ML090690060
| ML090690060 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/04/2009 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML090690060 (79) | |
See also: IR 05000327/2009301
Text
ES.-401 Site-Specific RO Written Examination Form ES-401-7
Cover Sheet
u.s. Nuclear Regu.latoryCommission
Site-Specific RO Written Examination
Applicant Information
Name:
Date: 02/04/2009 Facility/Unit: Sequoyah 1 & 2
Region: I D II ~ III D IV D Reactor Type: W IZI CE D BW D GE D
Start Time: Finish Time:
Instructions
Use the answer sheets provided to document your answers. Staple this cover sheet
on top of the answer sheets. To pass the exam*ination, you must achieve a final grade
of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.
Applicant Certification
All work done.on this examination is my own. I have neither given nor received aid.
Applicant's Signature
Results
Examination Value Points
Applicant's Score Points
Applicant's Grade - - - - - Percent
1/2009 SequoyahRO NRC Exam
2/4/2009
1. Given the following:
Unit 2 was at 60% power when a reactor trip occurred as a result of an
inadvertent Train "A" Feedwater Isolation Signal.
- After the plant was stabilized, the OATC observed the following on
Annunciator Panel 2-XA-55-4D, "Reactor First Out":
LS-3-97B, "8TM GEN LOOP 3 LEVEL LOW-LOW REACTOR TRIP"
window lit and NOT flashing.
- "P-9 TURBINE TRIP REACTOR TRIP" window flashing.
Which ONE of the following identifies the ca*use of the reactor trip and the
status of the Reactor Trip First Out Panel?
A. The reactor tripped due to the turbine trip;
The Reactor Trip First Out panel has been acknowledged, but NOT reset.
B. The re*actor tripped due to the turbine trip;
The Reactor Trip First Out panel has NOT been acknowledged and theSG
Low-Low level window came in after the reactor trip occurred.
c. The reactor tripped due to the SG low level;
The Reactor Trip First Out panel has been acknowledged, but NOT reset.
D. The reactor tripped due to the SG low level;
The Reactor Trip First Out panel has been acknowledged and the P-9 Turbine Trip
Reactor Trip window ca*me in after the panel was acknowledged.
Page 1
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2/4/2009
2. Given the following:
- Unit 2 operating at 1000/0 steady-state power.
- A Pressurizer safety valve fails partially open resulting in the crew
initiating a manual Reactor Trip and Safety Injection.
- The crew observed the following post-trip indications:
- Pressurizer pressure: 1820 psig and lowering
- Pressurizer level: 53% and rising
- PRT pressure: 45 psig and rising
Given the above conditions, which ONE of the following annu"nciatorswoul"d
ci.~
indicate~
J.J.. \1o~1\1
leak was occurring in addition to the leaking safety valve?
A. TS-68-309 PRESSURIZER RELIEF TANK TEMP HIGH
B. XS-68-363 PRESSURIZER RELIEF VALVE OPEN
c. MS-30-241 LOWER COMPTMOISTURE HIGH
D. LS-68-335D/E PRESSURIZER LEVEL HIGH-LOW
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2/4/2009
3. In accordance with AOP-R.05, "ReS Leak and Leak Source Identification", which ONE
of the following changes in containment conditions discriminates between a small
break LOCA and a steam line break inside containment?
A. Radiation
B. Humidity
C. Pressure
D. Temperature
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2/4/2009
4. In accordance with A.OP-R.04, "Reactor Coolant Pump Malfuncti'on", which ONE of the
following identifies the LOWEST temperature on the Reactor Coolant Pump lower
bearing, that if exceeded would require tripping the #1 RCP?
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1/2009 Sequoyah RO NRC Exam
2/4/2009
5. Given the following:
- Unit 2 is operating at 100 % power.
- The crew entered AOP-R.05, "RCS Leak and Leak Source Identification".
- The crew is re-establishing charging flow in accordance with EA-62-5,
"Establishing Normal Charging and Letdown".
- RCP sea"1 injection flows areas follows:
~-
9.2 gpm 10.5 gpm 11.9 gpm 13.4 gpm
Which ONE of the following identifies the adjustment needed to 2-FCV-62-89, "Seal
Water FCV" and the effect it will have on charging flow through the Regen Heat
Exchanger?
2-FCV-62-89 needs Charging Flow to the
to be throttled Regen Heat Exchanger WILL
A. OPEN Increase
B. OPEN D"ecrease
C. CLOSED Increase
D. CLOSED Decrease
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2/4/2009
6. Given the following:
Unit 1 has been shutdown and a cooldown is in progress.
Tavg is currently 220°F.
- Current RCP status is:
- 1 #2 #3 #4
Off "but Running Off & Off &
availa"ble tagged tagged
- All S/G levels are between 28 - 34% narrow range.
- The operating crew is in the process of p"lacing the unit on RHR cooling using
Train "B".
During relay testing on 6.9kV Shutdown board 1A-A a differential relay is
actuated.
If RHR Pump 1B-B trips when a start is attempted, which ONE of the following
identifies the status of Technical Specification 3.4.1.3, "Reactor Coolant System -
Shutdown"?
A. LCO entry is NOT required, the Technical Specification is met.
B. LCO would be entered until RCP #1 was placed in service.
C. LCO would be entered until one RHR pump was restored to service.
D. LCO would be entered until either both RHR pumps were returned to operable
status or the RCS was cooled to less than 200°F
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2/4/2009
7. Given the following:
- Both Units are at 100 % RTP.
- 1A-A Containment Spray Pump is tagged for maintenance~
- Unit 2 CCS is supplying the Spent Fuel Pool Cooling System.
- The C-S CCS Pump suffers a catastrophic bearing failure.
- The crew enters AOP-M.03, "Loss Of Component Cooling Water".
Which ONE of the following identifies the Containment Spray Pump(s) to be
locked out and the compensatory alignment required prior to restoring the
pumps?
Contai*nment Spray Pump(s) Compensatory
Locked Out Alignment Required
A. 2B-8 only Realign 2B-B CCS Pump for "B" Train cooling.
8. 1B-B and 28-B Realign 2B-B CCS Pump for "B" Train cooling.
C. 2B-8 only Realign 1B-B CCS Pump for "B" Train cooling.
D. 1B-B and 2B-B Realign 1B-B CCS Pump for "B" Train cooling.
Page 7
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2/4/2009
8. Given the following:
Unit 1 experiences an ATWS following a turbine trip.
Due to a trip of the Boric acid pump aligned to the unit, the operators
establish Emergency Boration from the RWST in accordance with
EA-68-4, "Emergency Boration".
- All plant equipment functions as designed except for the Reactor Trip
breakers and the boric acid pump.
- When completing the step for establishing emergency boration flow, the
crew notes Pressurizer pressure is 2260 psigand dropping.
For the above conditions, which ONE of the following ide'ntifies the existing
flowpath for emergency boration and correct status of the Pressurizer PORVs?
Emergency Boration Pressurizer
Flow Path PORVs
A. Through CCPIT Manually OPENED
B. ThroughCCPIT In AUTO and CLOSED
C~ Through charging line Manually OPENED
D. Through charging line In AUTO and CLOSED
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2/4/2009
9. Given the following:
Unit 2 is at 100 % power.
- SG #3 main steamHne ruptured inside containment.
Containment pressure is 6 psig and rising.
- All systems functioned as designed.
Which ONE of the following describes the minimum requirements for AFW flow
to the intactSG and how the intact SGlevels will be maintained while
responding to the event in progress?
Continue to feed the Then, maintain intact
intact SGs with... SG levels between ...
A. > 440 gpm AFW flow until 10 % and 50°/0 Narrow Range.
one SG narrow range level> 10%
B. > 440 gpm AFW flow until 25% and 50% Narrow Range.
one SG narrow range level> 25%
c. > 880 gpm AFW flow until 10% and 50% Narrow Range.
one SG narrow range level> 10%
D. > 880 gpm AFW flow until 25% and 500/0 Narrow Range.
one SG narrow range level> 25%
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10. Given the following:
FR-H.1 "Loss Of Secondary Heat Sink", is in progress.
J
ReS bleed and feed had been initiated when Auxiliary Feedwater (AFW)
capability was restored.
- All Steam generators (SGs) indicate approximately 8% Wide Range level and
approximate-Iy 90 psig.
Incore TC temperatures are stable at 552°F~
Which ONE of the following identifies an acceptable method of re-establishing feed
flow under these conditions and the reason why?
A. Feed ONLY one SG at a rate of 25 gpm to prevent MSIV closure due to
n-egative rate signal.
B. Feed ONLY one SG at a rate of 25 gpm to minimize thermal stresses to the
SG components.
c. Feed ALL SGs at maximum rate to ensure the minimum AFW flow required
for heat sink is established to allow termination of bleed and feed.
D. Feed ALL S-Gs at maximum rate to establish -minimum steam generator level
requirements to allow termination of RCS bleed and feed.
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11. Given the follo'wing:
- The crew is performing ECA-D.O, "Loss Of All AC Power".
ECA-O.O, Appendix A, Locking Out Shutdown Board Loads has been completed.
Offsite power has been restored and the crew is ready to re-energize the
Shutdown Boards.
Which ONE of th'e foUowingidentifies thepumpsthat will rema'in in A-AUTO and
available to start when power is restored to the Shutdown Boards?
A. Centrifugal Charging Pumps
B. Component Cooling Water Pumps
C. Essential Raw Cooling Water Pumps
D. Motor Driven Auxi*liary Feedwater Pumps
Page 11
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2/4/2009
12. Given the following:
- A Large Break LOCA occurred on Unit 1.
- A loss of offsite power occurs after ES-1.3, "Transfer To RHR Containment
Sump" had been completed.
- Shutdown Boards 1A and 1B were re-energized by the diesel generators.
In accordance with ES-1.3, which ONE of the following sequence of actions is taken to
restore core cooling following the loss of offsitepower?
A. Restart the RHR pumps.
Restart the SI pumps.
Ensure the CCPs auto start.
B. Place the CCPs in Pull-To-Lock.
Restart the RHR pumps.
Restart the CCPs and 81 pumps.
C. Ensure the RHRpumps auto start.
Restart the 81 pumps.
Ensure the CCPs auto start.
D. Place the CCPs in Pull-To-Lock.
Ensure the RHR and 81 pumps auto start.
Restart CCPs.
Page 12
1/2009 Sequoyah RONRC Exam
2/4/2009
13. Given the following:
- Unit 1 is at 100 o/oRTP.
- M'CR alarms received indicate that an electrical board has failed.
- All trip status lights on PaneI1-XX-55-5 (1-M-5) are OFF.
- The crew respo'nds in accordance with the appropriate procedure*.
Which ONE of the following identifies (1) the electrical board that failed and
(2) the reason that manipulation of Auxiliary Feedwater (AFW) controls will
be required?
ill
A. 120 VAG Vital Instrument Board 1-1. To prevent overcooling due to excessive
AFW flow due to the LCVs failing open.
B. 120 VAC Vital Instrument Board 1-1. To allow the turbine driven AFW pump to
be operated above minimum speed.
G. 120 VAG Vital Instrument Board 1-11. To prevent overcooling due to excessive
AFW flow due to the LCVs failing open.
D. 120 VAG Vital Instrument Board 1-11. To allow the turbine driven AFW pump to
be operated above minimum speed.
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14. Given the following conditions:
- Unit 1 is at 100 % power.
- Unit 2is in Mode 6 with upper internals removal in progress.
- 125V DC Vital Battery III output breaker tripped and. can NOT be reclosed.
In accordance withO-SO-250-1, "125 Volt DC Vital Power System", which ONE of the
following describes the alignment when 12*5V DC Vital Battery Board III is .restored to
Operable status?
A. 125V DC Vital Battery V and Charger V aligned to the board.
B. 125V DC Vital Battery BankV and .SpareCharger 2-8 aligned to the board.
C. 125V DC Vital Battery Bank V and Spare Charger 1-8 aligned to the board.
D. 125V DC Vital Battery Bank V and 125v DC Battery Charger III to the board.
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2/4/2009
15. Given the following:
Unit 1 in service at 900/0 power for previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after running at
100% power for the past 360 days.
Unit 2 in service at 1000/0 power for 3 days following a refueling outage.
Spent Fuel Pit cooling is being supplied from Unit 1.
Subsequently:
- All ERCW flow is lost due to an explosion at the ERCW pumping station.
- AOP-M.01, "Loss of Essential Raw Cooling Water" is implemented on
both Units.
- The operators are preparing to establish temporary cooling to a CCP on
one of the Units.
Which ONE of the following identifi*es which Unit should have theCCP temporary
cooling established first and the reason why?
Unit to have CCP temporary
Cooling Established First Reason
A. Unit 1 Because Unit has higher decay
heat due to operating longer.
B. Unit 1 Because Unit is aligned
to supply Spent Fuel Pit cooling.
C. Unit 2 Because Unit will have a faster CCS
heat up rate and is more time critical.
D. Unit 2 Because Unit has higher decay heat
since tripped from a higher power level.
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16. Which ONE of the following is the reason for the backup air supply for the Turbine
Driven AFW Pump LCVs and the action/condition required to align the backup supply?
A. Allows the LCVs to be CLOSED during a Statio*n Blackout event and
will require manual alignment locally when needed.
B. Allows the LCVs to be CLOSED during a Station Blackout event and
automatically supplied when air pressure drops below regulator setpoint.
C. Allows the LCVs to be OPENED during a Station Blackout event and
will require manual alignment locally when needed.
D. Allows the LCVs to be OPENED during a Station Blackout event and
automatically supplied when air pressure dro.ps below regulator setpoint.
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2/4/2009
17. Given the fO'Howing:
Unit 1 is at 100% RTP.
- All systems are aligned normally.
- Generator reactive load is currently at "0" MVARs.
- The Transmission Operator has notified the plant that system voltage problems
require Unit 1 to establish the maximurn allowable outgoing reactive load.
Whi'ch ONE of the following identifies the MAXIMUM outgoing reactive load in
accordance with GOI-6, "Apparatus Operation", and the correct operation of the Exciter
Voltage Adjuster?
Maximum Outgoing
Reactive Load Exciter Voltage Adjuster
A. 240 MVA*Rs Lower
B. 240 MVARs Raise
C. 300 MVARs Lower
D. 300 MVARs Raise
Page 17
1/2009 Sequoyah RO NRC Exam
2/4/2009
18. Given the following conditions:
- With Unit 1 initally at full power a large break LOCA occurred.
- Containment pressure = 11 psig.
Both Containment Spray Pumps are running
RWST level = 26%.
- The crew transitioned to ECA-1.1, "Loss Of RHR Sump Recirculation", and is
at the table in Step 8 to determine the proper containment spray pump
alignment and operation.
Which ONE of the following will result in the proper alignment of the containment
spray pumps under existing plant conditions?
A. Stop both containment spray pumps an*d place the handswitches in PULL
TO LOCK. \
B. Continue to run both containment spray pumps until RWST level is less than or
equal to 8%, then stop both containment spray pumps.
C. Stop one containment spray pump and allow the remaining containment
spray pump to take suction from the RWST.
D. Stop both containment spray pumps until suction can be aligned to the
containment sump, then restart one containment spray pump.
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1/2009 Sequoyah RO NRC Exam
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19. Given the following:
Unit 1is operating near EOl at 80% power.
Rod control is in AUTOMATIC with Control Bank "0" at 186 steps.
1-PT-1-73, Turbine Impulse Pressure Transmitter fails HIGH.
Which ONE of the following identifies the direction Control Bank "0" rods will move and
why the Rod Position Indicating (RPI) System Technical Specification requires the
ind'ividual rod RPls to bet 12 steps of the respective group step counter?
Direction TIS Requirement to be +/- 12 steps of Step Counter
A. Insert To maintain acceptable power distribution li*mits.
B. Insert To ensure moderator temperature coefficient remains
negative.
c. Withdraw To maintain acceptable power distribution limits.
o. Withdraw To ensure moderator temperature coefficient remains
negative.
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2/4/2009
20. Given the following:
Following a load reduction to 70% power, Control Bank "D" Rod M-8 was found
misaligned from its ba*nk by greater than 12 steps for twenty minutes.
- The crew entered AOP-C.01, "Rod Control System Malfunctions", and is
preparing to realign the control rod.
Reactor Engineering has determined the following*:
No restrictions apply to realigning the control rod.
- The misaligned rod is to be moved to the affected bank position.
Which ONE of the following identifies h.ow the Rod Control System will be operated to
re*align the control rod in accordance with AOP-C.01?
Operators will disconnect the lift coil(s) for ...
A. the misaligned rod and adjust the affected 9IQ1!Q.step counter to *match the
misaligned rod position.
B. the misaligned rod and adjust the affected bank step counters to match the
misaligned rod position.
c. each rod in the affected 9IQ1!Q (except M-8) and adjust the affected bank step
counters to match the misaligned rod position.
D. each rod in the affected bank (except M-8) and adjust the affected 9IQ1!Q step
counter to match the misaligned rod position.
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21. Given the following:
- A Reactor Trip occurred followed by the crew implementing EA-68-4.,
Section 4.2, "Emergency Boration from BAT".
- After placing 1-HS-62-138A, Emergency Boration FCV in OPEN, the
OATC released the handswitch after ob'serving flow indicated on
1-FI-62-137A, Emerg Boration Flow.
- Two minutes later, the OATC observed both 1-HS-62-138A RED and
GREEN lights LIT and flow stable at 50 gpm.
Which ONE of the following identifies the status of FCV~62-138, Emergency
Boration FCV and the correspo.nding emergency boration flow rate?
FCV-62-138 ...
A. stopped opening when the handswitch was released and the flow rate is
BELOW the minimum required.
B. stopped opening when the handswitch was released and the flow rate is
ABOVE the minimum required.
C. should be full open but has stopped due to thermal overload and the flow
rate is BE.LOW the minimum required.
D. should be full open but has stopped due to thermal overload and the flow
rate is ABOVE the minimum required.
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22. Given the following sequence of events:
Unit 1 in Mode 6 with core reload in progress.
Shutdown monitor was last reset when the count rate was at a steady
state 6 cps.
Source Range instruments indicate counts are rising unexpectedly.
- Annunciator "Source Range High Flux Level At Shutd*own" alarms
Which ONE of the followi.ng indicates the rise in count rate required to cause the
alarm of the "Source Range High Flux Level AtSh.utdown" annunciator and the
action(s) required if the alarm is valid?
Alarm
Setpoint Required Actions
A. 9 cps; Announce over the PA system to evacuate containment
and notify the Refueling SRO to immediately suspend
core alterations.
B. 9 cp.s; ONLY notify the Refueling SRO to immediately suspend
core alterations
C. 18 cps; Announce over the PA system to evacuate containment
and notify the Refueling SRO to immediately suspend
core alterations.
D. 18 cps; ONLY notify the Refueling SRO* to immediately suspend
core alterations
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23. Given the following:
An accidental spill of the Monitor Tank occurred in the Auxiliary Building.
- After isolating the spill, Radcon reported the following conditions:
General area radiation levels of 125 mR/hr at 30 cm
Highest contamination reading of 3.6E3 dpm/1 00 cm 2
Which ONE of the following describes the combination of postings required for the area
and the" radiological concern associated with the types of radiation?
Postings Required Radiological Concern
A. Radiation Area; Radiation is a gamma concern;
Contamination Area Contamination is a beta concern.
B. Radiation Area; Radiation is a beta concern;
High Contamination Area Contamination is a gamma concern.
C. High Radiation Area; Radiation is a gamma concern;
Contamination Area Contamination is a beta concern.
D. High Radiation Area; Radiation is a beta concern;
High Contamination Area Contamination is a gamma concern.
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24. Given the following:
- A fire is reported on MFPT Oil Tank 1A.
- The HPFP System is actuated from the Control Room using control switch
1-HS-26-75A, MFPT OIL TANK 1A FOG CONTROL.
Which ONE of the following com*binations shows the expected status of the
indicating lights on 1-HS-26-75A after actuating the HPFP System?
AMBE*R WHITE RED
A. OFF LIT L*IT
B. LIT OFF LIT
c. LIT LIT OFF
D. LIT LIT LIT
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25. Given the following:
- Unit 1 reactor tripped and a natural circulation cooldown was required.
- The LTOPs system was placed in service in accordance with ES-O.2, "Natural
Circulation Cooldown".
- Subsequently, a faulted steam generator resulted i.n entry into FR-P.1,
"Pressurized Thermal Shock".
- All RCS temperatures have been stabilized at approximately 290°F.
- RCS Pressure is 630 psig.
- Loop 3 Cold Leg Temperatur.e fails LOW.
Which ONE of the foHowing describes the effect on the unit?
A. PORV PCV-68-334 will open and remain open unless itismanua'ilyclosed.
B. PORV PCV-68-340 will open and remain open unless it is manually closed.
C. PORV PCV-68-334 ,will open until ReS pressure drops below the minimum LTOP
setpoint.
D. PORV PCV-68-340 will o,pen until RCS pressure drops below the minimum LTOP
setpoint.
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26. Given the following:
Unit 1 experienced a reactor trip and loss of offsite power.
- The crew is performing ES-0.4, "Natural Circulation Cooldown With Steam
Void in Vessel (Without RVLIS)".
While performing RCS depressurization steps in ES-0.4, whi*ch ONE of the*
following explains a function served by using the Pressurizer heaters to
repressurize theRCS by 100 psigwhen Pressurizer level exceeds 90 0/0?
A. Promotes heat removal from the upper head regi.on of the vessel by
collapsing the steam void.
B. Mai*ntains Pressurizer conditions that allow restarting the Reactor Coolant
Pumps when power is restored.
C. Provides exchange of liquid in the pressurizer to maintain Pressurizer and
RCS boron concentrations within 50 ppm.
D. Allows transfer of the upper head void into the RCS hot legs where the
RCS subcooled mass will collapse the void.
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27. Which one of the following states interlocks that must be met before valve FCV-72-23
(Train A Containment Spray Suction from Containment Sump) can be opened?
A. Both FCV-74-3 (RHR Suction from RWST) closed and FCV-72-40 (RHR Discharge
to RHR Spray) must be closed.
B. Both FCV-72-40 (RHR Discharge to RHR Spray) and FCV-72-34 (Containment
Spray Pump Recirc) must be closed.
c. Both FCV-72-22 (Containment Spray Suction from RWST) and FCV-74-3 (RHR
Suction from RWST) must be closed.
D. Both FCV-72-34 (Containment Spray Pump Recirc) and F'CV-72-22 (Containment
Spray Suction from RWST) must be closed.
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28. Given the following:
Unit 1 is at 100% power.
- Annunciator PaneI1-XA-55-5B, Window B-5~ "LS-68-34A1B REAC COOL
PMP 2 OIL RESERVOIR LEVEL HI~LOW" alarms.
RCP#2 motor bearing temperatures are within limits, stable,and being
monitored.
Reactor Building Poc"ket Sump level is 52%.
Which ONE of the following identify actions required by the Annunciator Response
Procedure?
A. Pump pocket sump level down and monitor pocket sump level for significant
change in rate of rise.
Request Electricians to determine the oil level.
B. Pump pocket sump level down and monitor pocket sump level for significant
change in rate of rise.
Place RCP Lift Oil Pump in service until oil levels can be verified.
C. Lockout the pocket sump pumps to prevent pumping oil until status of RCP motor
bearing oil levels can be determined.
Request Electricians to determine the oil level.
D. Lockout the pocket sump pumps to prevent pumping oil until status of Rep motor
bearing oil levels can be determined.
Place Rep Lift Oil Pump in service until"oillevels can be verified.
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29. Given the following:
Unit 1 is in Mode 5 with water solid operation.
RHR Train "A" is operating in shutdown cooling mode.
RCS is at 160°F.
- VCT temperature is 115°F.
- #2 RCP as the only Rep running was inadvertently stopped 10 minutes ago
after a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> run.
Which ONE of the following identifies the requirements that must be met prior to
attempting a restart of the #2 RCP?
A. Must wait 30 minutes from the time the pump was stopped and can be restarted
with current plant conditions.
B. Must wait 30 minutes from the time the pump was stopped but a steam bubble
must be established in the Pressurizer.
C. No time restriction on restarting the pump and can be restarted with current plant
conditions.
D. No time restriction on restarting the pump but a steam bubble must be established
in the Pressurizer.
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30. Given the following:
- Operators are responding to a small break LOCA on Unit 1 in
accordance with E-1, "Loss Of Reactor or Secondary Coolant".
- The Non~Essential Control Air header inside containment was
depressurized and isolated due to a pipe rupture.
Which ONE of the following-identifies how the CVCS charging and letdown isolation
valves automatically respond to the given plant conditions?
1-FCV-62-90 1-FCV-62-69
Charging FCV Isolation Letdown Isolation
A. OPEN OPEN
B. O-PEN CLOSED
C. CLOSED OPEN
D. CLOSED CLOSED
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31. Plant conditions are as follows:
- U.nit 1 is in Mode 4.
- RHR Train "A" is in service per 0-SO-74-1, "Residual Heat Removal
System".
- RCS temperature is stable atthe current RHR flow rate.
Which ONE of the foUowing malfunctions will result in a REDUCTION in flow
through the RHR Heat Exchanger 1A?
A loss of ...
A. air to 1-FCV-74-32, RHR HTX Bypass.
B. air to 1-FCV-74-16, RHR HTX "A" Outlet.
c. 120V AC Vital*lnstrument Power Board 1-11.
D. 480V Shutdown Board 1A1-A.
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32. Given the following:
- A Main Steam Line Break occurred on Unit 2.
- Reactor Trip and Safety Injection actuated automatically.
- No operator actions have been taken.
Which ONE of the following identifies the expected ECCS valve position for these
conditions?
VA*LVE POSITION
A. FCV-63-25, CePIT Outlet Valve Closed
B. LCV-62-133, VCT Outlet Valve Open
C. FCV-62-98,. CCP Miniflow Valve Open
D. FCV-74-16, RHR Heat Exch. Outlet Valve Closed
Page 32
1/2009 Sequoyah RO NRC Exam
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33. Given the following:
- Unit 1 is operating at 100 % power.
- Annunciator PaneI1-XA-55-5A, Window D-1: "PS-68-301 PRESSURIZER
RELIEF TANK PRESS HIGH" alarms.
- The GATC observes the following conditions:
- PRT pressure is 8.5 psigand slowly rising.
- PRT temperature is 104°F and stable.
- PRT level is 72%.
Which ONE of the following describes (1) the reason for the high pressure and (2) the
action required?
ill
A. Nitrogen regulator leak Reduce PRT pressure by reducing level
B. Nitrogen regulator leak Vent the PRT to the Waste Gas Vent Header
C. Letdown relief lifted Reduce PRT pressure by reducing level
D. Letdown reHef lifted Vent the PRT to the Waste Gas Vent Header
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1/2009 SequoyahRO NRC Exam
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34. Given the following:
- Both Units are at 100 % RTP.
- The CCSSystem is in a normal alignment with the 1A-A,C-S, and 28-8
pumps in service.
- CCS Pumps 1B-B and 2A-A are in A-AUTO.
- 6.9kv Shutdown Board 1A-A normal feeder breaker trips open spuriously.
- Diesel Generator 1A-A starts and loads normally.
Which ONE of the following identifies the CCS pumps that are load shed and the
pumps that are running after load sequencing is complete?
Load Shed Following Load Sequencing
A. Only the 1A-A Only 1A-A, C-S, and 28-8
B. Only the 1A-A 1A-A, 18-8, C-S, and 28-8
c. Both 1A-A & C-S On*ly 1A-A, C-S, and 2B~8
D. Both 1A-A & C-S 1A-A, 1B-8, C-S, and 28-B
Page 34
1/2009 Sequoyah RO NRC Exam
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35. Given the following:
- Unit 1 is at 1000/0 power.
- VeT pressure is at 18 psig.
Which ONE of the following identifies the location of aces le*ak that would
result in the condition listed below?
LEAK* LOCATION CONDITION
A. Rep Thermal Barrier TBBP in A-P auto starts
B. Letdown Heat Exchang*er ees Rad Monitor rising
c. RH*R 1B-BHeat Exchanger ees Surge Tank level rising
D. Seal Return Heat Exchanger VeT level dropping
Page 35
1/2009 SequoyahRO NRC Exam
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36. Given the following:
Unit 1 is at 100 0/0 power.
Pressurizer pressure is 2235 psig with both spray valves closed.
- Annunciator "MOTOR TRIPOUT PNL 1-M-1 THRU 1-M-6" alarms.
- Operator notes Pressurizer pressure slowly dropping.
- There are no other annunciators in alarm.
Which ONE of the following identifies...
(1 ) the breaker trip that caused the motor tripoutalarm
and
(2) the action associated with 1-PIC-68-340A, "Pressurizer Pressure Control"
that could be taken to restore Pressurizer pressure?
A. (1) Centrifugal Charging Pump.
(2) Raise the controller output.
B. (1) Centrifugal Charging Pump.
(2) Lower the controller output.
c. (1) Pressurizer heater Control Group D.
(2) Raise the controller output.
D. (1) Pressurizer heater Control Group D.
(2) Lower the controller output.
Page 36
1/2009 Sequoyah RO NRC Exam
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37. Given the following:
- Unit 1 is at 100 % power.
- A loss of 125V DC Vital Battery Board I occurs.
Which ONE of the following describes the effect on Main Control Board (MCB)
indication and the associated Reactor Trip Breaker?
A. MCB indication is lost and the reactor trip breaker is NOT capable of tripping
on a SHUNT trip.
B. MCB indication is lost and the reactor trip breakertrips OPEN due to loss of
power to the SHUNT coil.
c. MCB indication remains lit. The reactor trip breaker is NOT capable of
tripping o*n a SHUNT trip.
D. MCB indication remains lit. The reactor trip breaker trips OPEN due to loss
of power to the SHUNT coil.
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1/2009 Sequoyah RO NRC Exam
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38. Given the following:
Unit 2 was in Mode 3 performing Shutdown Bank withdrawal.
- Three (3) minutes ago, Safety InjE?ction actuated when a Pressurizer PORV
inadvertently opened before the PORV block valve was closed.
Both reactor trip breakers failed to OPEN.
- The rea.ctor was tripped locally by opening the M-G set motor supply
breakers per FR-S.1, "Response to Nuclear Power Generation/ATWS".
Pressurizer pressure is currently 1940 psig.
Bypass and Permissi've Panel annunciators are as follows:
D-4 S.1. ACTUATED is LIT.
- C-4 AUTO S.1. BLOCKED is DARK.
If the SI Reset push buttons were depressed,.which ONE of the following
represents the correct annunciator status and associated reason following the
reset of Safety Injection for th'e above conditions?
A. SI ACTUATED will rema*in LIT b.ecause P-11 Permissive has NOT bee*n met.
B. 81 ACTUATED will remain LIT because Pressurizer pressure is less than the 81
setpoint.
c. AUTOSI BLOCKED will remain DARK because the SI timing relay has NOT timed
OUT.
D. AUTO SI BLOCKED will remain DARK because the P-4 Permissive has NOT been
met.
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1/2009 Sequoyah RO NRC Exam
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39. Which ONE of the following Containment Cooling System fans will trip and
isolate as a DIRECT result of a manual Containment Isolation Phase-A Signal?
A. Lower Compartment Coolers
B. Upper Compartment Coolers
C. Control Rod Drive Motor coolers
D. Incore Instrument Room coolers
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1/2009 Sequoyah RO NRC Exam
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40. Which ONE of the following Ice Condenser temperatures is within the optimum range
to minimize sublimation, frost buildup, and ice condenser door binding problems?
Page 40
1/2009 Sequoyah RO NRC Exam
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41. Which ONE of the following identifies an ice condenser door that would require
entering a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Technical Specification *LCO if the door was found to be physically
restrained from opening and which of the doors are equipped with flow proportioning
springs to control opening?
Require 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> LCO entry if Doors equipped with
physically restrainedu from opening flow proportioning springs
A. Only an inlet door Inlet doors
B. Only an inlet door Intermediate doors
C. Either an inlet or Inlet doors
intermed*iate deck door
D. Either an inlet or Intermediate doors
intermediate deck door
Page 41
1/2009 Sequoyah RO NRC Exam
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42. Given the following:
Unit 1 and Unit 2 6.9kV Shutdown Boards are align-ed as follows:
1A-A from normal feed
1B-B from normal feed
2A-A from alternate feed
- 28-8 from normal feed
Diesel Generator 28-8 is tagged for maintenance.
- 6.9kV Unit Board 2C is de-energized due to a fire.
Which ONE of the following has lost power?
C. Containment Spray Pump 28-8
D. Residual Heat Rem*oval Pump 2A-A
Page 42
1/2009 Sequoyah RO NRC Exam
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43. Given the foHowing conditio'ns:
Unit 1 is operating at 100% power.
1A-A Containment Spray (CS) Pump is out of service.
- A large break LOCA occurs
1B-B RHR Pump trips on instanta*neous overcurrent and is damaged.
60 minutes later, the following conditions exist:
- Containment pressure is 10 psig.
- FR-Z.1, "High Containment Pressure" isin progress.
- ES-1.3, "Transfer To RH*R Containment Sump" has been completed.
- The crew observes 1B-B CSPump ru.nning with a discharge flow of
approximately 4000 gpm.
Which ONE of the following describes the condition of the Containment Spray
System and the FR-Z.1 direction concerning RHR spray?
A. Containment spray flow is normal andRHR spray should be placed in service.
B. Containment spray flow is normal and RHR spray should NOT be placed in servi*ce.
C. Containment spray flow is LOWER than normal and RHR spray should be placed in
service.
D. Containme*nt spray flow is LOWER than normal and RHR spray should NOT be
placed in service.
Page 43
1/2009 Sequoyah RO NRC Exam
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44. Given the following:
Plant startup in progress with MSIVs and bypass valves closed.
ReS at 2235 psig and 547°F.
- The crew began warming the main steam lines and observed the following
RCS temperature changes:
0900 - 547°F
0915 - 522°F
0930 - 495°F
0945 - 467°F
1000- 453°F
1015 - 424°F
1030 - 410°F
1045 - 398°F
1100 - 402°F
Which ONE of the following .identifies the status of the RCS cooldown rate
Technical Specification limit and the component stress that represent the bases
for the limit?
Cooldown Rate Limiting Component
A. Tech Spec limit was exceeded Reactor Vessel
B. Tech Spec limit was exceeded Steam Generator Tube* Sheet
c. Maintained within the Tech Spec limit Reactor Vessel
D. Maintained within the Tech Spec limit Steam Generator Tube Sheet
Page 44
1/2009 Sequoyah RO NRC Exam
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45. Given the following:
Unit 1 is at 1000/0 power.
- A significant feedwater heater level transient results in HI-HI levels in Feedwater
Heaters A1 and B1.
Extraction steam to the feedwater heaters isolates.
In accordance with AOP-S.04, "Condensate or Heater Drains Malfunction", which ONE
of the following will be the effect on indicated SG narrow range levels, RCS Tcold, and
reactor power?
A. SG NR levels will decrease, ReST cold will decrease, and reactor power will
increase.
B. SG NR levels wiU decrease, ReS T cold will decrease, and reactor power will
decrease.
C. SG NR levels will increase, ReS T cold will increase, and reactor power will
increase.
D. SG NRlevelswili increase, ReS T cold will increase, and reactor power will
decrease.
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1/2009 Sequoyah RO NRC Exam
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46. Given the following conditions:
Unit 2 is initially at 100 % power.
Instrument failures cause a spurious Main Feedwater Isolation Signal.
NO Auxiliary Feedwater Pumps start.
- The reactor does NOT trip.
- AMSAC fails to actuate.
Assuming NO operator action, which ONE of the following is the primary concern to
plant systems and why?
A. Main steamline break due to thermal shock on Steam Generator shell.
B. SG tube rupture due to highprimary-to-secondary differential pressure.
C. Challenge to PZR PORVs and safety valves due to overpressure transient
in the ReS.
D. Overpower condition due to the failure of the turbine to receive a trip
signal.
Page 46
1/2009 Sequoyah RO NRC Exam
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47. Given the following:
_ . A reactor trip occurred on Unit 1/ wJ,; Ie .f1.e U/v:4 W IV:> oJ rU() O!" ~el'\.
- The only operator action taken was to manually close the LCVsto the SGs
supplied from 1A-A MDAFW Pump.
Which ONE of the following describes the flow that will continue to be passed .through
the pump?
A. 30 GPM to the CST
B. 30 GPM to the condenser hotwell
C. 165 GPM to the CST
D. 165 GPM to the condenser hotwell
Page 47
1/2009 Sequoyah RO NRC Exam
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48.
Given the following:
Loss of off site power occurred on Unit 1 resulting in a Reactor Trip
a.nd Safety Injection.
- The Emergency Diesel Generators (DGs) started. and DG 1A-A
loaded to 4.6 MWs.
In accordance w*ith AOP-P~01, "Loss of Offsite Power", which ONE of the
followi'ng describesthe operation of DG 1A~A under this load condition?
A. Must be immediately tripped.
B. May operate for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
c. May operate for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. May operate indefinitely.
.Page 48
1/2009 Sequoyah RO NRC Exam
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49. Given the following:
- Unit 2 at 1000/0 power.
- Panel 2-M~1 Annunciator Window "125V DC VITAL CHGR III FAILNITAL
BAT III DISCHARGE" alarms.
- The crew enters AOP-P.02,"Loss Of 125V DC Vital Battery Board".
- A reactor trip o-ccurs on high PZR pressure.
Which ONE of the following identifies the allowed usage of AOP-P.02 after
the Emergency Operat~ng Procedure network is entered following the reactor
trip?
Continued performance of AOP-P.02 is ...
A. allowed after the crew enters ES-O.1, "Reactor Trip Response" because
ES-0.1 is NOT an accident mitigation EOP.
B. allowed after the crew enters ES-O.1, "Reactor Trip Respo-nse" because
restoring power could have an impact on meeting the goals of the EOP.
C. NOT allowed until the crew exits ES-O.1, "Reactor Trip Response"
because the procedure reader must remain dedicated to the EOP in
effect until the EOPs are exited.
D. NOT allowed until the crew exits ES-O.1, "Reactor Trip Response"
because actions taken in AOP-P.02 could degrade the performance of
the EOP.
Page 49
1/2009 Sequoyah RO NRC Exam
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50. Given the following:
DIG 1A-A is running at 4.4 MW for surveillance testing.
DIG Day Tank levels are as follows:
1A1 - 250 gallons
1A2 - 300 gallons
Neither Fuel !ransferPump starts in automatic.
Which ONE of the following represents how long DIG 1A-A would continue to operate
WITHOUT makeup to DIG 1A1 Day Tank AND the effect on DIG 1A2 Day Tank if-the
1A1 Fuel Transfer Pump is able to be manually started?
A. Greater than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
DIG 1A2 Day Tank level rises.
B. Greater than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
DIG 1A2 Day Tank level continues to drop.
c. Less than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
DIG 1A2 Day Tank level rises.
D. Less than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
DIG 1A2 Day Tank level continues to drop.
Page 50
1/2009 Sequoyah RO NRC Exam
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51. Given the following plant conditions:
Unit 1 & 2 are steady-state at 100 % power.
125V DC Vital Battery Board IV is inadvertently deenergized.
- All 4 Diesel Generators start.
Which ONE of the following describes an effect this has' on the diesel generators?
A. Diesel Generator 1B-B could only be shutdown using the EMERGENCY
STOP pushbutton on O-M-26.
B. Diesel Generator2B-B could only be shutdown using the Local Panel
EMERGENCY STOP pushbutton at the DG Building.
c. All engine trips except foroverspeed on Diesel Generator 1B-B would be
disabled and ALL generator trips would remain enabled.
D. All generator trips except for generator differential on Diesel Generator
2B-Bwould be disabled and ALL engine trips would remain enabled.
Page 51
1/2009 Sequoyah RO NRC Exam
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52. Given the following:
- A Source check is to be performed on O-RM-90-1 01 B, "Auxiliary
Building Vent Rad Monitor".
- The ESF function of the monitor is to be blocked using O-HS-90-136A3,
"Process Rad Monitor System Block Switch".
In accordance with the applicable System Operating Instruction, which ONE of
the following describes how ...
(1) the block switch would be positioned during the source check.
and
(2) the effect the positioning of the block switch will have on the ability to
block the ESF function of 1~RM-90-130, "Containment Purge Rad
Monitor"?
A. (1) The block switch would be placed to the "101 Btt position and pulled out.
(2) 1-RM-90-130A .could be blocked without pulling the HI RAD relay.
B. (1) The block switch would be placed to the "101 B" position and pulled out.
(2) 1-RM~90-130A could NOT be blocked without pulling the HI RAD relay.
C. (1) The block switch would be placed to the "101 Bit position and pushed in.
(2) 1-RM-90-130A could be blocked without pulling the HI RAD relay.
D. (1) The block switch would be placed to the "101 B" position and pushed in.
(2) 1-RM-90-130A could NOT be blocked without pulling the HI RAD relay.
Page 52
1/2009 Sequoyah RO NRC Exam
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53. Given the following Unit 1 conditions:
- All ERCW pump controls are in a normal preferred alignment per 0-80-67-1,
II-Essential Raw Cooling Water".
ERCW Pump L-B trips.
- Train "B" ERCWheader stabilizes at 68 psig.
The CRO places L-B pump handswitch in STOP PULL-TO-LOCK.
In accordance with AOP-M.01, "Loss of Essential Raw Cooling Water", which ONE of
the following identifies the additional action(s) required to be taken in response to this
event?
A. Manually start E-RCW Pump N-B. RepositionO-XS-67-286, DGPower Selector
Switch.
B. Manually start ERCW Pump N-B. Do NOT reposition switch O-XS-67-286, DG
Power Selector Switch.
c. Pressure remains within the normal operating-band. Reposition O-XS-67-286, DG
Power Selector Switch.
D. Pressure remains within the normal operating band. Do NOT reposition switch
O-XS-67-286~ DG Power Selector Switch.
Page 53
1/2009 Sequoyah RO NRC Exam
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54. Given the following:
Unit 1 is in Mode 5 with 6.9kV Shutdown Board 1A-A tagged for maintenance.
- Subsequently, 6.9kVShutdown Board 2B-B trips and locks out due to
relay operation.
Which ONE of the following ide.ntifiesthe status ofthe Auxiliary Air Compressor
power supplies?
A. Both Auxiliary Air Compressors have a power supply available.
B. Neither Auxiliary Air Compressor has a power supply available.
c. Only the Auxiliary.Air Compressor A-A has a power supply available.
D. Only the Auxiliary Air Compressor B-B has a power supply available.
Page 54
1/2009 Sequoyah RO NRC Exam
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55. Which ONE of the following identifies...
(1) when FCV-30-46, 47, & 48, "Containment Vacuum Relief System Isolation
Valves" would automatically close
AND
(2) the condition(s) required prior to the valves being manually re-opened?
A. (1) Only a containment pressure rise to 1.5psid relative to the annulus;
(2) Containment pressure must be less than 1 ~O psid.
B. (1) Only a containment pressure rise to 1.5 psid relative to the annulus;
(2) Containment pressure must be less than 1.0 psid and safety
injection must be reset.
C. (1) Initiation of any Safety Injection signal;
(2) Containment pressure must be less than 1.0 psid.
D. (1) Initiation of any Safety Injection signal;
(2) Containment pressure must be less than 1.0 psid and safety
injection must be reset.
Page 55
1/2009 Sequoyah RO NRC Exam
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56. Given the following:
Unit 1 is at 85% power steady-state.
Rod control is in MANUAL.
RCS Tavg Auctioneering Unit fails to 530°F.
Which ONE of the following identifies the effect the failure has on Pressurizer level and
pressure with NO operator action?
Pressurizer Level Pressurizer Pressure
A. Drops until letdown isolates. Drops due to heaters deenergizing.
B. Drops until letdown isolates. Rises due to level rising after letdown
isolates.
C. Stabilizes before letdown Stabilizes with variable heaters energized.
isolates.
D. Stabilizes before letdown Stabilizes with spray valves opening.
isolates.
Page 56
1/2009 Sequoyah RO NRC Exam
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57. Given the following:
- A Unit 1 reactor startup is in progress.
- Control Bank "0" rods are being withdrawn *when Rod H-8 dropped into
the core.
- Control Bank "0" step counters indicated 31 steps and Rod H-8 RPI
indicated 28 steps at the time of the rod drop.
Which ONE of the following identifies the status of the H-8 Rod Bottom Light and
Annunciator PaneI1-XA-55-4B, WindowD-7: "FULL LENGTH RODS RODS AT
BOTTOM" for the above conditions?
H-8 Rod. Bottom Light Annunciator 0-7
A. LIT before the rod dropped and In alarm
remained LIT after the rod dropped.
B. LIT before the rod dropped and NOT in alarm
remained LIT after the rod dropped.
c. DARK before the rod dropped and In alarm
LIT after the rod dropped.
o. DARK before the rod dropped and NOT in alarm
LIT after the rod dropped.
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1/2009 Sequoyah RO NRC Exam
21412009
58. Given the following:
- Unit 1 is at 100 % power.
- Power Range Channel NI-44 fails due. to a loss of instrument power.
Which ONE of the following identifies the impact the failure ofNI-44 has on
Annunciator PaneI1-XA-55-4B, Window D-4: "COMPUTER ALARM RODDEV&SEQ
NIS RANGE TILTS"?
The window will alarm due to ICS sensing ...
A. An AFD alarm and the window has reflash capability for alarms from other sources.
B~ AnA*FD alarm, but the window does NOT have reflash capability for alarms from
other sources.
c. A QPTR alarm and the window *has reflash capability for alarms from other sources.
D.A QPTR alarm, but the window does NOT have reflash capability for alarms from
other sources.
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1/2009 Sequoyah RO NRC Exam
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59. Which ONE of the following identifies the alternate locations available for Charging flow
control and indication outside of the Main Control Room?
Aux Control Room Locally in the Aux Building
(1-L-10) (1-L-112A)
A. Controller functions and the flow No control function on panel,
indication reads only with Nor-Aux flow indication only
switch in AUX.
B. Controller functions and the flow Panel has both controller
indi*cation reads only with Nor-Aux function and flow indication
switch in AUX.
C. Controller functions only with No control function on panel,
Nor-Aux switch in AUX. flow indication only
Indication reads with Nor-Aux
switch in either position.
D. Controller functions only with Panel has both controller
Nor-Aux switch in AUX. function and flow indication
Indication reads with Nor-Aux
switch in either position.
Page 59
1/2009 Sequoyah RO NRC Exam
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60. Given the following:
Unit 2 operating at 10% reactor power.
- CONDITION 1: Two hours- following a reactor trip and trip of all Reps.
- CONDITION 2: Two hours following a reactor trip with all RCPs running.
Which ONE of the following identifies the correct combination of expected indications
for incore thermocouple temperatures (TCs) and RCS cold leg temperatures (Tcold) for
the stated conditions?
CONDITION 1 CONDITION 2
(No Reps) (ALL Reps)
A. TCs only slightly TCs only slightly
above Tcold above Tcold
B. TCsonly slightly TCs several degrees
above Tcold greater than Tcold
c. TCs several degrees TCsonly slightly
greater than Tcold above Tcold
D. TCs several degrees res several degrees
greater than Tcold greater than Tcold
Page 60
1/2009 Sequoyah RO NRC Exam
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61. Which ONE of the following is the power supply to the Emergency Gas Treatment
System (EGTS) Fan B?
A. C & A Vent Board 181-B
B. C & AVent Board 281-B
c. Reactor Vent Board 1B-B
D. Reactor Vent Board 28-8
Page 61
1/2009 Sequoyah RO NRC Exam
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62. Given the following:
Unit 1 is at 50% power and stable when a transient occurs.
- The eRO reports the following parameters and trends for 8G#1 with similar
trends on the other 8G's:
- 5G Pressure: 860 psig and lowering
- 8G Level: 460/0 and rising
- 5G Steam Flow: 2.0 x10 6 pph and rising
Which ONE of the following identifies the event in progress?
A. SG tube has ruptured
B. SG atmospheric relief valve open
C. RCS dilution event is in progress
D. Main turbine runback in progress
Page 62
1/2009 Sequoyah RO NRC Exam
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63. Given the following:
- Unit 1 is at 10 % power during a plant startup.
- A reactor trip occurs.
Steam dumps should be controlling steam pressure at approximately ...
A. 870 psig
B. 965 psig
c. 1005 psig
D. 1040 psig
Page 63
1/2009 Sequoyah RO NRC Exam
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64. Given the following:
- Unit 2 is operating at 1160 MWe.
- Generator reactive load is 325 MVARsincoming.
- All systems are operating normally.
Which ONE of the following hydrogen pressures is the LOWEST that will provide
acceptable generator-cooling in accordance with the generator capability curve?
REFERENCE PROVIDED
A. 55 psig
B. 60 psig
c. 65 psig
D. 70 -psig
Page 64
1/2009 Sequoyah RO NRC Exam
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65. Given the following:
- W*aste Gas Decay Tank A is "IN SERVICE".
- Waste Gas Decay Tank D is in "STANDBY MODE".
- An automatic transfer occurs from WGDT A to WGDT D.
- An AUO dispatched to respond to the transfer reports the following:
-WGDT A pressure is 120 psig.
- WGDT 0 pressure is 9 psig.
Which ONE of the following descri'bes BOTH the transfer from WGDT A to
WGDT 0 and the status of the WGDT D pressure?
A. The transfer occurred prior to the automatic swapover setpoint.
WGDT D pressure is above the minimum pressure to be "IN SERVICE".
B. The transfer occurred prior to the automatic swapover setpoint.
WGDT 0 pressure needs to be raised by adding nitrogen to the tank.
C. The transfer occurred past the automatic swapover setpoint .
WGDT Dpressure is above the minimum pressure to be "IN SERVICE".
D. The transfer occurred past the automatic swapover setpoint.
WGDT D pressure needs to be raised by adding nitrogen to the tank.
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1/2009 Sequoyah RO NRC Exam
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66. Following Safety Injection, which ONE of the following identifies the
'Procedural Requirement' to ensure a plant announcement has been
made regarding the reactor trip/safety injection?
A. Immediately after completing the Immediate Action Steps in "E~O, "Reactor
Trip or Safety Injection".
B. Immediately after transitioning fromE-O, "Reactor Trip or Safety Injection" to
anoth"er ERG procedure.
c. When directed to by a step in ES-O.1, "ReactorTrip Response".
D. When directed to by a step in ES-O.5, "Equipment Verifications".
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67. Which ONE of the following identifies the items in the list below that are
required to be reviewed by an oncoming OATe during Shift Turnover in
accordance with OPDP-1, "Conduct of Operations"?
1. Abnormal equipment lineup/conditions
2. SllTest in progress/planned
3. Standing Order changes since last shift worked
4. Work Orders generated since last shift worked
5. Tech Spec LeOs in effect
6. Priority 1 and 2 Operator Workarounds
A. All EXCEPT 1 and 2
B. All EXCEPT 1 and 4
c. All EXCEPT 2 and 6
D. All EXCEPT 4 and 6
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68. The administrative requirements for reactivity management contained in OPDP-1,
"Conduct of Operations" states that Unit Operators are responsible for ...
A. personally overseeing all reactivity changes in the MeR.
B. making positive reactivity changes by only one method at a time.
C. reviewing and approving all planned reactivity changes as developed by
Reactor Engineering.
D. notifying the shift Reactor Engineer of unplanned reactivity changes that
exceed 1% thermal power.
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69. Given the following plant conditions:
Unit 1 in Mode 5.
1-FCV-62-93, "Charging Flow Control Valve", is selected as a
boundary isolation valve for a clearance on the cves charging header.
In accordance with SPP-10.-2, "Clearance Procedure to Safely Control Energy",
which ONE of the following is an acceptable method for tagging 1-FCV-62-93?
A. Ensure the air isolation valve in the open position, place handswitch in closed
position and tag both the air isolation valve and the handswitch.
B. Close the valve, install a jacking device, isolate the air supply and tag both
the jacking *device a*nd the air isolation valve.
c. Dog the valve closed with its handwheel, isolate the air supply and tag both
the handwheel and the air isolation valve.
D. Isolate the air supply to the valve, place handswitch in closed position and
tag both the air isolation valve and the handswitch.
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1/2009 SequoyahRO NRC Exam
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70. Given the following:
Both Units are at 100 % power with all systems are aligned normal.
ERCW pumps J-A and M-B are tagged out of service for maintenance.
Which ONE of the* following identifies the MAXIMUM averageERCW temperature
allowed without entering a Technical Specification LCO, and the LCO that would be
entered if the temperature was exceeded?
Maximum Allowed LCO
Temperature Entered
A. 3.7.4, Essential Raw Cooling Water System
B. 3.7.5, Ultimate Heat Sink
c. 87°F 3.7.4, Essential Raw Cooling Water System
D. 3.7.5, Ultimate Heat Sink
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71. Which ONE of the following identifies the FIRST radiation monitor that should
respond to a SGTR and the effect on the monitor when the SGTR results in
Safety Injection being actuated?
A. RM-90-119, Condenser Vacuum Exhaust Monitor. The monitor will
automatically isolate.
B. RM-90-119, Condenser Vacuum Exhaust Monitor. The monitor will NOT
automatically isolate.
c. RM-90-120/121, Steam Generator Slowdown Sample Monitor. The monitor
will automatically isolate.
D. RM-90-120/121, Steam Generator Slowdown Sample Monitor. The monitor
will NOT automatically isolate.
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72. Given the following plant conditions:
- A LOCA has occurred and a SAE has been declared.
- The TSC and OSC have been activated.
- To prevent damage to equipment needed for protection of the public, it is
recommended that an individual make an entry into the 1A-A Safety
Injection Pump Room 1A.
Projected dose rate in the pump room is 1.0 x10 5 mRlhr.
Duration of the exposure is expected to be 6 minutes.
Which ONE of the following individuals must authorize this exposure?
A. Radcon Manager
B. S"ite Emergency Director
C. Plant Manager
D. Site Vice President
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73. Given the following:
- Unit 2 was at 100 % powerwhenan inadvertent reactor trip occurred.
- After completing the Immediate Actions of E~O, "Reactor Trip or Safety
Injection", the crew transitioned to ES-O.1, "Reactor Trip Response".
- The STA was delayed from arriving in the MeR.
Who should be assigned to monitor the Critical Safety Function Status Trees
until the STA arrives in accordance with EPM-4, "User's Guide"?
A. Extra Operator
B. DATe
C. Unit Supervisor
D. Shift Manager
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74. In response to a Heat Sink Red Path condition, the crew entered FR-H.1, "Loss Of
Secondary Heat Sink". While progressing through FR-H.1, the STA reports the
fo*llowing Status Tree conditions:
- Subcriticality: Orange Path - FR-S.1, "Nuclear Power Generation/ATWS"
- Core Cooling: Green Path
Heat Sink: Green Path
Integrity: Green Path
- Containment: Red Path - FR-Z.1, "High Containment Pressure"
Inventory: Green Path
Which ONE of the following describes the required procedural actions in response to
the above conditions?
A. Immediately exit FR-H.1 and implement to FR-Z.1.
B. Immediately exit FR-H.1 and implement to F*R-S.1.
c. Complete FR-H.1, then implement to FR-Z.1.
D. Complete FR-H.1, then implement to FR-S.1.
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75. Given the following:
- The Unit 1 CROis in the Cafeteria eating lunch with an AUO who is
assigned as an OSC responder.
- A Site Area Emergency is declared on Unit 1.
In accordance with EPIP-8 "Personnel Accountability And Evacuation", which ONE of
the following identifies responsibilities of the CRO and theAUO following the initiation
of Assembly and Accountability.
A. CRO - Report to the Main Control Room, swipe bad.ge in the MCR card reader.
AUO - Swipe badge in the Cafeteria card reader, and report to the OSC.
B. CRG - Report to the Main Control Room, swipe badge in the MCR card reader.
AUG - Report to the Main Control Room, swipe badge in the MCR card reader and
then report to the OSC.
C. CRO - Swipe badge in the Cafeteria card reader, and report to the Main Control
Room.
AUO - Swipe badge in the Cafeteria card reader, and report to the OSC.
D. CRO - Swipe badge in the Cafeteria card reader; Report to the Main Control Room.
AUG - Report to the Main Control Room, swipe badge in the* MCR card reader and
then report to the OSC.
Page 75
RO Reference Package
1. TI-28, Fig. A.14
1/2009 Sequoyah RO NRC Exam
2/4/2009
1 007 EK2.03 1 B
2 008 AG2.4.45 2 C
3 009 EA2.10 3 A
4 015 AA2.08 4 D
5 022 AK.1.02 5 A
6 025 AG2.2.36 6 A
7 026 AA2.03 7 D
8 029 EG2.1.31*8 D
9 040 AK.1.06 9 B
10 054 AK.1.02 10 B
11 055 EK2.04 11 C
12 056 AA1.11 12 B
13 057 AK.3.01 13 A
14 058 AA1.01 14 B
15 062 AK.3.03 15 C
16 065 AK3.04 16 A
17 077 AA1.03 17 B
18 W/E11 EK2.118 C
19 001 AK3.02 19 C
20 005 AA1.01 20 D
21 024 AA2.01 21 B
22 036 AK3.01 22 C
23 059 AK1.02 23 C
24 067 AG2.1.31 24 D
25 W/E08 EA1.1 25 C
26 W/E10 EK 1.1 26 A
27 WE14 EK2.1 27 C
28 003 A1.04 28 A
29 003 K4.02 29 D
30 004 A3.l1 30 D
31 005 K6.03 31 A
32 006 A3.06 32 C
33 007 A2.05 33 B
34 008 A3.04 34 B
35 008 K1.04 35 B
36 010 A.2.01 36 D
37 012 K2.01 37 A
38 013 G2.4.46 38 D
39 022K4.0339 D
40 025 K5.02 40 A
41 025 K6.01 41 A
42 026 K2.01 42 C
43 026 K3.02 43 C
44 039 K5.05 44 C
45 059 K3.04 45 A
46 061 K3.01 46 C
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1/2009 Sequoyah RO NRC Exam
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47 061 K5.03 47 A
48 062 K1.02 48 B
49 063 G2.4.8 49 B
50 064 A1.02 50 C
51 064 K1.04 51 B
52 073 A4.02 52 A
53 076 A4.01 53 A
54 078 K2.02 54 C
55 103 A1.01 55 A
56 011 K1.02 56 D
57 014 K5.02 57 D
58- 015 K3.04 58 C
59 016 K4.01 59 D
60 017 A3.01 60 C
61 027 K2.01 61 A
62 035 K6.02 62 B
63 041 A1.02 63 C
64 045G2.1.25 64 B
65 071 A4.16 65 D
66 G 2.1.14 66 D
67 G 2.1.3 67 D
68 G 2.1.37 68 B
69 G2.2.1369 B
70 G 2.2.3770 D
71 G2.3.1171 B
72 G 2.3.472 B
73 G 2.4.13 73 A
74 G 2.4.2374 C
75 G 2.4.39 75 A
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