
due to the failure of 2-PIS-64-56D (High Drywell Pressure 52 Channel). During
troubleshooting the IM's report that NONE of the High Drywell Pressure switches will
initiate an RPS actuation.
Which ONE of the following most accurately describes the actionsllimitations imposed
by Tech Specs?
A. Verify RPS "B" is in the tripped condition immediately and no further actions are
required.
B.' Restore RPS trip capability within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, otherwise, 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 />.
C. Place RPS "A" in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, otherwise, 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 />.
D. Enter TS 3.0.3 and commence a shutdown within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in Mode 2 within
10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
KIA 212000 A2.03 Ability to (a) predict the impacts of the following on the REACTOR
PROTECTION SYSTEM; and (b) based on those predictions, use procedures to
correct, control, or mitigate the consequences of those abnormal conditions or
operations: Surveillance testing. (3.3/3.5)
References: 2-01-99 Illustration 3 Wev.55
2-01-64 illustration 2 Rev.74
Tech Spec 3.3.1 .I-1 Function 6
A. Incorrect since RPS Function not met. Action C required to be entered
B. Correct answer. Action C entered and then Action G as required by Table 3.3.1.1-1.
C. Incorrect since RPS Function net met. Action 5 is already met.
B. Incorrect since 3.0.3 is not entered since this condition is accounted for in the
Required Actions.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
Which ONE of the following correctly describes the Unit 1 Reactor Protection System
power supply?
A. RPS " A and RPS "3" receive alternate power from 480V RMOV Board 1B.
B. RPS " A and RPS "B" can both be powered simultaneously from 480V Shutdown
Board 1B.
C? Both RPS Buses have a mechanical interlock to prevent simultaneously paralleling
their normal power supply with their alternate power supply.
D. RPS Bus alternate power is supplied through a transformer shared with the unit
preferred system.
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K/A 212000 K4.03 Knowledge of REACTOR PROTECTION SYSTEM design
feature(s) and/or interlocks which provide for the following: The prevention of supplying
power to a given RPS bus from multiple sources simultaneously. (3.0/3.1)
References: OPk171.028, Rev.13, pg 11 of 39
Learning Objective WB4.
A. Incorrect since the alternate power supply is 480V Shutdown Board 1 B.
B. Incorrect since there is an interlock which prevents both RPS buses from being
powered simultaneously from the alternate power source.
6.
Correct answer.
B. Incorrect since the power is supplied just through a transformer. Unit 2 has the
power supplied through a transformer shared with the unit preferred system.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
The Shift Manager has authorized the performance of 2-SR-3.3.2.1.1, Rod Block
Monitor (RBM) Functional Test. While performing steps 9.6.25.1 through 7.6.25.5 for
" A RBM Upscale Trip, the 190 receives:
- CONTROL ROB WITHDRAWAL BLOCK (2-XA-55-5A, Window 7)
- RBM WIGH/INOP (2-XA-55-5A, Window 24)
The UO notes that RBM A HIGH Indicating bight on panel 2-9-5 is NOT illuminated
and the Instrument Tech did NOT receive ROD BLOCK indication on 2-MQN-92-5A.
Which ON of the following actions should be taken for this situation?
(Reference provided)
A," Notify the Shift Manager immediately and he should declare " A RBM Inoperable.
B. Note the discrepancy on Attachment 2 in the Post Test remarks. Ensure the
deficiency is evaluated. No further action is required.
C. Re-perform section 7.6.25.1 through 7.6.25.5 and if the same indications are
received then stop the surveillance and inform the Shifl Manager.
D. Continue with the procedure and notify the Shift Manager after completing sections
7.9.25.1 through 7.7.25.5 for the "B" WBM.
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WA 21500% 82.05 Ability to (a) predict the impacts of the following an the ROD
BLOCK MONITOR SYSTEM; and (bj based on those predictions, use procedures to
correct, control, or mitigate the consequences of those abnormal conditions or
operations: Back panel meters and indicating lights. (3.213.2)
References: 2-SR-3.3.2.1.1, Rev.3 (Provide as a reference on exam)
A. Correct answer. Acceptance Criteria not met. See section 6.1
B. Incorrect since further action to declare A RBM inoperable is required.
C. Incorrect since you do not re-perform steps if something doesn't work right.
D. Incorrect since you stop the procedure until discrepancy is resolved.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
10. 21 5002K2.03 001/1'2G2//NEUTRON hlONlTOKING/MEhl2.8i2.9/BiBF0430I/R!TCK
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Which ONE of the following describes the power supply to the PRNM system?
RPS A supplies power to .....
A. both RBM interface panels and to only half of the APRM chassis.
5. one RBM interface panel and to only half of the LPRM chassis.
6. both RBM interface panels and to all of the LPRM and APRM chassis.
B:' one RBM intetface panel and to all of the APRM chassis.
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K/A 215002 K2.03 Knowledge of electrical power supplies to the following: APRM
channels. (2.8/2.9)
References: OPLf71.148, Rev.7, pg 52
2-QC92BIC, Wev.33
Enabling Objective #I315
A, B and C. Incorrect since RPS A supplies power to all chassis.
D. Correct answer.
Browns Ferry Nuclear Plant 2004-301
SRO M a l Exam
Unit 3 is making preparations for a plant startup from Mode 4 . IRM G is currently
INOPERABLE and IRM A has just failed upscale during testing prior to entering
Mode 2.
Which ONE of the following describes the action required by Tech Specs and the
impact on plant startup?
A. Must place the "A" channel in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Startup cannot continue.
B.' No actions required by Tech Specs at this time. ERM A or IRM G must be
OPERABLE prior to entering Mode 2.
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C. Must place the "A" channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Startup cannot continue.
D. No actions required by Tech Specs at this time. If IRM G is Bypassed and "w"
channel is placed in trip then Unit 3 can continue with the startup.
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KIA 215003 82.02 Ability to (a) predict the impacts of the following on the
INTERMEDIATE RANGE MONITOR (IRM) SYSTEM; and (b) based on those
predictions, use procedures to correct, control, or mitigate the consequences of those
abnormal conditions or operations: IRM inop condition. (3.93.9)
References: Tech Spec section 3.3.7 .I,
Action A
Tech Spec Table 3.3.7 .I-1, Function 1
OPb771.Q20, Rev.7, Pg 23 of 55
A. incorrect since no actions are required with the unit in Mode 4.
B. Correct answer since only one IRM needs to be declared OPERABLE prior to
entering Mode 2.
C. Incorrect since no actions are required with the unit in Mode 4.
8.
Incorrect since unit startup cannot continue since a rod block will be inserted if first
action is taken.
Browns Ferry Nuclear Plant 2004-305
SRO lnital Exam
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12. 21 5003A3.03 001!12Gl/!RPS/C!A
3.7!3.6/M!DF03301,~~TCK
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The reactor has just reached criticality during a reactor startup. A malfunction in the
RMCS results in a control rod being continuously withdrawn from 00 to full out position.
With no operator action, which ONE of the following would be the FIRST signal to
terminate this reactivity addition event?
C. REACTOR HI PRESSURE scram.
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K/A 215003 A3.03 Ability to monitor automatic operations of the INTERMEDIATE
RANGE MONITOR (IRM) SYSTEM including: RPS status. (3.7/3.6)
References: QPL171.028, Rev.13, pg I 9 Lo 22
Learning Objective #B6
A. Incorrect since the SRM Hi Hi scram signal is bypassed with the shorting links
installed.
B. Correct answer.
C. Incorrect since under these conditions the reactor is vented and the reactor High
Pressure Scram is unattainable.
D. Incorrect since the IRM Hi Hi signal will be initiated prior to the APRM Hi Hi signal.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
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13. 215004K1.01 001lT2GI/lSRMIMEM 3.6!3.7!MiHF04301~/TCK
Which ONE of the following correctly describes the response of the Reactor Protection
System to neutron monitoring inputs with all of the shorting links removed?
A. 1/2 scram on any APRM HI-Hi or hop.
B. FULL scram on any IRM HI signal.
C I FULL scram on any SRM Hi-HI or inop.
D. 1/2 scram on any SRM HI-HI or inop.
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K/A 2150Q4 K1 .Q1 Knowledge of the physical connections andlor cause-effect
relationships between SOURCE RANGE MONITOR (SRM) SYSTEM and the following:
Reactor protection system. (3.6/3.7)
References: OQL271.028, Rev.l3, pg 20 and 22 of 39
Enabling Objective #B7
A. Incorrect since an APRM Hi Hi signal from any APWM will cause a full scram with a19
of the shorting links removed. This would be true if only the blue links were removed.
B. Incorrect since an IRM Hi Hi signal from any IRM will cause a full scram with all of
the shorting links removed. This would be true if only the blue links were removed.
C. Correct answer.
D. Incorrect since a full scram will occur from an SRM Hi Hi signal with all of the
shorting links removed.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
An LPRM, assigned to APRM 2, is bypassed with High Voltage On at Panel 9-14.
Which ONE of the following is the result of this operator action?
A. The output of the LPRM to APRM 2 is inhibited, however, the output cannot be read
at the NI Console.
3. The output of the LPRM is active to APRM 2, however, the output can be read on
the NI Console.
CY The output of the LPRM to APRM 2 is inhibited, however, the output can be read at
the NB Console.
D. The output of the LPRM is active to APRM 2, however, the output cannot be read
on the NI Console.
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K/A 215005 A4.05 Ability to manually operate andlor monitor in the control room: Trip
bypasses. (3.4/3.4)
References: 2-01-92B
Learning Objective #6
A. Incorrect since the output can be read from the NI console.
B. Incorrect since the output of the LPRM is inactive.
C. Correct answer.
D. Incorrect since the output of the LPRM is inactive.
Browns Ferry Nuclear Plant 2004-302
SWO lnital Exam
15. 215005K6 05 0@112GlIRM/C/.4 2 93 lMiBF043@1/R/TCK
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Unit 3 is conducting a startup with the following conditions present:
- MODE Switch position
- IRM readings
- Reactor Pressure
960 psig
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Reactor Water Level
StartIHot Stby
Ail on range 9
+36 and steady
A control rod drop accident occurs followed by a Rx Scram. The operator reports that
ALL IRMs are reading Hi Hi but that the reactor failed to scram from this signal.
Which ONE of the following signals. caused the Rx Scram?
A. Reactor Water Level - Low.
B. IRM - hop.
C: APRM Hi Hi (setdown).
D. APRM Hi Hi.
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KIA 215005K6.05 Knowledge of the effect that a loss or malfunction of the foilowing
wili have on the AVEKAGE POWER KANGE MONITORILOGAL POWEK RANGE
MONITOR SYSTEM: IRM. (2.9I3.1)
Keferences: OQL171.028, Rev.? 3, Appendix 1
A. Incorrect since reactor water level should not reach the scram setpoint with only one
rod dropping.
B. Incorrect since the IRMs already failed to initiate a scram and this. is the same logic.
C. Correct answer. With the Mode Switch in SIU this function is active.
B. Incorrect since the APRM Hi Hi (setdown) occurs well below this setpoint.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
16. 21700062.4.30 00l/iT2G I/KEPORTABII.ITY!C/A 2.2!3.6~iBF04301/SiTCK
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During the performance of Unit 2 WClC Quarterly Flow Rate Test, the controller
operated erratically which resulted in WClC being declared INOPERABLE.
Which ONE of the following describes the Notification requirements for this condition?
A,* No Outside Agencies are required to be notified of this condition.
B. The NRC must be notified within I hour of this condition.
C. The NRC must be notified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of this condition.
B. The NRC and state agencies must be notified within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of this condition.
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K/A 21 7000 G2.4.30 Knowledge of which events related to system operationdstatus
should be reported to outside agencies. (2.%/3.6)
References: Licensee needs to provide documentation and verify correct answer.
A. Correct answer. Although RCIC is a single train system, it is not an ESF System
and does not require outside agencies to be notified upon INOPERABlblTY.
B. Incorrect since notification is not required. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is a valid time frame under other
conditions.
C. Incorrect since notification is not required. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is a valid time frame under other
conditions.
D. Incorrect since notification is not required. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is a valid time frame under other
conditions.
Browns Ferry Nuclear Plant 2004-301
SWO lnital Exam
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The normal power supply to the Unit 3 RCIC Flow Controller, FIC-71-368, has become
erratic and I&C has requested the controller to be transferred to the alternate power
SWPlY.
Which ONE of the following sources of power will now be available to the RClC Flow
Controller once the transfer is complete?
A. DIV 1 ECCS Inverter.
B. BIV 2 ECCS Inverter.
61 Unit Preferred power system.
B. Plant Preferred power system.
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W 8 217000 K2.03 Knowledge of electrical power supplies to the following: WCiC flow
controller. (2.7/2.8)
References: OPL171.049, Rev.18, pg 20 of 53
Enabling Objective #B7
A. Incorrect since this is the normal power supply to the WClC Flow Controller.
B. Incorrect since this is the normal power supply to the HPCL Flow Controller.
6.
Correct answer.
B. Incorrect since the alternate power supply to the RClC Flow Controller is the Unit
Preferred power supply.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
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18. 218000Al 04 001/T2GII/ADS,'MFM4
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A small break LOCA has occurred on Unit 2 with a failure of all high pressure injection.
Conditions have deteriorated to the point of auto initiation of ADS.
Which ONE of the following describes when the ADS valves will close assuming all
ADS valves remain in Auto?
A. When all low pressure ECCS pumps are secured.
B. When reactor water level rises above -122 inches.
C. When reactor pressure drops below 150 psig.
D?' When reactor pressure lowers to 20 psig above suppression chamber pressure.
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K/A 228000 A4.04 Ability to predict and/or monitor changes in parameters associated
with operating the AUTOMATIC DEQRESSUREATBON SYSTEM controls including:
Reactor pressure. (4.1/4.2)
References: QPL171.043, Rev.10, pg
OPL171.009, Rev.8, pg 17 of 57
Enabling Objective #B3 (OPbl71.043)
A. Incorrect since the pumps need to be running to initiate ADS, not to secure it
B. Incorrect since the ADS valves have already been actuated and remain that way
until the reactor is depressurized.
C. Incorrect since this is the pressure at which the ADS valves are required to be
operable and has no affect on ABS operation.
B. Correct answer.
Browns Ferry Nuclear Plant 2004-306
SRQ lnital Exam
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Which ONE of the following is the basis for initiation of drywell sprays before the bulk
drywell temperature reaches the drywell design temperature limit?
A. To prevent excessive thermal stresses on the containment structure.
B." To ensure that equipment within the drywell will operate when required.
C. To ensure that the capacity of the suppression chamber to drywell vacuum
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breakers are not exceeded.
B. To limit the amount of containment spray that flashes to steam upon initial spray
flow actuation which could cause a pressure increase above design limits.
KIA 223004 K1.03 Knowledge of the physicaf connections and/or cause-effect
relationships between PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES and
the following: Containment/drywell atmosphere control. (3.Z3.3)
Keferences: EOlPM Section 8-V-D, 01-2, Primary Containment Control Bases, Pgs
6,8,
and 18 of 245.
A. insurrect since the Containment Analyses accounts for all conditions of containment
temperature up to the design basis temperature.
B. Correct answer.
C. Incorrect since drywell sprays can be isolated if the containment pressure reaches 0
pig. The only concern prior to initiating sprays is whether or not the vacuum breakers
are covered with water.
B. Incorrect since initiation of dryweli sprays causes an immediate drop in drywell
temperature and pressure due to evaporative cooling.
Browns Ferry Nuclear Plant 2004-3631
SRO lnital Exam
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20. 22300262.1.8 001iT2G 1 /\\MSIV/C/A 3.8/3.&%/RFO4301 !RiTTCK
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A loss of control air has occurred on Unit 2 which resulted in the Outboard MSlV's
failing closed. The Shift Manager has determined that the Main Condenser is required
for a heat sink. The PCIS Group 6 signal is reset.
Which ONE of the following actions is required to be performed to open the Outboard
M S BV's?
A. Verify the Inboard MSIV's are open and then perform Appendix 88, Reopening
MSIV's Following Group I
Isolation.
B. Close the Inboard MSIV's and then Open the Outboard MSiV's from the Control
Room. Perform Appendix 8B, Reopening MSIV's Following Group 1 Isolation.
C. Perform 2-AOl-32-2, Loss of Control Air. Attachment 2 to align nitrogen to the
Drywell Control Air Compressor Suction. Open one Outboard MSIV lo equalize
pressure in header and then open remaining Outboard MSIV's.
D I Perform 2-AOl-32-2, Loss of Control Air, Attachment 2 to align nitrogen to the
Drywell Control Ais Compressor Suction. Then perform Appendix 8B, Reopening
MSIV's Following Group 1 Isolation.
WA 223002 G2.1.8 Ability to coordinate personnel activities outside the control room.
(3.8B.6)
References: 2-801-32-2, Attachment 2
2-01-1, Section 5.2.7
A. Incorrect since Attachment 2 of 2-A01-32-2 is required to be performed to open the
MSWs.
B. incorrect since Attachment 2 of 2-801-32-2 is required to be performed to open the
MSIV'S.
C. incorrect since pressure in the header is not equalized by just opening an MSIV.
D. Correct answer.
Browns Ferry Nuclear Plant 2004-302
SRO lnital Exam
2 1 . 2230OZK3.03 001iT2(i 1 iIPCISMEM 3.6:3.8/N!BFCWO 1IIPITCK
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A design basis LOCA has occurred on Unit 3 concurrent with the Torus-to-Drywell
vacuum breakers failing open. All low pressure systems functioned as designed with
vessel level currentiy being maintained at +40 inches.
Which ONE of the following is the most likely cause of an increase in the Off-Site
radioactive release rates?
A. The Standby Gas Treatment system has failed due to contamination of the charcoal
filters.
B. A fuel failure has occurred due to voiding of the reactor vessel.
6. Inadequate scrubbing of the steam atmosphere has occurred due to bypassing the
downmmers.
DI The Primary Containment has failed due to exceeding the design pressure limit.
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K/A 223602 K3.03 Knowledge of the effect that a loss or malfunction of the PRIMARY
CONTAINMENT ISOLATION SYSTEMINBICLEAR STEAM SUPPLY SHUT-OFF will
have on the following: OfB-site radioactive release rates. (3.6/3.8)
References: OPL171.016, Rev.12, pg 30 of76
A. Incorrect since the Standby Gas Treatment is designed to take a suction on an
environment that may have steam in it.
5. Incorrect since the reactor design accounts for this voiding and the reflood of low
pressure systems in time to prevent core damage.
C. Incorrect since this would not result in an increase in off-site release rates. This
does happen if the containment remains in tact.
D. Correct answer.
Browns Ferry Nuclear Plant 2084-301
SRO lnitai Exam
A small break b0CA has occurred on Unit 3. Drywall Pressure reached 8 psig at which
time Torus and Drywell Sprays were initiated. The following conditions exist at this
time:
- Drywell Pressure
1.6 psig
- Torus Pressure
1.2 QSig
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Reactor Water Level
+5 inches
- Reactor Pressure
298 psig
- LPCI Initiation Signal Selecff Reset switch
- Keylock Bypass Switch,3-XS-74-122
- Drywell Temperature
110°F
Select position
Bypass position
Which ONE of the following indicates the Division 1 RWR System status?
(Assume no operator action)
A. Both RHR pumps are running with SQme flow to the vessel and some flow directed
to Torus and Drywell Sprays.
By Both WHR pumps are running with some flow to the vessel and the rest directed
through the minimum flow line.
C. A RHR pump is running with all of the flow directed through the minimum Row line.
D. B RHR pump is running with some flow to the vessel and some flow directed to
Torus and Drywell Sprays.
1
Browns F ~ F V
Nuclear Plant 2084-301
SRO lnital Exam
WA 226001 A3.06 Ability to monitor automatic operations of the RHFULPCI:
CONTAiNMENT SPRAY SYSTEM MODE including: Containment temperature.
(3.5/3.5)
References: OPL171.044, Rev.lQ, pg. 29 and 42
3-01-74, Rev.58, P&L 3.29.7
A. Incorrect since the Spray Line isolation interlock at 1.96 psig Drywell Pressure
cannot be bypassed.
B. Correct answer.
6. Incorrect since both RHR pumps should be running and some of the flow should be
going to the vessel.
13.
Incorrect since bath RHR pumps should be running and the Spray Line isolation
interlock at 1.96 psig Drywell Pressure cannot be bypassed.
Browns Ferry Nuclear Plant 2004-381
SRO lnita! Exam
23. 23000062.3.9 OOl~rZCi2ilCONTAINM~~T/MEha
2.5/3.4iUIBF04301/ICK
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Unit 2 is in MODE 2. A containment entry to add oil to the " A Recirc motor upper
bearing has just been completed. The Drywell and the Torus are currently de-inerted.
Which ONE of the following describes the containment herding flow path for this
condition?
During containment inerting operation, the normal flow path would be the supply to:
A,* the suppression chamber and exhaust from the suppression chamber (through the
Containment Purge Filter).
B. only the drywell and exhaust from only the suppression chamber (through the
Standby Gas Treatment System).
C. both the drywell and suppression chamber and exhirerst from both (through the
containment Purge Filter).
B. both the d w e l l and suppression chamber and exhaust from both (through the
Standby Gas Treatment System).
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%(/A 230000 G2.3.9 Knowledge of the process for performing a containment purge.
(2 33.4)
References: OPL171.032, Rev.10, Pg 10 of 32
2-01-76, Rev.58, Step 5.1.43 Note
A. Correct answer. Can only purge the torus or the drywell in Mode 2.
B. Incorrect since this ties the Drywell to the Torus.
C. Incorrect since can only purge the drywell or torus in Mode 2.
D. Incorrect since can only purge the dfywell or torus in Mode 2.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
24. 239001A4 01 001?r2G2/MSIV/MEM
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4.214 ONBFO4301IRITCK
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Unit 2 Reactor Power has been reduced to 66% RTP in preparation for MSlV testing. A
fuse has been removed to simulate the B OTBB MSIV closed.
Which ONE of the following describes the indications that will be observed when the
MSlV LINE A OUTBOARD TEST, 2-HS-1-158 (2-FCV-1-15) push-button is
depressed?
A half-scram will occur .....
A. when " A OPBB MSlV indicates mid position (red light and green light ON).
B. when the open indication goes out.
C:' prior to any change in MSIV position indication.
D. when the TEST push-button is depressed.
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K/A 239001 A4.01 Ability to manually operate and/or monitor in the control room:
MSIV's. (4.2/4.0)
References: 2-08-1, Rev.36, Pg 4 of 42
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A. Incorrect since the scram setpoint is 90% open and the dosed indication light is set
at 85% open.
El. Incorrect since the scram setpoint is set at 90% open and does not rely on red light
indication.
C. Correct answer.
B. Incorrect since the scram function is based on MSIV position indication of 90% open
and not when the valve initially goes closed.
Browns Ferry Nuclear Plant 2004-301
SRQ lnital Exam
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239002A4.0 1 00 1X2G IIISAFETY RELEFSICIA
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A Reactor Scram has just occurred on Unit 2. While you were performing a board
walkdown you note that Reactor Pressure has reached 14 15 psig and there are some
SRV's that have automatically opened.
Which ONE of the following is correct regarding the maximum number of SRV's that
could be open given that ALL SRVs are within the Tech Spec allowable tolerances?
(Reference provided)
A. 4
B. 5
CP 8
D. 13
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WA 239002A4.01 Ability to manually operate andlor monitor in the control room:
SRV's. (4.414.4)
References: OPbdSl.Q03, Rev.8, pg 20 of 57
Tech Spec 3.4.3, Safety/Relief Valves (SIRVs)
A. incorrect since all SRV's have a tolerance of + 3% so 4 could open at 1100# and 4
could open at 11 1 O#. The other 5 shouldn't open until 11 20#. Zem is plausible since
the first setpoint is I 1 35#.
8. Incorrect since 8 SRV's could be open and still be within tech spec tolerance.
C. Incorrect since 8 SRV's could be open and stili be within tech spec tolerance.
5. Correct answer as shown above.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
26. 241000G2.2 11 001/fT2(i2TEMPORARY AI.TERATION/?EM 2.5/3.4/N,~F~301/S/~K
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A jumper has been installed and tagged on Unit 3 as directed by 3-SR-3.3.6 .I
.13(8),
Turbine Stop Valve Limit Switch Calibration, step 7.1.9.10. The tag references this
surveillance number. The jumper does not affect the OPERABILITY of the system
components but it does affect an alarm indication. The system engineer has requested
the jumper remain installed until the next performance of this surveillance.
Which ONE of the following is appropriate for controlling this jumper?
A. The Unit Supervisor verifies all Tech Spec requirements are met and logs that the
jumper will remain installed until a work order is created to control the jumper.
B. Leave the tag on the jumper and NIA the step for removal of the jumper. Note at
the end of the procedure that the jumper is still installed. The next performance of
the procedure will control the jumper.
Cy Complete the paperwork for a Temporary Alteration prior to removing the jumper as
directed by the procedure. Note at the end of the surveillance that the jumper
remained installed and identify the Temporary Alteration number.
D. The jumper must be removed in accordance with the surveillance procedure. A
Temporary Alteration is not appropriate for this condition. Complete paperwork for
a design change that allows this jumper to be installed.
K/A 241000 G2.2.11 Knowledge of the process for controlling temporary changes.
(2 3 3 . 4 1
References: OPLf71.079,
Rev.12, Pg 7 and 8 of 21
A. Incorrect since you cannot leave a jumper installed and control it witR a log entry.
Creating a Work Order cannot control a jumper either.
B. incorrect since if the procedure is closed out then nothing is controlling the jumper.
Referencing a controlling procedure is not good enough.
C. Correct answer. Since the procedure is closed out then the Temp Art program must
control the jumper.
D. Incorrect since this does not need a design change and the jumper does not have to
be removed by the procedure if the Temp Ak program is controlling it.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
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27. 241000K4.10 001/TXi2iiMAIN TURB1NE:MERI 2 5/2.SiB/BF04301/RiTCK
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The main turbine is being placed in shell warming per 01-47,
Which ONE of the following describes a consequence of opening the #2 stop valve
internal pilot valve too far during this evolution?
A. Turbine Trip on Differential Expansion.
8. Turbine trip on High Exhaust Hood Temperature,
C I Reactor scram due to Turbine Stop Valve Closure.
D. Reactor Scram due to Turbine Control Valve Closure.
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K/A 241000 K4.10 Knowledge of REACTOWTURBINE PRESSURE REGULATING
SYSTEM design feature(s) and/or interlocks which provide for the following: Turbine
shell warming: EHC-Only. (2.5/2.5)
References: 241-47, Rev.117, Pg 10, 11 and 23 of 162
A. Incorrect since this takes operator action to mitigate.
B. Incorrect since this function has been disabled. Bt now takes operator action.
C. Correct answer. This happens if Turbine first stage pressure reaches 147 psig.
B. Incorrect since the Control Valves are already closed.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
I
The Unit 3 Operator notes the following indications while monitoring plant parameters:
Main Steam Line radiation
increasing
_. Condensate Demineralizer Dp
increasing
- Condensate Conductivity after Bemins
increasing
- Offgas Pretreatment radiation
increasing
Which ONE of the following is the most likely cause of these indications?
A. Condensate Demin resin breakthrough.
5:' Increasing dissolved solids.
C. Decreasing condensate conductivity.
D. Increasing condensate oxygen concentrations.
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KIA 256000 A I .08 Ability to predict and/or monitor changes in parameters associated
with operating the REACTOR CONDENSATE SYSTEM controls including: System
water quality. (2.7L2.9)
References: OPb171.01 I,
Rev.9, pg 23, and 27-29 of 27
2-019, Rev.66, pg 21 of 59
2-AOl-2-1, Rev.17, pg 1 of 5
A. Incorrect since this would cause Condensate Demin Dp to decrease. All other
indications would increase.
B. Correct answer.
C. Incorrect since increasing the conductivity would produce the same indications as
increasing the dissolved solids.
D. Incorrect since increasing the amount of oxygen in the condensate system does not
affect condensate demin Dp.
Browns Ferry Nuclear Plant 2004-301
SRQ lnital Exam
29~
259001K5.02 00IfT2621@EEDWAlER~MEM
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2.5/2.5/B/BF04301!RlTCK
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Which ONE ofthe following is the main reason for ensuring that a piping system, such
as Feedwater, is completely filled and vented PRIOR to initiating system flow?
A. To minimize the system head losses and a potential for runout conditions.
3. To ensure all noncondensible gases are removed from the piping system to reduce
corrosion.
6. TIJ preclude a reduction in the overall heat transfer coefficient.
D? To minimize the potential for water hammer.
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WA 259006 K5.02 Knowledge of the operational implications of the following concepts
as they apply to REACTOR FEEDWATEW SYSTEM: Water hammer. (2.5/2.5)
References: Operating experience
A. Incorrect since runout conditions are caused by too much flow. This is minimized by
starting a centrifugal pump with the discharge valve closed.
B. Incorrect since noncondensibles are undesirable under any circumstances.
C. Incorrect since the areas where the piping is vented are not in heat exchangers but
at high point vents.
B. Correct answer.
Browns Ferry Nuclear Plant 2004-301
§RO lnital Exam
30. 259002K4 11 001,TZGl/iFEEUWATER LEVEL/C/A 3.3i3.3WBFO4301R/TCK
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Unit 3 Reactor Vessel Narrow Range instrument, LT-3-53, has a srnali leak on the
reference leg tap. The Feedwater bevel Control System (FWLCS) is in 3-element
control. The NXTQW Range instruments indicate as follows:
- LP-3-53
44 inches
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LT-3-60
33 inches
- LT-3-206
31 inches
- LT-3-253
33 inches
Which ONE of the following indicates the Reactor Vessel Level that the FWLCS will try 1
to maintain? (Wound to nearest whole number)
A:' 32 inches.
B. 33 inches.
C. 35inches.
B. 37 inches.
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WA 259002 K4.1 I Knowledge of REACTOR WATER LEVEL CONTROL SYSTEM
design feature(s) and/or interlocks which provide for the following: DP control. (3.3/3.3)
References: OPL171.012, Rev.30, pg 19-21
Learning Objective #B5
A. Correct answer. The high level indicated by LT-3-53 is discarded since it is s8
inches above the average. The other 3 signals are averaged for the appropriate control
Bevel.
B. Incorrect since this is the level that would be maintained if the two highest middle
levels were selected. Since LT-3-53 reads >8 above the average then it is discarded
and the average of the 3 remaining levels is used.
C. Incorrect since this is the average of all levels id the highest level is not discarded.
D. Incorrect since this is the average of the 3 highest readings.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
31. 261000A3 02
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001~T2Gll/SBGT/CIA 3 213 l.B/BF0430IflU1CK
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SGT trains A, B, & C are sunning due to a bow Rx Water Level signal that is still
present on Unit 2. Subsequently, the 480v load shed logic is initiated.
Which ONE of the following describes SGT train response?
SGT trains A & B trip and .....
A. will restart in 40 secs. SGT train 6 trips and cannot be restarted.
El. cannot be restarted. SGT train C trips and cannot be restarted.
C I will restart in 40 secs. SGT train C continues to run.
D. cannot be restarted. SGP train 6 continues to run.
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K/A 263000 A3.02 Ability to monitor automatic operations of the STANDBY GAS
TREATMENT SYSTEM including: Fan start. (3.2/3.1)
References: OPL171.818, Rev.$, pg 22 of 30
Learning Objectives #EM and B9
A. Incorrect since Train C is unaffected by the load shed.
B. Incorrect since Grain A and B will restart in 40 seconds and Train C is unaffected by
the load shed.
C. Correct answer.
B. Incorrect since Train A and B will restart in 40 seconds.
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32. 261000K1
'7.2
'SHGTICi'A
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
The following conditions exist on Unit 3:
~ Torus Pressure
2.38 psig
- Reactor Water Level
+3 inches
- Reactor Zone Ventilation High Radiation
- Refueling Zone High Radiation
- SGT System Control Switch Position
- Steam leak in the Drywell
90-1428 detector @ 73 mWhr and
98-143B detector is downscale
90-140A detector @ 69 mWhr am
90-14'i B detector is downscale
All 3 in Auto
Which ONE of the following describes the proper SGT system alignment for these
conditions?
The SGT systems are .....
A. in Standby.
B.' running due to High Containment Pressure
C. running due to Refueling Zone High Radiation.
D. running due to Reactor Zone Ventilation High Radiation.
WA 26? 000 K1 .I
1 Knowledge of the physical connections andlor cause-effect
relationships between STANDBY GAS TREATMENT SYSTEM and the following:
Primary containment pressure. (3.213.3)
References: OPL172.048, Rev.8, pg 21 of 30
Learning Objective #B9
A. incorrect since alk 3 trains should be running due to High Drywell Pressure. With
Torus Pressure at 2.38 psig then Drywell Pressure should be at least 2.98 psig.
B. Correct answer. With Torus pressure at 2.38 psig then Drywell pressure should be
at least 2.98 psig.
C. Incorrect since it takes 2 monitors reading high or one downscale in each division.
B. incorrect since it takes 2 monitors reading high or one downscale in each division.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
33. 26200162.3 3 OOl::TZGI/RADWASTWMEM 1 8~2.9,NBF04301/STCK
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Which ONE of the following REQUIRES Shift Manager approval?
A: Decanting the Condensate Phase Separators directly to the Hotwell.
B. Discharge of water to the Condensate Storage Tanks.
C. Transferring water from the Chemical Waste Tank to the Floor Brain Collector Tank.
D. Crosstie operations between the Floor Drain and Waste filters.
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KIA 262001 62.3.3 Knowledge of SRO responsibilities for auxiliary systems that are
outside the control room (e.g./waste disposal and handling systems). (I
.8/2.9)
Keferences: OPbli'1.084, Rev.5, pg 32,33,34,43.
A. Correct answer. This option requires Shift Manager approval.
B. Incorrect since this option only requires Chemistry Approval.
6. Incorrect since this is a normal Radwaste evolution.
D. Incorrect since this option could be approved by the Unit Supervisor.
Which ONE of the following is the expected electrical system response?
The generator breaker opens .....
A. and 4KV Unit Boards 2A, 28, and 2C transfer to start buses.
B? with no further bus transfers.
C. and 4KV Common Boards 2A & 2B transfer to Start Bus 1A & 1 B respectively.
I.
and 2C 4KV Unit Board transfers to start bus, 4KV Unit Boards 2A & 28 do not
transfer.
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A. Incorrect since the unit boards do not transfer to the start buses. With offsite Dower
available the Main Transformer still supplies all power to the unit.
B. Correct answer.
C. Incorrect since the common hoards do not transfer to the start buses. With offsite
power available the Main Transformer still supplies all power to the unit.
D. Inccmect since the 2C Unit Board does not transfer. With offsite power available the
Main Transformer still supplies all power to the unit.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
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~ ~- 2.5!2.911rl/BF0430
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1 k T C K
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Unit 2 has just experienced an underfrequency condition on the output of the MMG set
that lastedfor 3 seconds.
Which ONE of the following is the appropriate indications for this condition?
A. The AC supply breaker trips, the DC motor picks up the load and the MMG set
continues to supply the loads.
B. The AC and DC supply breakers trip, the loads are automatically transferred to Unit
3 MMG output, and the MMG set stops.
61 The DC supply breaker trips, excitation is lost to the MMG set and the MMG set
continues to run.
B. The MMG set continues to supply loads since the 5 second time delay for the
underfrequency condition was not actuated.
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WA 262002 A I .Q2 Abiiity to predict and/or monitor changes in parameters associated
with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls
including: Motor generator outputs. (232.9)
References: QPL171.102, Rev.4, Pg 10, 12, 13 and 14 of 28
A. Incorrect since the DC breaker trips and does not pick up the load.
B. Incorrect since the AC breaker does not trip, the DC breaker does. The MMG set
continues to run.
C. Correct answer.
B. Incorrect since the 5 second time delay is not applicable to underfrequency but it is
applicable to 120 VAC transformers.
Browns Ferry Nuclear Plant 2004-304
SRO lnital Exam
36. 263000K102
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00iiT2(ilIiDC SYSTEMKIA
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3.2/3.3W/AF04301,RTCK
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A fault has occurred on the "A" Diesel Generator Room 125 V DC Distribution Panel
causing a loss of the battery charger and battery supply.
Which ONE of the following describes the effect this has on the "A" Diesel Generator?
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A. No effect since the "A" diesel generator control power auto swaps to "Unit
Preferred".
B. "A" Diesel Generator will start and come up to rated speed and voltage but the
output breaker can not close because it has lost control power.
C. "A" Diesel Generator control power is [ost; a manual transfer to "Unit Preferred is
required.
D I "A" DieseI Generator control power and field Wash source can not be restored until
the fault is cleared.
WA 263000 K1.02 Knowledge of the physical connections andior cause-effect
relationships between D.C.
ELECTRICAL DISTRIBUTION and the following: Battery
charger and battery. (3.2B.3)
References: QPL17q.037, Wev.8, pg 14 and 15 of 47.
Enabling Qbjective #I
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A. Incorrect since there is no auto transfer feature for the "A" DG $25 VDC distribution
panel.
B. Incorrect since the diesel will not be able to come up to rated voltage since the field
flashing is not available.
C. Incorrect since there is no manual transfer capability for the "A" DG a25 VDC
distribution panel.
5. Correct answer.
Browns Ferry Nuclear Plant 2004-301
SRO M a l Exam
37. 263OOOK3.02 00 liT2G 1 !/KHRSW SYSTEMMEM 3.5/3.8/NN;F@l3O I/RiTCK
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Which ONE of the following components may receive an automatic start signal if the
25QVDC control power to the "C" 4KV Shutdown Board is transferred to the alternate
source while the C Diesel Generator is running?
A. "B" WHR Pump.
B. "B" CS Pump
C. "B1" RHRSW Pump.
WA 263800 K3.02 Knowledge of the effect that a loss or malfunction of the D.C.
ELECTRICAL. DISTRIBUTION will have on the following: Components using D.C.
control power (i.e. breakers). (3S3.8)
References: 0-01-57B, Rev.74, Pf 9 of T 14
OPL171.037, Rev.8, pg 26 of 47
OPLl71 ,038,
Rev.14, pg 48 of 88
OPL171 .Q46, Rev.9, pg 13 of 22
A. Incorrect since the RHR Pump is not susceptible to this phenomena but it is powered
from "c" 4KV Shutdown Board.
B. lncorrect since the CS Pump is not susceptible to this phenomena but it is powered
from "c" 4KV Shutdown Board.
C. Incorrect since the "Bl" RHRSW Pump is powered from the 36 Diesel Generator via
3EC Shutdown Board. Plausible since all other components are related to "B".
5. Correct answer.
Browns Ferry Nuclear Plant 2004-304
SRO lnital Exam
The Unit 3 Operator is in the process of unloading the 3A EDG and placing it in the
standby condition. In accordance with 3-01-82, Standby Diesel Generator System,
step 8.1.16.2, the output breaker is tripped when the DIG reaches IOOKW and 100
WAR.
Which ONE of the following CAUTIONS is associated with completing this step without
tripping the BIG?
A! Failure to SLOWLY approach the 100KWI1OOKVAR limit may result in a reverse
power trip of the DIG.
B. operation of Diesel Generators at low RPM may result in a trip due to a low oil
pressure trip.
C. Continuous operation of Diesel Generators at loads below 550KW may result in e
Dieset Generator Timed Overcurrent trip.
D. Continuous operation of Diesel Generators at loads below 55OKW may result in a
Diesel Generator Differential Overcurrent trip.
_ _ _ _ .
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1
WA 264000 A2.09 Ability to (a) predict the impacts of the following on the
EMERGENCY GENERATORS (DIESEUJET); and (b) based on those predictions, use
procedures to correct, control, or mitigate the consequences of those abnormal
conditions or operations: Maintaining minimum load on emergency generator (to
prevent reverse power). (3.013.1)
References: OPL171.038, Rev.14, pg 29,38
3-01-82, Rev.73, step 8.1.16 (Caution)
3-08-82, Rev.73, step 3.18 (Trip Signals)
A. Correct answer.
5. Incorrect since the WPM of a loaded DG never changes from approximately 900
RPM.
C. Incorrect since operating the DIG at loads 4 5 0 KW may only result in soot buildup
in the exhaust piping.
D. Incorrect since operating the DIG at loads e550 KW may only result in soot buildup
in the exhaust piping.
Browns Ferry Nuclear Plant 2004-301
Sa0 lnital Exam
39. 264000K3 02 001/TZGl/fl)!G/C'A 3 914 OIBBF04301/RITCK
___
Unit 2 has experienced a loss of offsite power from 100% power. A11 diesels started
and tied to their 4KV Shutdown Boards except B (output breaker did not close). A
small leak has developed in containment with the following conditions present:
- Drywell Pressure
4.5 psig
- Reactor Pressure
800 psig
- Reactor Water bevel
60 inches
~
Loop I RHR is in suppression pool cooling
Which ONE of the following describes how "A" BG and "2A" RHR pump would respond
if water level decreased to -122" on LI-3-58 A&B?
I
A. D/G breaker remains closed and RHR 28 remains running.
B. Output breaker remains closed, RHR Pump 28 trips and starts back @ T = 7.
CY Output breaker would trip, WHW Pump 2A would trip and then restart @ T = 0 after
the output breaker recloses.
D. Output breaker would trip, RHR Pump 28 would trip and then restart @ T = 7 after
the output breaker recloses.
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WA 264000 K3.02 Knowledge of the effect that a [OS§ or malfunction of the
EMERGENCY GENERATORS (DIESEL/JET) will have on the following: A.C. electrical
distribution. (3.9/4.0)
References: OPL171.038, Rev.14, pg 47 and 48 of 80
Learning Objective #B6
A. Incorrect since Load Shed occurs when Rx Vessel level decreases to -122".
B. Incorrect since output breaker re-opens upon a load shed signal when Wx Vessel
level reaches -122".
C. Correct answer.
D. Incorrect since the 2 8 RWR Pump will start at T=O after the DIG output breaker
re-closes.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
40. 286000K1.07 001,T2G2//FiRE PROTECI'ION/MEM 2.8/2.9/N/BF04301iCK
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...
Unit 1 has experienced a loss of Plant Preferred concurrent with indications of a fire in
the Unit 1 DIG Building.
Which ONE of the following describes the operation of the CO2 System under these
conditions'?
A? Both COz Master Routing valves have opened to charge the distribution header
and Unit 1 DIG Building individual hazard control valve must be manually opened.
B. One C02 Master Routing valve has opened which does not charge the distribution
header but the Unit 1 DIG Building individual hazard control valve has automatically
opened.
C. Both CQ2 Master Routing valves have opened to charge the distribution header
and Unit 1 DIG Buiiding individual hazard control valve has automatically opened.
B. One C02 Master Routing valve has opened which does not charge the distribution
header and the Unit 1 5/G Building individual hazard control valve must be
manually opened.
KIA 286000 K1.07 Knowledge of the physical connections and/or cause-effect
relationships between FIRE PROTECTION SYSTEM and the following: A.C. power
supplies. (2.8I2.3)
References: QPb171.049, Rev.12, pg 30 and 31
A. Correct answer.
B. Incorrect since both CO2 Master Routing valves are de-energized which open them
and the Unita DIG individual valve must be manually opened.
C. incorrect since Unit f D/G individual valve must be manually opened.
D. Incorrect since both C02 Master Routing valves open upon Boss of Plant Preferred.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
4 1 . 2X60OOK3.0 1 00 I,'T2G2//FIRE/C/A
-
3.2/3.4/E,BFM30 1IRITCK
A fire rated door listed in Table 9.3.1 1 .E of the BFNP FIRE PROTECTION PLAN is
about to become impaired by propping the door open. There is no fire detection
equipment available to protect either side of the inoperabie door. The door is located
tn a contamination zone.
Which ON of the following is the MINIMUM action that must be taken to compensate
for this impaired fire barrier?
(Reference provided)
A. Establish a roving hourly fire watch to monitor the area until the door is restored to
an operable status.
B. If hot work is to be performed in either ofthe adjacent rooms, establish a
continuous fire watch on either side of the open door.
C I Establish a continuous/dedicated fire watch to monitor the impaired fire door area
until the door is restored to an operable status.
B. To reduce radiation exposures ALARA, establish a continuouslarea fire watch to
monitor the area at least once every 15 minutes until the door is restored to an
operable status.
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WA 286000 K3.01 Knowledge of the effect that a loss or malfunction of the FIRE
PROTECTION SYSTEM will have on the following: The ability to detect fires. (3213.4)
References: BFNP Fire Protection Report, Vol. 1 (Rev 09), Page 9.0-14,
and Vol. 2
(Rev 0002), Page 9 of 20.
A. This would be correct if fire detection and suppression were operable to protect one
B. This would be correct if fire detection and suppression were operable to protect both
C. (Correct)
B. The PLAN does not permit this option if the fire watch has to deal with a C-zone.
side of the door.
sides of the door.
Browns Ferry Nucsear Plant 2004-301
SRO lnital Exam
42. 288OOOK6.01 001,~PIGPIIYENTII,ATIONIMEM 2 7/2 7/B/BF04301/RTCK
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Which ONE of the following Combinations of electrical board losses would result in both
CREV units being inoperable? (Assume normal alignment and no board transfers)
A. 480V Shutdown Board 1 B; 4kV Shutdown Board 3EC
B. 480V Shutdown Board IA; 480V Shutdown Board 28
Cf 480V Shutdown Board 3B; 4kV Shutdown Board A
5. 4kV Shutdown Board B; 4kV Shutdown Beard 3EA
K/A 288000 K6.01 Knowledge of the effect that a loss or malfunction of the following
will have on the PLANT VENTILATION SYSTEMS: A.C. electrical. (2.4E.4)
References: OPL141.067,
Rev.11, Pg 28 of 60
Learning Objective #B2
A, B, and D. Incorrect since these do not meet the combination of power supplies for
the CWEV trains.
C. Correct since the power supplies are 480 VAC RMOV Board 38 for fan B and 480
VAC RMOV Board 1A for fan A which is supplied by 4KV Shutdown Board A.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
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43. 295001AA2.01 001/K161/PWIUFLOW MAP/C/A 333.8 UBF04301S/TCK
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Unit 3 is in the process of starting up. A 90% rod line has been established at 80%
KTP. Recirc Fow is currently being raised. A maintenance worker bumps a relay
which causes a trip of the 3B VFD. The operator notes the following conditions after
the pump trip:
I I
- MWE-500
- MWT = 1645
- Core Flow = 34%
~
OPRMs are INOPEWLE
Using lllustration d from 3-01-68, determine which ONE of the following describes the
appropriate action to take?
(Reference provided)
A. Region 2 has been entered, restart the 38 Recirc pump after verifying the Recirc
pump restart limitations.
B. Region 1 has been entered, scram the reactor immediately.
C: Region 2 has been entered, insert control rods to less than 66.7% rod line.
D. Region 1 has been entered, insert control rods to less than a 95.2% rod line.
I
Browns Ferry Nuclear Plant 2004-381
SRO lnital Exam
WA 295501 AA2.01 Ability to determine and/or interpret the following as they apply to
PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:
Powedflow map. (3.513.8)
Procedure 388-3.3.1 .I
.I, Rev.QQ02 pg 7 of 1.5
3-SR-3.3.1.1.1, Rev.0002 pg 8 of 15
3-SR-3.3.1 .I
.I, Rev.0002 Attachment 2
3-01-68, Rev.45 pg 6 of 96
A. Incorrect due to CAUTION in 3-SR-3.3.1.1 .I stating it is inappropriate to start a
Recirc pump to exit Region 2 or 3.
B. Incorrect because Region I
is not entered. If PowedFLow map is used incorrectly
and student reads flow at 85% power then Region 1 would be entered. Also, map
indicates that Reactor should be scrammed if enter Region I.
C. Correct answer. Per 3-SW-3.3.2.1 .I step 7.10.1 can use the option of inserting rods
to less than the 66.7% rod line.
D. Incorrect because Region 1 is not entered. If PowerFLow map is used incorrectly
and student reads Wow at 80% power then Region 1 would be entered. Also, if OPRMs
are Operable then could insert rods to less than 95.2% rod line.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
A startup of Unit 2 is in progress with no equipment out of service and Reactor power i!
currently 40%. The speed of both Recirc Pumps has just been raised to 30%.
A trip of Recirc Pump "2A" occurs and the operators respond to the transient per the
guidance in 2-AOl-68-18, "Recirc Pump PriplCore Flow Decrease" to stabilize the
plant.
Which ONE of the following describes the effect this has on Neutron Monitoring
instrumentation?
A. Flow compare alarm initiated by RBM, flow indicators indicate half the value
indicated on the recorders.
8. "M Recirc Loop flow indicators go to approximately zero, only APRM 1 and 3 flow
biased rod block and scram setpoints are lowered.
C I "A" Recirc Loop flow indicators go to approximately zero, all ARPM flow biased rod
block and scram setpoints are lowered.
D. APRM Flow Bias Off Normal alarm, all ARPM flow biased rod block and scram
setpoints are lowered.
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K/A 295001 AA2.02 Ability to determine andior interpret the following as they apply to
PARTIAL OR COMPLETE LQSS OF FORCED CORE FLOW CIRCULATION: Neutron
monitoring. (3.1132)
References: OPb1?1.148, Rev.?, pg 28-30 of 94
EnaMing Objective M I 0
A. Incorrect since the flow comparator alarm does not actuate and the Row indicators
shouId read the same value as the recorders.
B. Incorrect since all of the APRM's are affected.
6.
Correct answer.
D. Incorrect since the flow comparator alarm does not actuate and the Row recorders
should read the same as the indicators.
Browns Ferry Nuclear Plant 2004-301
SRO lnitai Exam
45. 295002M2.02 OOl//Tl GUMAIN TURBME/C/A
~ . . ~ ~ . ~ ~ ~ .
3.2/3.3,'NMF04301/SiTCK
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The Unit 2 Operator reports that Reactor Power is decreasing slowly. The Unit had
been operating at 50% RTP for the past couple of days. Upon investigation the
following parameters are observed:
- Generator Qutput
Decreasing slowly
- Reactor Pressure
Steady
= Recirc Flow
Steady
~ OffgasFlow
Decreasing slowly
Which ONE of the following conditions is the most likely cause of this situation?
A? Hotwell level high.
B. Loss of Feedwater Heating.
C. Control Valve failed closed.
D. RFP minimum flow valve failed open.
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K/A 295002 M2.02 Ability to determine and/or interpret the following as they apply to
LOSS QF MAIN CONDENSER VACUUM: Reactor power. (3.Z3.3)
References: 2-AWP-9-6A, Rev.16, Tile 6
A. Correct answer. Hotwell level going high causes a loss of condenser vacuum.
B. Incorrect since this would cause reactor power to increase due to colder water.
C. Incorrect since at 50% power the other controi valves should be able to handle the
load and reactor power would remain stable.
D. Incorrect since the min flow valve coming open would tend to affect reactor level and
generator output should remain the same.
Browns Ferry Nuclear Plant 2004-386
SRO lnital Exam
46. 295003AA2.02
.
0OIff lGl//ELEC!TRICAl, SYSTEM/C/A
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4.2!4.3/NBF0430
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I/R/TCK
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Unit 3 is at 38% RTP during a startup. Unit preferred is lost. The MMG set and 9-9
cabinets failed to transfer to alternate.
Which ONE of the following will occur due to this situation?
A. Loss of all automatic level control and level rises in response to xenon building in,
eventually tripping the reactor on high level.
i
E3. Pressure being controlled by the main turbine control system. If the turbine trips,
reactor pressure will require control by SRVs.
CY Reactor level control remains in automatic, however, automatic level setpoint
cannot be changed from the control room.
D. Master FWLC'system controller is lost. The control of RFPT is by governor only.
K/A 295003 AAZ.02 Ability to determine andlor interpret the following as they apply to
PARTIAL OR COMPLETE LOSS OF A.C. POWER: Reactor powerlpressureiand level.
(4.214.3)
References: 3-AOl-57-58, Rev.26, Pg 3 and 4 of 36
A. incorrect since automatic level control is not lost.
B. Incorrect since bypass valves can still control pressure.
C. Correct answer.
D. Incorrect since the governor is avaikable along with automatic control.
Browns Fer9 Nuclear Plant 2004-301
SRO inital Exam
47. 295004AK3 02 001iTlGTlDC SYSTEMMEM 3 1/3.5/N/BF04101/R/TCK
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Unit 2 has experienced a loss of the Unit Preferred. Region 2 of the PowerFlow map
has been entered. The Unit Supervisor has determined that control rods are required
to be inserted immediately.
Which ONE of the following describes the method and the reason for inserting control
rods?
A.' Insert a manual scram due to the loss of RPlS indication.
5. insert control rods in sequence using "Ernesg in" due to entry into Region 2 of the
Power/FIow map.
C. lnsert a manual scram due to the closure of 2-FCV-85-1 'l(NB), CRD Flow Control
Valve.
D. Insert control rods IAW the Emergency Shove Sheet due to the loss of RPlS
indication.
K/A 295004 AK3.02 Knowledge of the reasons for the following responses as they
apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Reactor SCRAM. (3.213.5)
References: 2-801-57-4, Rev.34, pg 4 of 24
A. Correct answer.
B. Incorrect since the control rods cannot be selected or moved manually.
C. Incorrect since manual scram is not directed for the closure of the CRB Flow Control
Valve.
D. Incorrect since the control rods cannot be selected or moved manually.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
-~
48. 295OO462.4.11 00 1lK I G 1 ELECTRICAL SY STEMMEM 3.413.6NBFM3O LlSiTCK
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Unit 2 is operating at 100% RBP when the following annunciators alarm:
~
- Battery Bd 3 BKR TRIPOUT
The RO reports that all previous illuminated annunciators have cleared. Also, the
affected annunciator panels will not test.
Which ONE of the following describes the actions that should be ordered by the Unit
Supervisor?
A. Take actions to transfer affected equipment to backup or standby systems.
B.* Dispatch personnel to locally monitor any affected equipment and stop all
surveillance activities being performed on affected systems.
C. Commence a Unit Shutdown within I
Hour due to entering TS LCO 3.0.3.
D. Take manual control of any systems associated with the above annunciators.
Request extra operators as necessary to monitor each affected panel.
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tVA 29500462.4.1 a Knowledge of abnormal condition procedures. (3.43.6)
References: 2-AOI-57-9 symptoms pgl and 3
A. Incorrect since it is undesirable to manipulate any systems until the annunciator
power is returned to normal.
B. Correct answer.
C. Incorrect since a 3.0.3 entry is not required.
D. Incorrect since taking manual control of systems is not required but monitoring those
systems is required.
Browns Ferry Nuclear Plant 2004-301
SRQ lnital Exam
49. 295005AA2.04
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00 1i.m 1 G l;RPS/CIA 3.7/3.8/BBF0430 1 iSiTCK
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Unit 2 is operating at 35% RTP. Turbine Bypass valves are being opened for a special
test. The following conditions currently exist:
- Bypass valves #1 and #2 are full open.
- Bypass valve #3 is 50% open.
- Total main steam flow is 35%.
- No other testing is in progress.
Which ONE of the following describes the response of the reactor if a Main Turbine trip
occurs at this time?
A,' Reactor scrams on high reactor pressure.
B. Reactor continues to operate at 35% power.
C. Reactor continues to operate and power decreases to 28%.
D. Reactor immediately scrams on Turbine Stop Valve 10% closure.
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%</A 295005 AA2.04 Ability to determine andlor interpret the folbowing as they apply to
MAIN TURBINE GENERATOR TRIP: Reactor pressure. (3.7/3.8)
References: 0PL171.028,
Rev. 13, Pg. 31
FSAR Section 11 5.3
Changed Rx power from 38% to 32%. Removed statement for turbine load at 23%.
A. Correct since bypass valves can only handle 25% load.
B. Incorrect since reactor pressure would increase due to bypass valves full open can
only handle 25% load.
C. Incorrect since power does not run back. This is also distracting because this is the
load at which the bypass valves can handle.
D. Incorrect since this scram signal is bypassed at <30% power based on first stage
pressure. With 3 bypass valves open this drops turbine load to 28% and these signals
are bypassed.
Browns Ferry Nuclear Plant 2004-301
SRQ lnital Exam
50
I 295005AK2.04 00 lfT 1 G 1 /,MAIN OENERATOIUMEM
.
3.3!3.3iN&3FM30 I/'RiTCK
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Which ONE of the following lists the automatic Turbine Trip signals that are designed
to protect the Main Generator?
A. electrical overspeed, reverse power, loss of condenser vacuum.
B. remote electrical trip, backup electrical overspeed, transformer faults (86 device).
6: reverse power, transformer faults (86 device), stator cooling low flow.
B. stator cooling high temperature, high vibration, electrical overspeed.
K/A 295005 AK2.04 Knowledge of the interrelations between MAIN TURBINE
GENERATOR TRIP and the following: Main generator protection. (3.3/3.3)
References: OPL171.135, Rev.5, Pg. ?5 of 44
OPLl711.010, WEV.11, Pg. 55-57 Of 90
A. Incorrect since eiecfrical overspeed and loss of main c~fldenser vacuum are
designed to protect the turbine.
B. Incorrect since backup electrical overspeed is designed to protect the turbine.
C. Correct answer.
D. Incorrect since high vibration and electrical overspeed are designed to protect the
turbine.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
Unit 2 was performing a rapid shutdown from 100% RTP due to a condenser vacuum
leak. The SRO ordered a manual Rx Scram when vacuum decreased to 23" vacuum.
The following conditions exist:
~
Reactor Pressure
Reactor Water Level
- Drywell Pressure
2.6 psig
- Condenser Vacuum
- Reactor Temperature
- Main Steam Relief Valves
980 psig increasing slowly
- -lo" increasing slowly
6" vacuum decreasing slowly
545°F increasing slowly
Cycled as necessary to maintain 800-1 000
Psig
The SRO orders a cooldown to be commenced per 2-GOI-100-12A, Unit Shutdown
from Power Operation to Cold Shutdown.
Which ONE of the following systems and optimum cooldown rates should be used to
obtain cotd shutdown conditions per 2-601-100-1 2A?
A. Condenser Bypass Valves at 25°F every 115 minutes.
$3. WPCl system in IMJECTION/REC%RCULTlON mode at 20°F every 15 minutes.
C. Core Spray in the REACTOR VESSEL MAKEUP mode at 25°F every 15 minutes.
DP Main Steam Relief Valves at 20°F every I 5 minutes.
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Browns Ferry Nuclear Plant 2004-301
SRQ lnital Exam
WA 295006 AK1 .OI Knowledge of the operational implications of the following
concepts as they apply to SCRAM: Decay heat generation and removal. (3.7/3.9)
References: 2-681-1 00-1 28, Rev.71, pg 35 of 70
A. Incorrect since condenser bypass valves are not available under current plant
conditions and cookdown rate exceeds the optimum rate of 20°F every 15 minutes.
B. Incorrect since HPC8 cannot be operated to attain cold shutdown conditions. It
isolates at 105 psig.
C. Incorrect since Core Spray cannot be operated in the injection mode under current
plant conditions and cooldown rate exceeds the optimum rate of 20°F every 15
minutes.
D. Correct answer. Optimum cooldown fate is 20°F every 15 minutes to prevent
exceeding the admin limit of 9Q"F per hour.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
A: Collapse in voids due to the scram.
B. Lowering of vessel level setpoint due to the scram which reduced feedwater Blow.
C. Lowering of reactor pressure due to turbine staying on line until it trips on reverse
power.
D. Reduced reactor water temperature due to steam still being drawn off the reactor b)
the pressure control system and house loads.
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Unit 2 is operating at 75% WTP when a spurious scram signal is received. Reactor
vessel level drops to -10 inches and is subsequently restored to +15 inches by the
feedwater system. The RWCU system isolated as expected.
Which ONE of the following explains why reactor vessel level initially dropped?
References: Plant experience
A. Correct answer.
B. Incorrect since vessel level goes far below the new setpoint and the collapse in voids
is immediate.
C. Incorrect since lowering pressure would tend to increase level.
D. Incorrect since the collapse in voids happens quicker than the lowering of reactor
water temperature.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
53.
.. 295009AA1.03 001/T1G2//RCIC/C/A
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3.4/3.5flr1BF04301flUTC#
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A loss of offsite power has occurred on Unit 2 with all associated Diesel Generators in
operation. The foBlowing conditions exist at this time:
~ Vessel Level
-30 inches
- Drywell Pressure
12 psig
- Torus Pressure
I 1 psig
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Reactor Pressure
450 psig
- TorusLevel
15 feet
Which ONE of the following is available to inject water to the vessel?
A: RCIC
B. "N Core Spray Pump
C. " A RHR Pump
D. "A" Main Feedwater Pump
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WA 295007 AAl.83 Ability to operate andlor monitor the following as they apply to
HIGH REACTOR PRESSURE: RCIC. (3.4135)
References: OPhZ 91.040,
Rev.17, System Description
A. Correct answer. Does not require power and is above low pressure isolation.
B. Incorrect since reactor pressure is above the discharge pressure of the pump.
C. Incorrect since reactor pressure is above the discharge pressure of the pump.
B. lncosrect since power is not available.
Browns Ferry Nuclear Plant 2004-301
SRO M a l Exam
54. 295008AK2.08 001/TlGZ/!MAIN 'TURBINE1MEM
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3.4/3.5,WBF04301/R/TUTCK
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Unit 2 is at 20% RTPduring a Reactor Startup. The Unit Operator controlling vessel
Bevel manually raises the running RFP speed too far and Reactor Water level increases
to +56 inches on the normal range instruments before being restored to normal.
Which ONE of the following lists the automatic actions that should have occurred?
B. Main Turbine and RFPT trip only.
CY RCIC, HPCI, Main Turbine and WFPT trip only.
D. RCK, HPCI, Main Turbine and RFPT trip and a Reactor Scram.
WA 295008 AK2.08 Knowledge of the interrelations between HIGH REACTOR
WATER LEVEL and the following: Main turbine. (3.4/3.5)
RefeFenCes: OPb171.010, Wev.1 I,
pg 55 of 90
Learning Qbjective #E37
OPL171.012, Rev.10, pg 71 of 68
OPb191.042, Rev.16, pg 44 of 70
A. Incorrect since reactor water level at 55" also trips the turbine and the WFP's.
B. Incorrect since reactor water level at 55" also trips HPCI and RCIC.
C. Correct answer.
D. Incorrect since reactor high water level is not a Reactor Scram signal. The Scram
comes from the Turbine Trip signal but is bypassed at this low of a level.
Browns Ferry Nuclear Plant 2004-304
SRO lnital Exam
~. 5%. 295008G2.1.7 001/flYG2/MSIV/C/A
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3.7/4.4/B/BFM301/S/TCK
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Unit 2 scrammed from high Drywell pressure with the following conditions present:
Reactor pressure
920 psig
Reactor water level
Drywell pressure
3.8 psig
Feedwater pumps
running
HPCl injecting
5000 gpm
RClC in standby
+ 53 inches and increasing
Which ONE of the following describes the action to be taken and the reason for the
action?
A. Trip and lock out HPCl only to prevent moisture carryover into the steam lines.
B. Take manual control of HPCl and reduce flow to prevent reaching feedwater high
level trip setpoint.
C. Take manual control of HPCl and Feedwater pumps to prevent overflowing the
main steam lines while pressurized.
D. Trip and lock out HPCI and trip Feedwater pumps to prevent violating MCPR and
LHGR during a feedwater controller minimum demand failure.
WA 295008 G2.1.7 Ability to evaluate plant performance and make operational
judgments based on operating characteristicslreactor behaviodand instrument
interpretation. (3.714.4)
References: OPL171.003 Wev.45 pg 26 and 27
Enabling Objective QPLl71 .003 B#7
A. Correct answer. HPCI above hi level trip.
B. Incorrect since you dont take manual control of HPCl when above hi level trip
setpoint.
C. Incorrect since you dont take manual control of HPCl whm above hi level trip
setpoint.
D. Incorrect since the reason for tripping the equipment is to prevent exceeding MCPR
and LHGR limits during a feedwater controller failure to maximum demand.
Browns Ferry Nuclear Plant 2004-30a
SRO InitaI Exam
56. 295009AK1.03 001/TlG2!/RECIRC SYSTEWMEM 2.7/2.7iNIBF04301MCK
.
.
.
~
~
~
~
~
~
.___~
..
Which ONE of the following interlocks exist to protect the Jet Pumps from a loss of Net
Positive Suction Head?
A. Recirc Pump speed limited to 20% untiK total Feedwater Flow exceeds 29%.
B. 75% Limiter actuates an automatic runback if any individual RFP Wow is 49% and
vessel low level alarm actuates.
C I Automatic Recirc Pump runback to 28% if total Feedwater Flow drops below 19%.
B. End of Cycle Recirc Pump Trip is actuated upon a Turbine Trip or Load Reject.
.~
~~~~~~. .___
%(/A 295009 AK1.03 Knowledge of the operational implications of the following
concepts as they apply to LOW REACTOR WATER LEVEL: Jet pump net positive
suction head. (2.7/2.7)
References: QPLl71.007, Rev.20, Pg 48 and 49 of 11 7
A. Incorrect since Recirc Speed is not limited to 20%. It is limited to 28% which would
make this answer also correct.
B. Incorrect since this protective action is provided to reduce reactor power within the
capacity of the remaining RFP.
C. Correct answer.
D. Incorrect since this protective action is needed at the end of life to quickly lower
reactor power upon a load reject or turbine trip.
Browns Ferry Nuclear Plant 2004-302
SRO lnital Exam
Unit 2 was maintaining 80% RTP when the Operator notes the following conditions:
- constant positive reactor period
- main steam line flow decreases on E main steam line
- reactor water level increases
~ APRMs begin to increase
~ Torus temperature increasing
Which ONE of the following is the most likely cause of the above conditions?
A. B turbine Control Valve failing to the full open position.
B. inadvertent operation of Safety/Relief valve PCV 1-18.
C. E Recirc pump speed increasing.
D! lnadvertent HPCI operation.
-
.-
WA 295014 AA2.03 Ability to determine andlor interpret the following as they apply to
INADVERTENT REACTIVITY ADDITION: Cause of reactivity addition. (4.CV4.3)
References: 2-AOI-1-1
I Relief Valve Stuck Open, Wev.22, pg 1 of 8
FSAR section 4.4.
A. Incorrect since this would not cause Torus temp to increase.
8. Incorrect since this would not cause reactor power to increase.
C. Incorrect since this would not cause torus temp to increase.
D. Correct answer since cold water is causing Rx power to increase. Also, Main steam
line flow for E line would decrease since HPCl taps off prior to flow element.
Browns Feny Nuclear Plant 2004-301
SRO lnital Exam
~-
58. 2950 15AA2.0 1 ..
00 l/.m 1 G2EOI CONTROLiMEM
.... ~ ~ ~ ~ . ~ . . .
4.2/4.3/NIBFO43O
VSff
. . ~ ~ ~ ~ ~ ~ ~ ~ ~ . .
CK
.~
Unit 3 has received a Reactor Scram signal and 01-1 has been entered. The SRO is
executing the RClQ ieg and needs to determine if the Reactor will remain subcritical
under ail conditions without boron.
Which ONE of the following conditions will satisfy the requirement of remaining
subcritical under all conditions without boron?
A. All control rods inserted to position 00 with the exception of one control rod at
position 86 and one control rod at position 08.
B. IRMs are on Range 3 with a negative 80 second period.
C! All control rods inserted to or beyond position 02.
B. Shift Manager has determined that the reactor will remain subcritical under the
current conditions.
~
.~
K/A 295015 BA2.01 Ability to determine and/or interpret the following as they apply to
INCOMPLETE SCRAM: Reactor power. (4.2/4.3)
References: EO/-1, RPV Control, Note 1
A. Incorrect since 2 rods are not inserted to at least position 02 or beyond. Only one
control rod is allowed to be stuck out.
B. Incorrect since this doesnt mean that ail rods inserted to or beyond position 02.
C. Correct answer.
D. Incorrect since Reactor Engineering must make this determination.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
59. 2950 1 6AK3 .O 1 00 liT 1 G1 //CR ABANDONMENT/~M4.1/4.~,WB)F~30
.....
~ ....
l/RECK
..
. . . .
The Shift Manager has determined that the Unit 3 Control Room must be abandoned.
A Reactor Scram has been inserted in accordance with 3-AOI-100-2, Control Room
Abandonment, Immediate Action step 4.1 2.
Which ON of the following is the reason for inserting a manual scram prior to
evacuating the control room?
A:' Actions are taken to minimize inventory loss from the reactor until control outside
the control room can be established to bring the plant to a cold shutdown condition.
B. This ensures the control of reactor power, pressure and level is established from
outside the control room within 20 minutes.
C. This prevents fission product barrier damage by establishing the ability to control
critical parameters from outside the control room.
D. It places the unit in a lower mode quicker than waiting until an operator is stationed
at the backup controls.
KIA 295016 AK3.01 Knowledge of the reasons for the following responses as they
apply to CONTROL ROOM ABANDONMENT: Reactor SCRAM. (4.1/4.2)
References: EPIP-I I Rev.30, Pg 160 and 162 of 207
3-801-10Q-2a. Rev.15, Pg 4 of 80
A. Correct answer. This includes the bottling up of the reactor until a cooldown can be
started.
B. incorrect since scramming the reactor does not ensure the 20 minutes is met. The
procedure is written (3-AOI-200-2a) to ensure the 20 minute time limit is met.
C. lncorrect since the reactor scram prior to leaving the control room does not prevent
this. Maintaining the critical parameters within their critical band does this function.
D. Incorrect since the reactor scram is not based on getting to a lower mode quicker.
Browns Ferry Nuclear Plant 2004-301
SRO lnita! Exam
60.
295017AK1.02 001!TlG2//EPIP/MEM 3.8/4.3/NiBF04301/RTCK
.. . .
An off-site release is in progress on Unit 3 and the CECC is not staffed.
Which ONE of the following is the LOWEST Emergency Classification which requires
the SED to make Protective Action Recommendations for the general public?
I
A. Unusual Event
B. Alert
C. Site Area Emergency
8): General Emergency
-
-
K/A 29504 7 AK1.02 Knowledge of the operational implications of the following
concepts as they apply to HIGH OFF-SITE RELEASE RBTE: Protection of the general
public. (3.W4.3)
References: PIP-5, Rev.23, Pg. 6 of 12
A, B, and C are incorrect since PARS are not required to be made by the SED until a
General Emergency is declared.
D. Correct answer.
Browns Ferry Nuclear Plant 2004-301
SWO lnital Exam
61. 295018AA2.04 001/KIG1!CCWiC/A
..... ~ . ~ ~ . . ~ . .
2.9/2.9/N/BFC4301/SXTCK
. .
.
....
Unit 2 is operating at 80% RTP. The following alarms are received shortly after taking
the shift:
- DRYWELL EQPT DR SUMP TEMP HIGH
- RWCU NON-REGENERATIVE HX DISCH TEMP HIGH
- DRYWELL PRESSURE ABNORMAL
Which ONE of the following conditions is the most likely cause of these alarms?
A. Trip of an RWCU pump.
B.* Trip of an RBCCW pump with a failure of 2-FCV-7048 to close.
C. RBCCW Heat Exchanger TCV fails open.
I
1
D. Loss of Drywell Coolers.
K/A 295018 M2.04 Ability to determine andlor interpret the following as they apply to
PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: System flow.
(2.9129)
References: 2-AOI-70-1, Rev.21, Pg. 1 and 2 of 8
A. Incorrect since a trip of the RWCU pump should not cause the Drywell Eqt sump
temp to increase or the Drywell Temp to increase. Immediate action of AOI is to trip
the RWCU pumps.
B. Correct answer. Loss of RBCCW flow will cause all these parameters to increase.
C. Incorrect since the TCV failing open should cause all these temps to decrease.
B. Incorrect since the loss of Drywell Coolers will not increase RWCU NRHX outlet
temps but it may cause the increase in the other parameters.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
62. ZYS018G2.4.10 001fT1 ........
Gl//CCWK!/A
~~~~~.~
3.0/3.1/N,BFM301WiCK
. .
Unit 2 has just experienced a loss od416Q VAC Unit Board 2A.
Which ONE of the fotfowing is the primary cause for receiving alarm "CN5R A NS
WATER BOX LEVEL LOW, 2-ARP-9-20A, on panel 9-20?
A. Sensor malfunction.
B. Vacuum Priming System malfunction.
61 "2A" CCW Pump tripped.
..
WA 295018 (32.4.10 Knowledge of annunciator response procedures. (3.0/3.?)
References: 2-ARP-9-20A alarm #8
OPb171.050, Rev.12, pg 15 of70
A. Incorrect since a more likely cause with the conditions given is that the " A
pump has lost power.
B. Incorrect since a more likely cause with the conditions given is that the "A" CCW
pump has lost power.
C. Correct answer. "A" CCW pump is powered from 4160 VAC Unit Board A
5. Incorrect since loss of condenser vacuum does not affect water box Bevel. Water
box level could have an affect on condenser vacuum.
Browns Ferry Nuclear Plant 2004-301
SWO lnita! Exam
63. 295019AA1.04 001XlGl/~KNSTRUMEhT AIRiMEM
.
. . . . . 3.3i3.2B/BF04301!~CK
..
.
~.
.
..
Unit 2 Control Air pressure has been decreasing slowly for the past hour.
Which ONE of the following describes the operation of Service Air Cross-tie to Control
Air Valve, O-FCV-33-1?
Opens at .......
A. 45 psig and remains open.
B. 65 psig and closes at 10 psig.
C. 75 psig and remains open.
D! 85 psig and closes at 30 psig.
-
-
KIA 295019 MI .04 Ability to operate andlor monitor the following as they apply tu
PARTIAL 88 COMPLETE LOSS OF INSTRUMENT AIR: Service air isolation valves.
(3.3/3.2)
References: 2-AOI-32-2, ATTACHMENT 1, SECTION 7.1, Rev.23
A. hxrrect since this is the pressure at which the MSlV's will get a closed signal if
control air pressure is iost instantaneously.
B. Incorrect since this is the pressure at which the Unit 2 to Unit 3 Control Air Crusstie,
2-pcv-03%-3901, will close.
C. Incorrect since this is the pressure at which the CAD tank A nitrogen will supply
2-FSV-64-20 and 21.
D. Correct answer. The added pressure for closing is there since most valves fail as is
on a loss of pressure but this one will re-position if the pressure gets too low.
Browns Ferry Nuciear Plant 2004-304
SRQ lnital Exam
Unit 2 is at full power with both RWCU pumps tagged out of service. An MSlV poppet
becomes disconnected and closes causing a Group 1 isolation and a trip of both Recirt
Pumps.
Which ONE of the following is the correct operator response to these conditions
including the reason for the action@)?
A. Verify WWCU isolation valves open, perform Recirc Pump restart limitations SR,
and restart a Recirc Pump to avoid stratification of reactor vessel.
B. Initiate RClc for level control, control pressure with s!?Vs 800-1000#, and reopen
MSlVs to establish main condenser as a heat sink to ensure containment integrity is
not compromised.
C. Initiate HPCI in INJECTBONIWECIRC mode for pressure and level control to avoid
cladding damage due lo overheating.
D I Reset reactor scram, initiate cooldown as soon as possible to prevent violation of
PT curve for bottom head temperature.
._
.... ~ ~ ~ ~ . ~ . .
- . .
...
K/A 295020 G2.4.11 Knowledge of abnormal condition procedures. (3.213.6)
References: 2-AOl-$OO-l Rev.76
A. Incorrect since WWCU system has no flow. SR cannot be performed.
B. Incorrect since MSlVs not open does not threaten containment.
C. Incorrect since cannot perform pressure and level control at the same time.
B. Correct answer.
Browns Feny Nuclear Plant 2004-301
SRO Inital Exam
6s. 295021AA1 .I4 OOlff lGI//SIIJTDOUN COOLINGiCiA 3.7/3.7/NWFO4301ntTC#
_ _ _ . ~ . . . . .. .. .
. ... .-
Unit 3 is in Mode 4 and has been shutdown for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> with Shutdown Cooling in
service using RHR System I. Both Recirc pumps are off.
Which ONE of the following is NOT a viable method that can be used for alternate
decay heat removal if Shutdown Cooling is lost?
A l Place Auxiliary Decay Heat Removal (ADHR) in service with all available heat
exchangers in service.
B. Place Unit 2 RHR loop in setvice, CROSS-TIED with Unit 3, for Shutdown Cooling.
Shift Manager approval is required.
C. Raise RPV level to +80 inches and maintain a band of +70 to +90 inches. Increase
monitoring frequency of reactor coolant temperature.
D. Increase RWCU flow rate to maximum AND maximize RWCU blowdown.
__
..
__
WA 295021 AA1.04 Abihty to operate and/or monitor the following as they apply to
LOSS OF SHUTDOWN COOLING: Alternate heat removal methods. (3.713.7)
References: 3-AO8-74-1 I Rev.10, pg 5,7,and 8.
Tech Spec Bases 3.4.8 ACTIONS A.7
A. Correct answer. Unit required to be in Mode 5 with gates removed.
8, C and D. Incorrect since this is a method pes 3-A08-74-1.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
66. 295022AK3.02 -. 001/TlG2/!CRD!MEM
.-
2.9/3.lNE3F04301/CK
.
Unit 2 is operating at 50% RTP with the "2A" CRD pump out-of-service. A fault occurs
in the motor of the "1 B" CRB pump which causes it to trip.
Which ONE of the following is the reason CWD graphitar seak may be damaged?
A. Loss of Drive water pressure.
B.' Loss of Cooling water ROW.
C. Inability to open the scram outlet valve during a scram.
D. The index tube expands and causes excessive friction on the seals.
.
-
-.
K/A 295022 AK3.02 Knowledge of the reasons for the following responses as they
apply to LOSS OF CRD PUMPS: CRDM high temperature. (2.913.1)
References: OPL171.006, Rev.7, Pg 38 and 44 of 72
A. Incorrect since Drive water pressure does nothing for the seals.
5. Correct answer since this causes seals to increase in temperature and this is why
there is a 350°F temperature limit.
6.
incorrect since the scram outlet valve is air operated.
8). Incorrect since the index tube does not interact with the graphitar seals.
Browns Ferry Nuclear Plant 2004-301
SRO lnitai Exam
Fuel loading is in progress. As a fuel assembly is lowered into the core the CR
operator observes SRM counts rising and verifies SRM period lights illuminated. The
CR operator immediately notifies the Refuel Floor personnel of the indications.
Which ON of the following actions should be performed immediately?
A. Stop the fuel movement and evacuate the Refuel Floor.
B. Notify the SM & RX engineer for directions concerning an inadvertent criticality.
CY Remove the fuel assembly from the core ti if criticality is still confirmed, then move
fuel assembly away from core to the cattle chute and evacuate the Refuel Floor.
B. Remove the fuel assembly from the core 8 if criticality is still confirmed, then move
the assembly to the SFW least populated rack location with grapple latched and
evacuate the Refuel Floor.
_ _
-
WA 295823 AKI .03 Knowledge of the operational implications of the following
concepts as they apply to BEFUELING ACCIDENTS: Inadvertent criticality. (3.7/4.0)
References: 2/3-AOl-79-2, sections 4.1.3 and 4.1.4, Rev.11.
A. Incorrect since this is the action if withdrawing a control rod.
B. Incorrect since this is a subsequent action and not an immediate action.
C. Correct answer per 4.1 3.3.
D. Incorrect since this is the action to take if reactor can be determined to be subcritical.
Browns Ferry Nuclear Plant 2804-301
SRO Inital Exam
68. 29502462 4 1 001XlGl//EOI CONTROL/C/A 4.3/4.6,B/E3FW30iMCK
~
-
..
Unit 3 reactor has scrammed and EOI-1 has been entered due to low water level
caused by a malfunction of the FWLCS. One control rod indicates position 14.
Subsequently, a leak develops in the Brywell causing pressure to increase to 2.6 psig.
Which ONE of the following describes the appropriate actions to take 7
Enter 81-2 and:
A. Continue in EOLl
Execute c-5
B! Re-enter EOi-1
Execute 3-AOI-100-1
C. Continue in EQI-1
Execute RClQ
D. Re-enter 01-1
Execute C-5
-
~
K/A 295024 62.4.1 Knowledge of EOP entry conditions and immediate action steps.
(4.314.6)
References: EOI-1, Rev.5
A. Incorrect since a new entry condition has been exceeded which requires re-entry
into EQ8-1. Also, C5 is inappropriate at this time since only 1 control rod is out.
B. Correct answer. Per the RC/Q leg the reactor is subcritical and no boron Ras been
added so the override is in effect.
C. Incorrect since a new entry condition has been exceeded which requires re-entry
into 01-1.
8). Incorrect since C5 is inappropriate at this time due to only 4 control rod is out.
Browns Ferry Nuclear Plant 2084-304
SRO lnital Exam
I
Unit 3 has scrammed due to a Group 1 isolation. The " A Main Steam bine has failed
I
to isolate and radiation levels in secondary containment are increasing. The following i
conditions exist:
~
HPCl Room
MAX normal exceeded
~
RB EL 565 W
MAX normal exceeded
- RB EL 621
MAX safe exceeded
Which ONE of the following actions are required per EQI-3, Secondary Containment
Control?
A. Enter EOI-1, RPV Control and rapidly depressurize with the SRVs.
BP Enter EOI-1, RPV Control and rapidly depressurize the RPV with the Main Turbine
Bypass Valves.
C. Enter C-2, Emergency RPV Depressurization and open all ABS valves.
B. Enter EOI-3, Secondary Containment Control and transition to GOI-IBO-l2A, Cold
Shutdown.
..
-
-
-
.-
WA 295825 G2.3.10 Ability to perform procedures to reduce excessive levels of
radiation and guard against personnel exposure. (293.3)
References: EOI-1, Rev.5
EOI-3, Rev.8
C-2, Rev.4
A. Incorrect since cannot use SRVs to rapidly depressurize.
B. Correct answer per the override in EOI-1
C. Incor~ed
since Emergency Depressurization is not required until 2 Max safe
conditions exist.
D. Incorrect since this transition is made only if emergency depressurization will not
reduce discharge into the secondary containment. This is not the case.
Browns Ferry Nuclear Plant 2004-302
SRQ lnital Exam
70. 295025G2.3.11001iTIGl/iEACTOR
~...
-
PRESSUREhIEM 2.7/3.2M/BF04301/RiTC~K
Which ONE of the following is the reason Tech Specs require all 3 trains of SBGT to be
A. All three trains are required to ensure negative pressure in the reactor building post
LQCA.
B. Two trains are required to ensure negative pressure in the reactor building and one
train is required to vent the drywell to ensure offsite releases are controlled post
LQCA.
CY Two trains are required post LQCA to ensure offsite rad releases are maintained
within 10CFR100 limits even considering a single failure of the third train.
8. One train is required for each unit in operation to ensure offsite and onsite releases
are controlled post LQCA. This will ensure control room habitability and protection
of the public.
-
-
..
WA 295025 62.3.1 1 Ability to control radiation releases. (2.7/3.2)
References: EQI-1, RPV Control
EO!-2, Primary Containment Control
A. Encorrect since 2 trains are required.
3. Incorrect since 2 trains are required for offsite release and not negative pressure.
6.
Correct answer.
D. Incorrect since 2 trains are required and secondary containment is not unit specific.
Browns Ferry Nuclear Plant 2004-301
SRO M a l Exam
A leaking SRV has caused Suppression Pool temperature to increase from 85°F to
100°F. All Tech Spec required actions are being taken.
Which ONE of the following describes the indications that would be observed by the
operator for this change in temperature?
A! Drywell pressure would increase.
B. Suppression chamber level would decrease.
@. Drywell temperature would increase.
D. Suppression chamber temperature would decrease.
-
-
WA 295026 EK2.05 Knowledge of the interrelations between SUPPRESSION POOL
HIGH WATER TEMPERATURE and the following: Containment pressure. (3.013.3)
References: Thermal Hydraulics
A. Correct answer due to the expansion of the Torus water. Pressure would increase
and back up water into the downcomers.
B. Incorrect since level would increase due to the higher temperature of the water.
C. Incorrect since the SRV goes under the torus water level. This would not affect
Dryweli temperature.
D. Incorrect since Suppression Chamber temperature would increase due to the
leaking SRV.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
7%. 295028EA1.04 001iTlGl~/FRIMARY CONTAMENTC/A
-
3 914 OiNiBF04301RTCK
-
-
A Small Break LOCA has occurred on Unit 2 with the following conditions present in
the Drywell and Torus:
- Drywell Pressure
- Drywell Temperature
~ TorusLevel
5 psig and stable
275°F and increasing slowly
16 ft and stable
~
Recirc Pumps
off
- Drywell Blowers
Off
If Drywell Sprays were initiated under these conditions, which QNE of the following
consequences would most likely be the result?
(Reference provided)
A. Water from the Torus would be drawn into the Drywell through the DW-to-Torus
vacuum breakers.
3:
Breach of Containment on negative pressure due to exceeding the capacity of tR
DW-to-Torus vacuum breakers.
C. Damage would occur to the DW Blowers,therefore, they should not be started
under any circumstances.
D. LOCA size would increase due to the thermal shock of the relatively cool water
being sprayed into containment.
5rowns Ferry Nuclear Plant 2004-301
SRO lnital Exam
WA 295028 AI .04 Ability to operate andlor monitor the following as they apply to
HIGH DRYWELL TEMPERATURE: Drywell pressure. (3.9/4.0)
(Provide copy of Curve 5, BW Spray Initiation Limit)
References: EOP Basis Document
A. Incorrect since the water level is below 18 feet.
3. Correct answer.
C. Incorrect since DW coolers may be initiated under other conditions such as
containment temperature still high but sprays not necessary.
D. Incorrect since the water going out the leak will prevent the colder water from the
sprays getting to the piping.
Browns Ferry Nuclear Plant 2004-301
SRO Inital Exam
73. 29502XEA2.02 001!~~1Gl/CONTAI~ENT/CiA
3.4/3.7/NjBF04301/SICK
.
A steam Beak has occurred inside the Unit 3 Containment. The following conditions
exist at this time:
- Drywell temperature
- Drywell pressure
- Reactor pressure
- Torus temperature
- Torus level
~
MSlVS
350°F
28 psig
950 psig steady
260°F
29 ft
open
Which ONE of the following actions is required with regards to reactor pressure at this
time?
A. Commence a cooldown using the Bypass Valves at el00"FIHr.
B. Immediately lower reactor pressure using Bypass Valves to 700 psig to stay within
the Heat Capacity Temp Limit.
C? Emergency Depressurize the reactor per C-2, Emergency RPV Depressurization.
D. Maintain reactor pressure in a band of 808-1000 psig.
WA 295028 EA2.02 Ability to determine andlor interpret the following as they apply to
HIGH DRYWELL TEMPERATURE: Reactor pressure. (3.8/3.9)
References: EOI-2, Primary Containment Control
EOI-1, RPV Conttd
C-2, Emergency RPV Depressurization
A. Incorrect since Drywell Temperature cannot be maintained below 160°F. With Torus
level above 18 ft this requires Emergency Depresslerization.
B. Incorrect since the Heat Capacity Temp Limit is not being challenged at this time.
C. Correct answer.
D. Incorrect since conditions exist which require Emergency Depressurization. This
pressure band is normally given per EOl-1 which is in effect long enough to get to
Emergency Depressurization through the override.
Browns Ferry Nudear Plant 2004-304
SRO lnital Exam
.... 74. 295030EAZ.01 001,TlGlilTORUSiCIA 4.1~4.2iX/BF043011WTCK
..
.. . .. -
~~~ -
Unit 3 is commencing a Startup from an outage with Reactor Power at 3% RTP. The
Drywell and Suppression Chamber are de-inerted at this time.
Which ONE of the following requires the earliest entry into Tech Spec Actions for
Suppression Chamber Water Level?
(Reference provided)
A. -5.5 inches
B. -6.5 inches
CP -7.5 inches
D. -8.5inches
-
..
WA 295030 EA2.01 Ability to determine and/or interpret the following as they apply to
LOW SUQPKESSION POOL WATER LEVEL: Suppression pool level. (4.1/4.2)
References: Tech Spec section 3.6.2.2
A. Incorrect since this level is bounded by the initial conditions of Dp not established
and level band of
-7.25 inches.
B. Incorrect since this is still not an entry into Tech Spec Actions since the band is
-9.25 inches.
C. Correct answer since it is outside the level band of > -7.25 inches.
D. Incorrect since the previous answer is the earliest entry into Tech Specs.
Browns Ferry Nuclear Plant 2004-301
SRO Inital Exam
75. 29503 1 EK2.0 1 00 UT 1 G lI!INSTIPITMENTATIONiC/A
...- ~
~
~
~
~
~
-
~
.
.
... 4.4/4.4iNiBF0430
-
1 RiTCK
..
. ~ . ~ ~ . ~ ~ ~ ~
A leak has developed on the variable leg side of the narrow range reactor vessel level
instruments.
Which ONE of the following describes the effect this will have on the indicated level
and why?
Indicated level will be
the transmitter.
A,' lower; higher
B. higher; lower
C. lower; lower
D. higher; higher
than actual levei due to a
Dp signal from
..~~~~~....
. .
......
. ..
WA 295832 %U2.01
Knowledge of the interrelations between REACTOR LOW WATER
LEVEL and the following: Reactor water level indication. (4.414.4)
References: OPL171 .OK$ Wev.15, Pg 18 of 61
Enabling Objective #B1
A. Correct answer.
B. Incorrect since the Dp get higher and this causes the instrument to read lower.
C. Incorrect since the instrument reads lower at a higher Dp.
D. Incorrect since the instrument reads lower at a higher Dp
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
__
76. 29503 1 G2.2.23 00 I!/
1 C 1 /LEVEL IWSTRUMENTATIOICYA 2.6/3.RIN!BFM30 IISITCK
_. -
~.
. . . ~ ~ ~ ~
.... ~.
..
Unit 2 is at 100% power. The following sequence of events occurred involving the
instrumentation associated with RPS Function #4, Reactor Vessel Water Level-bow,
Level 3: (Note: RPS Trip capability not affected.)
- 0800
- 1680
- 2480
- 0300
Trip System A instrument declared lNOP
Trip System B instrument declared fNOQ
Trip System A instrument declared OPERABLE
Trip System B instrument declared OPERABLE
Which ONE of the following describes the most limiting REBUlRED ACTION and
associated COMPLETION TIME that was applicable during the above sequence of
events?
(Reference provided)
A. Place one channel in trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
B. Place channel in one trip system in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
C. Be in MODE 2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
DI Be in MQDE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,
Browns Ferry Nuclear Plant 2004-301
SWO lnital Exam
WA 295031 G2.2.23 Ability to track limiting conditions for operations. (2613.8)
Provide references for TS 3.3.1 .I
and Table 3.3.4.1-1
References: Tech Spec section 3.3, RPS Instrumentation
Tech Spec table 3.3.1.1-1, RPS Instrumentation
A. Incorrect since the Trip System A instrument was INOP >I2 hours condition G
applies which requires the unit to 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 />.
B. Incorrect since the Trip System A instrument was INOP > I 2 hours condition G
applies which requires the unit to 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 />. This requirement was
applicable for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
C. Incorrect since Condition F does not apply under these conditions.
8). Correct answer. Trip System A instrument has been lNOP for greater than 12
hours. Condition G now applies which requires the unit to be in MODE 3 within 22
hOUfS.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
B. Post as a High Radiation Area with a barrier preventing entry to the area.
C:' Post as a Locked High Radiation Area and continuously guard or lock the entrance.
D. Post as a Very High Radiation Area and lock the entrance. RADCON Manages
I
I
must approve the RWB for entry.
77. -
29503362 3.1 001X162/iRAD CON'FROLSMEM 2.6/3.0/nTB)I;04301/R/TCK
._
~
A radwaste discharge has created a hot spat whish produces 1.2 RemlHr at 30
centimeters. Rad Protection needs your help to determine the proper controls for the
area.
Which ONE of the following describes the required controls for this situation?
A. Post as a Radiation Area and label the hot spot.
K/A 295033 G2.3.2 Knowledge of 10 CFR:20 and related facility radiation control
requirements. (2333.0)
References: RCI-17, Rev.40, Pg 2,3 and 6 of 44
A. Bncorrect since the hot spot exceeds the limits for Locked High Radiation Areas.
B. Incorrect since the barrier must be continuously guarded or locked. This condition is
for hot spots 4 .O RemlHr at 30 centimeters.
C. Correct answer.
19. incorrect since this is for a Very High Radiation Area and this does not meet those
limits of >5OQ Rads"
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
78. 295037EK1.02 001/TlGl//EOI CONTRQL!C/A .....
4.1/4.3/TYElF04301flUTCK .
...
_- ......................
. . .
An ATWS has occurred on Unit 2. The following plant conditions exist:
- SLC tank level
55%
- Reactor power
4%
- Reactor water level
- HP injection systems available
- Suppression Pool temperature
I A 2 T
- Reactor pressure
- 1 SRV open for pressure control
-40 inches
888 and slowly lowering
If reactor power starts to slowly rise, which ONE of the following actions is required to
be performed ?
A. Continue to monitor power level until SLC tank is at 43%. If power is still increasing
then lower level to -18% inches.
B. Evaluate the reactor power rise. If power continues to rise, then Bower level to at
least -162 inches.
C? Evaluate the reactor power rise. If power is above 5%, then lower RPV level to at
least -50 inches.
D. Determine if Reactor power can be lowered below 5%. If not, then Emergency
Depressurization is required.
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Browns Ferry Nuclear Plant 2004-304
SRO hital Exam
WA 295037 EKI .Q2 Knowledge of the operational implications of the following
concepts as they apply to SCRAM CONDITION PRESENT AN5 REACTOR POWER
ABOVE W R M 5OWN§CALE 5 W UNKNOWN: Reactor water Bevel effects on reactor
power. (4.1143)
References: C-5 Rev.6
A. Incorrect since lowering level does not depend on amount of SLC injection. Also,
level is fowered to -50 inches per step C5-11.
B. Incorrect since power rising above 5% with RWL at -40 inches requires level to be
dropped to -50 inches per step 65-1 I.
The -162 inches is referenced in step C5-6.
6. Correct answer per step (3-14.
B. Incorrect since Emergency Depressurization is required only if level cannot be
restored and maintained above -185 inches.
Browns Ferry Nuclear Plant 2004-301
SRQ M a l Exam
79. 295037G2.2.22 OOl!,TlGl!SAFETY ._
LIMITSICiA 3.4/4.lflrllnF04301!SiTCK
. . . .
.
-.1
...
Unit 2 experienced a catastrophic seal failure on the 28 Recirc Pump. The following
conditions exist at this time:
- Reactor Power
- Reactor Pressure
- Drywell Pressure
~ Total Core Flow
8%
MCPRvalue
1.01
28% and steady
99Q psig (cycling from 8 0
to 131 5 psig)
44 psig and steady
- Rec'src Pumps
Off
- Mode Switch Position
Shutdown
- Reactor Water Level
- Control Rods are being inserted manually.
-1 52 inches (intentionally lowered)
Which ONE of the following Tech Spec Safety Limits has been exceeded?
A. MCPR.
B. Reactor Water bevel,
6. Reactor Steam Dome Pressure.
D! Reactor Thermal Power.
. . . ~ ~ ~ ~ ~ . ~ .
...~~~~...
.. .
..
WA 295037 G2.2.22 Knowledge of limiting conditions for operations and safety limits.
(3.4/4.A )
References:
Tech Spec section 1 .I,
Table I .I
-1, Modes
Tech Spec section 3.4.10, Reactor Steam Dome Pressure
Tech Spec section 2.1 I Safety Limits
Tech Spec section 3.1.4, Control Rod Scram Times
A. Incorrect since core Blow is <IO%..
B. Incorrect since water level remains above TAF.
C. Incorrect since pressure does not exceed 1325 psig.
D. Correct answer.
Browns Ferry Nuclear Plant 2004-301
SRO Bnital Exam
.. 80. 295038EKI ... .02 ~l/TlGl//TL4D
. -
RELEASEMEM 4.2/4.4/73/BF04301/RCK
.......
~
. ..
Following core damage, an unisolable steam Beak in the Turbine Building requires
declaration of a General Emergency due to the Boss of three fission product barriers.
The crew is executing E.81-4, Radiation Release Control. Field surveys and Off-Site
dose projections are being performed.
Which ONE of the following describes when Emergency Depressurization is required to
be initiated?
A. Immediately, since a General Emergency was declared.
B. If two or more areas in the Turbine Building exceed their maximum safe operating
temperature limits.
C. lf two or more areas in the Turbine Building exceed their maximum safe operating
radiation limits.
D I If the Off-Site release rate approaches or exceeds the Emergency Action Level for
a General Emergency.
WA 295038 EK1.02 Knowledge of the operational implications of the following
concepts as they apply to HIGH OFF-SITE RELEASE RATE: Protection of the general
public. (4.2M.4)
References: EOI-4, Radiation Release Control
A,B,C - Incorrect since they do not meet the requirements per 01-4. If an unisolabk
leak was in the Reactor Building and two max safes were reached then this would have
required an Emergency Depressurization.
B. Correct answer.
Browns Ferry Nuclear Plant 2004-301
SRO M a l Exam
8 1 . 3OOOOOK5 .O 1 00 IiT2G IIIINSTRLJMENF
..
.
.
~
~
~
~
~
~
~
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AIWCiA 2.5/2.5/NBFO43O 1 !R/TCK
. . . .
. . .
A transient has occurred on Unit 2 which resulted in RMOV Board 2A being
de-energized for 6 seconds. The following conditions exist concerning the control air
system:
- Control Air Backup Controller is in service due to primary controller f a h e .
- 480 Shutdown Board 1A is out-of-sewice for planned maintenance.
~ Control Air pressure is 94 psig and dropping very slow[y (suspected leak)
~
Compressor controls: G comp - Modulate
C comp
~ Third bead
Acomp
~
Standby
Bcomp - Standby
B comp - Second Lead
Which ONE of the following describes the current condition of the control air
compressors?
A. Compressors G and B running loaded.
5. Compressors A, B and C running loaded.
C: Compressors B and C running loaded.
B. Compressors B, C and D running loaded.
~.
-
~
K/A 300000 K5.01 Knowledge of the operational implications of the following concepts
as they apply to the INSTRUMENT AIR SYSTEM: Air compressors. (2.5125)
References: OQL171.054,
Wev.9, pg 19,20,21 and 24.
A. Incorrect since the G compressor will not auto-restart aRer 4 seconds of being
de-energized.
B. Incorrect since the A compressor doesnt have a power supply.
C. Correct answer. B compressor starts and loads @ 97.5 psig and C compressor
starts and loads @ 94.5 psig.
B. Incorrect since D compressor doesnt get a start signal until 91.5 psig.
Browns Ferry Nudear Plant 2004-301
SRO lnital Exam
. .
.__
82. 400000K4.01 00IiT2Gl//RAW COOLING
-.
WATEWC/A 3.4/3.9,N!BF04301/CK
-.
..
.. ..
Unit 3 is experiencing Raw Cooling Water (RCW) header pressure fluctuations from 45
psig to 60 psig which have caused the automatic operation of the 3E RCW Pump.
Listed below is the start and stop times of the 3E WCW pump.
- initial start
08:30 am
- stoptime
0935 am
- subsequent start
09145 am
~ stop time
1O:OO am
Which ONE of the following is the earliest time that the 3E RCW pump would start if
another automatic start signal is received?
A. Immediately.
B. 10:30 am.
CI 11 :00 am.
D. 11:30am
~
K/A 400000 K4.01 Knowledge of CCWS design feature@) and/or interlocks which
provide for the following: Automatic start of standby pump. (3.4/3.9)
References: OPL171.048, Rev.?, pg 15 -l?
of 25
Enabling Objective #5
A. Incorrect since the first run time was >30 minutes and the second run time was 4 0
minutes then the pump is prevented from starting for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from the time the second
run was stopped.
B. Incorrect since the first run time was >30 minutes and the second run time was a30
minutes then the pump is prevented from starting for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from the time the second
run was stopped.
e. Correct answer.
D. Incorrect since the first run time was >30 minutes and the second run time was e30
minutes then the pump is prevented from starting for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from the time the second
run was stopped.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
83. 600000AK2.04
. . . ~ . . ~ ~ ~ . ~ ~ ~ ~ ~
OOl?TlGl//FIRE/C!A 2.5/2.6!B!BF04301/R,TCK
..
. . .
Due to a fire in the turbine building, all electrically driven fire pumps automatically
started. While the fire pumps were running, a loss of 161 KV and 500W offsite power
occurred. The EDGs then started and powered their respective shutdown boards.
Which ONE of the following describes how the fire pumps become available to fight the
fire?
A. No operator action is required; the pumps will automatically restart after the busses
are reenergized by the EBGs.
B. Ensure the diesel driven fire pump is running; the motor driven fire pumps must
remain load shed from the EDGs.
61 Place the NORMALEMERGENCY switch for the associated fire pumps to
EMERGENCY and back to NORMAL; pumps will start automatically.
8. Place the NORMALEMERGENCY switch for the associated fire pumps to
EMERGENCY and back to NORMAL; manually start the pumps at the associated
pump breakers.
~ ~.
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.
K/A 600000 AK2.04 Knowledge of the interrelations between PLANT FIRE ON SITE
and the following: Breakers/retays/and disconnects. (2.5/2.6)
REF: OPLI71.074, Rev. 6, Page 11
O-AOI-57-1A, Rev. 0041 Page 6
A. Incorrect since the logic has to be reset for the fire pumps to automatically restart.
B. Incorrect since the fire pumps are directed to be loaded onto the DG if a fire
conditions exists.
6.
Correct answer.
D. Incorrect since the fire pumps will automatically restart after the logic is reset.
Browns Ferry Nuclear Plant 2004-301
SRQ M a l Exam
Unit 3 is shutting down for a scheduled refueling outage. The HPCl system Steam
bine Qutboard Isolation valve, 3-FCV-073-0009, needs an LLRT performed to
determine if work is required to be added to the outage. The Work Control Center
notifies you (the Unit Supervisor) that personnel are standing by to perform the LLRT.
Current plant conditions are as follows:
~
Mode Switch position
Shutdown
- Reactor Temperature
400°F
- Reactor Pressure
235 psig
- Cooldown Rate
50"FIHr
Which ONE of the following actions should the Unit Supervisor take to support the
Work Control Center?
A. Isolate HPCl in preparation for the LLRT. Notify Work Control Center that the LLRT
may commence immediately.
B. Isolate HPCl and enter LCO 3.5.1
~ Notify Work Contmol Center that the LLWT may
commence immediately.
CY Notify the Work Control Center that the LLRT can start in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Have the LLRT
team standby.
D. Notify the Work Control Center that the LLRT cannot start for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Have the LLRT team standby.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
K/A 62.1.12 Ability to apply technical Specifications for 58 system. (2.9/4.0)
References:
Tech Spec 3.5.1, $9 3.5-1
Tech Spec Bases 3.6.1.3, Pg B 3.6-18, B 3.6-21
Tech Spec Bases LCQ 3.0.2, Pg 3 3.0-2, B 3.0-3
A. Incorrect since HPCl should not be isolated while it is in a Mode where HPCI is
required to be OPERABLE. Cannot isolate for Operational Convenience per LCO 3.0.2.
5. Incorrect since HPCl should not be isolated while it is in a Mode where HPCl is
required to be OPERABLE. Cannot isolate for Operational Convenience per LCO 3.0.2.
C. Correct answer. HPCI is not required to be OPERABLE with reactor pressure below
150 psig. With a moldown rate of 5O"FIHr then in1 hour reactor pressure will be below
150 psig.
D. Incorrect since you don't have to wait 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. LCQ 3.6.1.3 is still met with the HPCl
isolation valves closed and deactivated.
Browns Ferry Nuclear Plant 2004-301
SWO M a l Exam
85. 62. I. 16 .~
001~r3NCOMMUNICATION§~~M
~ ~ . ~ ~ . .
-. ~ ~ ~ ~ ~ . . .
2.9/2.#,BiBFM3Ol
... !?UTCK
. .~
~..
. . . ~ ~ ~
An Alert has been declared. The Shift Manager has directed you, as the Unit 1
Operator, to activate the Automatic Paging System (APS). You determined that the
AQS system did not respond.
Which ONE of the following is the correct method for notifying the Emergency
Responders?
A. Assemble a team to notify everyone on the duty list by telephone.
B:' Call the OB§ and have APS activated from Chattanooga.
C. Call the E$ staff to activate APS from the Local Recovery Center.
D. Have the EP staff or the ODS notify Emergency Responders by telephone.
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. ....
WA (32.1 .I
6 Ability to operate plant phonelpaging systemland two-way radio. (2912.8)
References: Bank question. Needs to be verified by utility.
B. Correct answer.
A,C and D. Incorrect since procedure directs answer B.
Browns Ferry Nuclear Plant 2004-301
SRO M a l Exam
86. ~2.1.22 001rr3/IMonE OF OPERATIONICIA
-. . ~ . S ! ~ . ~ I M ' B ~ ~ O ~ I R , T T C K
. .
. . . . .
. -
Which ON OB the following sets of plant conditions satisfies the definition for being in
MODE 3 per Tech Specs?
A! A normal shutdown has just been completed. Moderator temperature is
480 O F . The MSlVs are closed. The mode switch is in "Shutdown".
B. Preparatjons are in progress for a reactor startup. AB1 control rods are fully inserted
with the mode switch in "Shutdown". Moderator temperature is 180 "F.
C. The reactor is shutdown. Moderator temperature is I35 "F. The Mode Switch is in
Start/Hot Stby position during Mode Switch testing.
B. The reactor is subcritical on Range 4 of the lRMs and lowering. Moderator
temperature is 200 O F . The MSIVs are dosed for repairs to a steam line drain
valve. The mode switch is in "Start/Hot Stby".
~. -
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WA (32.1 22 Ability to determine Mode of Operation. (2N3.3)
References: Tech Spec Table 1.2-1
A. Correct answer since temperature is >212"F.
B. Incorrect since these conditions are applicable to Mode 4.
C. Incorrect since these conditions are applicable to Mode 5.
D. Incorrect since these conditions are applicable to Mode 2.
Browns Feny Nuclear Plant 2004-301
SRO lnital Exam
Which ONE of the following describes the purpose and function of the TIP Shear
Valves?
A. Provides an automatic emergency means to seal the TIP guide tube should the
guide tube leak with the TIP probe extended and unable to be retracted. The shear
valve cuts the cable and closes off the guide tube.
3: Provides a manual emergency means to seal the TIP guide tube should the guide
tube leak with the TIP probe extended and unable to be retracted. The shear valve
cuts the cable and closes off the guide tube.
C. Provides the normal means to seal the TIP guide tube should the guide tube leak
with the TIP probe extended and unable to be retracted. The shear valve is held
closed by a fail-safe spring.
D. Provides a manual emergency means to seal the TIP indexer should the indexer
leak nitrogen. The shear valve closes off the index mechanism for the leaking Tip
guide tube.
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K/A G2.1.18 Knowledge or the purpose and function of major system components and
controls. (3.2/3 3)
References: OPkl71.023 Rev.4 pg 10 and 1 1
ERabling Objective OPL172.023 I32
A. Incorrect since the shear valve does net operate automatically.
B. Correct answer.
C. Incorrect since the shear valve is not a normal means to isolate the guide tube.
D. Incorrect since the shear valve does not isolate the index mechanism.
Browns Ferry Nuclear Plant 2004-301
SRQ lnital Exam
88. G2.1.4 001!/T3LINIT STAFFING!C/A
....
~~ ...- 2.3/3.4/PIIBF04301/SiTCK
...~
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-. .
The Browns Ferry Units are in the following conditions:
- Unit 4
~
Unit 2
- Unit 3
Core verification in progress after initial fuel load
15% power performing a reactor startup
Mode switch in Shutdown with temp at 312°F following a scram
Which ONE of the following meets the Tech Spec minimum requirement for
non-licensed operators on shift?
A. 2
B. 3
C. 4
DP 5
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WA G2.1.4 Knowledge of shift staffing requirements. (2.3/3.4)
References: Tech Spec 5.2.2, Unit Staff
A. Incorrect since all 3 units have fuel in the vessel which requires one NbO and since
one control room has a unit in mode 1 then another NLO is required.
B. incorrect since all 3 units have fuel in the vessel which requires one NLO and since
one control room has a unit in mode 1 then another NLO is required.
C. Incorrect since all 3 units have fuel in the vessel which requires one NLQ and since
one control room has a unit in mode 1 then another NLO is required.
D. Correct answer
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
89. (32.2.1 1 001/T3//TEMPORARY ALTERATION/C/A 2.5/3.4/B/WF04301/WgCK
.
. ... .
Which ONE of the following situations would require that a Temporary Alteration
Control Form (TACF) be initiated per SPP 9.5?
A. Leads for a common alarm are being lifted to support maintenance under a
clearance.
B. A keylocked test switch for a system will be placed in an abnormal position to allow
troubleshooting.
CI A small leak on the WHW suction piping from the Torus that has been patched per
an approved work implementing document.
B. Some of the valves in a system must be placed in positions that are not in
accordance with the valve checklist.
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WA G2.2.11 Knowledge of the process for controlling temporary changes. (2.5B.4)
References: SPP 9.5, Temporary Alterations, Wev.6
A. Incorrect since this Is covered under a clearance for maintenance.
B. Incorrect since this is covered under troubleshooting.
C. Correct answer.
D. Incorrect since the system is not being changed.
Browns Ferry Nuclear Plant 2004-30'l
SRO lnital Exam
Which ONE of the foilowing is responsible for the overall control and coordination of
the Operations Surveillance Testing program?
A? Operations Manager
B. Plant Manager
C. Operations Superintendent
D. Unit Manager
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K/A 62.2.1 2 Knowledge of surveillance procedures. (3.Q13.4)
References: OPDP-5, Rev.3, Section 3.t
Updated titles lo the new procedure.
A. Correct answer.
B. Incorrect since the Operations Manager is responsible for the Qperations
procedures.
C. Incorrect since he is not responsible for the "overall" program.
B. Incorrect since he is not responsible for the "overall" program.
Unit 3 is in a Refueling Outage with a 24 month Group 2 $CIS surveillance in progress
The Test Director assigned to coordinate the surveiilance is in the control room
monitoring the test when the SGT system receives an actual Auto Start signal. The
Test Director stops the surveiilance until the conditions that caused SGT to auto start
are corrected.
Which ONE of the following describes the actions the Best Director must perform to
complete the surveillance?
A. Discard the surveillance test that was interrupted and repeat the surveillance from
the beginning.
B.' Re-verify the Initial conditions with Operations and ensure equipment performance
will not be jeopardized by completing the remainder of the procedure.
C. Verify with Operations that they are able to support the remainder of the
surveillance test and continue the surveillance by re-performing the last step that
was completed and continuing until the test is complete.
B. The Test Director and Operations can review the procedure to verify all of the
Acceptance Criteria is met. If the Acceptance Criteria is met then the surveillance
can be signed off as complete.
._
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%</A (32.2.14 Knowledge of the process for making configuration changes. (2.1/3.0)
Reference: SPP-8.1 Rev.2 Pg 9 and 12
OPLl74.078 Rev.ll Pg 14
Enabling Objective OPL171.078 #I311
A. Incorrect since the previous procedure is not discarded.
B. Correct answer.
C. Incorrect since the Test Director and Operations must re-verify the initial conditions
prior to restarting the test and there is no direction to repeat a step.
D. Incorrect since the surveillance cannot be signed off as complete until all steps are
completed or N/Ad.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
92.
(32.2.3 001/T3//LJNIT DEFF'ERENCES,MMEM
. _ 3.1/3.3~~F04301/R/TCK
-
_ _
Which ONE of the following describes the Reactor Protection System Instrumentation
functions applicable to Unit 1 only?
A,' Main Condenser Vacuum - Low
Low Scram Pilot Air Header Pressure
B. Main Condenser Vacuum ~ Low
Scram Discharge Volume Water Level - High (Float Switch)
C. Low Scram Pilot Air Header Pressure
Scram Discharge Volume Water bevel - High (Float Switch)
D. Turbine Control Valve Fast Closure, Trip Oil Pressure - Low
Low Scram Pilot Air Header Pressure
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K/A G2.2.3 Knowledge of the design/procedural/and operational differences between
units. (3.213.3)
References: FSAR section 7.2.3.6
item 10.
A. Correct answer.
B, C and D. incorrect since these functions are applicable to Unit 1 along with the
other 2 units.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
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93. G2 2.30 OOl/T3/FFUEL POOWMEM 3.5/3.3BBFQ4301,WR/TCK
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While off-loading fuel bundles from the reactor, alarm 3-XA-78-51, FUEL POOL
SYSTEM ABNORMAL, is received in the control room with a report that fuel pool level
is decreasing uncontrollably.
Which QNE of the following describes a method available from the control room to add
water to the fuel pool in accordance with the above alarm procedure?
PI.'
Start a condensate pump and inject to the reactor vessel to maintain fuel pool Bevel.
B. Open emergency makeup supply valve from EECW to the fuel pool to maintain
level.
C. Align fuel pool cooling and cleanup heat exchanger RBCCW supply to the fuel pool
to maintain level.
B. Gravity drain the CST, to the main condenser hotwell, then inject to the reactor
vessel with condensate booster pumps.
SUA G2.2.30 Knowledge of RO duties in the control room during fuel handling such as
alarms from fuel handling arealcommunication with fuel storage facility1systems
operated from the control room in support of fueling sperations/and supporting
instrumentation. (3.513.3)
References: 3-ARP-9-4C, alarm 3-XA-78-51 Rev.20
3-A0l-78-1, Rev.10, pg 3 of 4 1
A. Correct answer.
3. Incorrect since this function requires local actions outside the control room.
C. lncssrect since this requires local actions outside the control room.
D. Incorrect since this requires local actions outside the control room.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
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94.
G2.3.11 001A"3!XAD REIEASEMEM
-. 2.4/3.2/NBFQ43Ql/CK
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Unit 2 is operating at 100% WTP when the following aEarms are received:
- OG POST TWTMT RADIATION HIGH (2-XA-55-42, Window 33).
- OG POST TRTMP RADIATION HIGH-HIGH (2-XA-55-4C, Window 34).
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OG POST TRITMT RAD MONITOR HI-HI-HI/INOP (2-XA-554C, Window 35).
The Operator immediately reduced core flow to 55% and inserted a manual Reactor Scram. After 10 minutes, Qffgas Post Treatment indicator 2-RR-90-265 is still reading
greater than 5 ~ ~ 0 6 c p s .
Which ONE of the following actions should be taken for these conditions?
A. Immediately commence a cooldown to cold shutdown, not to exceed a cooldown
rate of 100"FIHr.
B. Place standby SJAE into operation per 2-01-66, Off-Gas System, step 8.4.
CY Close all the MSIV's and Main Steam Line drains, 2-FCV-1-55 and 2-FCV-1-56.
D. Commence purging the Off-Gas System per 2-01-66, Off-Gas System, step 8.2.
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K/A G2.3.11 Ability to control radiation releases. (2.7/3.2)
References: 2-AOI-66-2, Rev.16, pg 2 and 3 of 4
A. Incorrect since the unit does not have to be cooled down for this procedure. It is an
option that the Shift Manager could take but it would not be related to this condition
specifically.
B. Incorrect since placing on another SJAE is not appropriate. Could be considered
reasonable to Rusk more steam through the piping.
C. Correct answer.
D. Incorrect since the AI0 does not reference purging the Off-Gas system but it does
have direction lie, start more dilution fans.
Browns Fer9 Nuclear Plant 2004-301
SRO lnital Exam
95. G2.3.9 001liT3lCONTAINMENT/C:A
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2.S/3.4/E/EF04301/CK
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Unit 2 startup is in progress with the following conditions existing:
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Reactor Power
10% RTP
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Reactor Pressure
920 psig
- Mode Switch Position
START/HQT STBY
- Containment is being inerted.
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Purge filter fan is in service.
Which ONE of the following describes the results of placing the Reactor Mode Switch
to the RUN position?
A. Initiates a Group 6 $CIS isolation unless Bypass switches are placed in BYPASS
on panel 9-3.
B!' Automaticaiiy closes ail valves required for inerting with the purge filter fan unless
Bypass switches are placed in BYPASS on panel 9-3.
C. Autornaticafly closes ail valves required for inerting with the purge filter fan unless
the DrywellTTorus Bypass switch on panel 9-3 is taken to Torus position and any
SGT fan is running.
D. Automatically closes the drywell and suppression chamber exhaust isolation valves
unless the DrywelllSuppression Chamber Train A/B Vent keybock switches are
positioned to DRYWELL.
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WA G2.3.9 Knowledge of the process for performing a containment purge. (233.4)
References: OPha71.032 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.
6.
Incorrect since the DrywellTTorus bypass switch on the 9-3 panel is the incorrect
switch.
D. Incorrect since placing the DrywelllSuppression Chamber Train AIB Vent keylock
switches to the DRYWELL position does not preveflt valve movement.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
96.
G2.4.1 OOlIIT3EOI CONTROLICIA 3.0I3.7/B/BF04301/SITCK
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Unit 2 has experienced a Rx scram due to a loss of Feedwater. bevel has decreased
to -10 inches and is being restored by RClC manual initiation. Due to a partial loss of
drywell cooling, the Drywell Temperature reached 172°F before being reported to the
sao.
Which ONE of the following i5 the correct action?
A. Enter EOI-1 and inhibit ADS; Enter 08-2 and initiate Drywell Sprays.
B. Enter C-I
~ Alternate bevel Control and inhibit ADS.
C I Enter EOI-1 and control level +2 to +50 inches; Enter EOI-2 and initiate all available
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drywell cooling.
B. Enter EOI-2 and initiate Suppression Chamber Sprays.
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K/A (32.4.4 Knowledge of EOP entry conditions and immediate action steps. (4.314.6)
References: EO!-I I RPV Control, Rev.10
EOI-2, Primary Containment Control, Rev.8
6-1, Alternate bevel Control, Rev.7
A. Incorrect since you don't get far enough into EOI-1 to inhibit ADS and D w e l l
Temperature is not high enough to initiate Drywell Sprays.
B. Incorrect since Bevel is being restored so it doesn't get low enough to enter 6-1.
C. Correct answer.
D. Bncorrect since YOU do not initiate Suppression Chamber Sprays for high drywell
temperature.
Browns Ferry Nudear Plant 2004-303
SRQ lnital Exam
A small feedwater leak has occurred on Unit 3 concurrent with a loss of off-site power.
The reactor scrammed OR RPV low level with the following conditions present 15
minutes after the event:
- RPVLevel
- RPV pressure
1050 psig
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Drywell Pressure
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Drywell Temperature
4 85°F
~ All D E S started and loaded as designed
- A I rods fully inserted
-90 inches lowering slowly
3.1 psig steady
Which ONE of the following EQl's is the highest priority with the appropriate
cantingency procedure?
A. EQI-1, RPV Control with SBLC from the boron hank per Appx 7s.
B. EQI-2, Primary Containment Control with Suppression Chamber sprays per Appx
17C.
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C:
EOI-I , RPV Control with RCIC from CST if possible pes ~ p p x
5 ~ .
B. EQI-2, Primary Containment Control with Drywell sprays per Appx 178.
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Browns Ferry Nuclear Plant 2004-301
SRO InitaI Exam
K/A 62.4.1 6 Knowledge of EOP implementation hierarchy and coordination with other
support procedures. (3.0/4.0)
References: EO!-1, RPV Control
EQI-2, Primary Containment Control
A. incorrect since RClC has not reached its initiation signal yet then it must be started
before moving onto the next step.
B. Incorrect since the RPV level C O R ~ ~ O ~
takes precedence since no injection sources
into the vessel yet. HPCl failed to start and a loss of all AC has stopped all other
injection sources at this time. Conditions are met SO that Suppression Chamber sprays
can be started at this time.
C. Correct answer. RClC must be started prior to answering the question whether level
can be maintained above 92 inches. It doesnt have an initiation signal yet.
D. Incorrect since EOI-1 takes precedence. Conditions arent met to start Drywell
sprays.
Browns Ferry Nuclear Plant 2004-301
SRO Inital Exam
98.
G2.4.22 OOl//T3,EOI
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. __ CONTROLIMEM 3.O!~.O,~~F04301!SiCK
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EOI-I, RPV Control, RC1Q leg directs the operators to reduce Recirc Pump speeds to
minimum prior to tripping them if Rx Power is above 5%.
Which ON of the following is the bases for this action?
A. To minimize power oscillations that may result from tripping Recirc Pumps at higher
speeds.
BI To prevent tripping the turbine on high water level and exceeding the capacity of
the bypass valves.
C. To allow time for AWI to actuate thus allowing the Recirc Pumps to stay in operation
for coolant circulation.
B. To prevent RPV level from reaching -+ 2 inches as a result of tripping Recirc Pumps
at higher speeds and initiating PCIS.
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WA 62.4.22 Knowledge of the bases for prioritizing safety functions during
abnormallemesgency operations. (3.014.0)
References: QPLl71.102, Rev.6, Pg 61 and 62 of67
A. Incorrect since a rapid power reduction is required at this time.
B. Correct answer.
C. Incorrect since every means possible is used to reduce reactor power regardless of
how long it takes ARI to actuate.
B. Incorrect since tripping the recirc pumps causes swell, not shrink.
Browns Ferry Nuclear Plant 2004-301
SRO lnital Exam
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99. G2.4.44 OOl//T3/PAWS/C/A 2.1/4.O/N/BF04301/S/TCK
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Unit 2 has declared a General Emergency. An off-site airborne release is in progress
with the following information from the Off-site Dose Assessment Team at the 5 mile
point:
reading of 4.9E-6 micro Cilcc of lodine 131
reading of Q.5 Remihr External Dose
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projected to reach 0.8 REM PEDE
Which ONE of the following Protective Active !?ecomMendations is appropriate for
these conditions?
(Reference provided)
A. Evacuate 2 mile radius AND Shelter 5 miles downwind.
B. Evacuate 2 mile radius AND Sheiter remainder of 10 mile EFT.
C. Evacuate 2 mile radius and 5 miles downwind AND Shelter remainder of 10 mile
EPZ.
D: Evacuate 2 mile radius and 10 miles downwind AND Shelter remainder of 10 mile
EPZ.
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WA G2.4.44 Knowledge of emergency plan protective action recommendations.
(2.1/4.0)
Keferences: EPIP-5, Rev.29
A. Incorrect since doesnt address evacuation of downwind sectors and sheltering
should be 10 miles away.
B. incorrect since doesnt address evacuation downwind.
C. Incorrect since release the limits per Attachment C have exceeded the 5 miBe PAG
limits of Gable 1. This is the action to take if the limits have not been exceeded.
D. Correct answer since the reading of 4.E-6 micro Cikc of lodine 131 exceeds the
limit in table 1 of reading of 3.E-6 micro Cilcc of Iodine 131.
EM 4.014
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Browns Ferry Nuclear Plant 2004-302
SRO lnitai Exam
BF04301flUTCK
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Unit 1 is defueled and Unit 2 is operating at 75% RTP. There is dense smoke in the
control room which requires abandonment of the entire area. The foollowing is a list of
immediate actions to be performed on Unit 2:
1 ) Trip Reactor Feedwater Pumps.
2) Reduce core Row to between 50-60%.
3) Depress Reactor Scram A and B pushbuttons.
4) Trip Reactor Recirc Pumps.
5) Obtain hand-held radios from the Controi Room.
6) Place Reactor MODE Switch in SHUTDOWN.
7) Check all eight Scram Reset lights extinguished.
8) Verify Main Turbine tripped.
9) Check control rods fully inserted.
10) Proceed to Backup Control Panel 2-25-32.
Which ONE of the following is the correct order to perform these actions?
(Note: All of the actions may not be listed)
A. 2,6,4,7,9
B. 3,8,4,5,10
D. 3,6,7,1,4
WA G2.4.49 Ability to perform without reference to procedures those actions that
require immediate operation of system components and controls. (4.0/4.0)
References: 2-AQI-100-2, Rev.48, pg 4 and 5 of 83
A. Incorrect since the Recirc Pumps shouid be tripped after the control rods are verified
inserted.
B. Incorrect since the Resirc Pumps should be tripped before the Turbine is tripped.
6.
Correct answer.
D. Incorrect since the Recirc Pumps should be tripped before the Feedwater pumps.