ML090690051
| ML090690051 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/04/2009 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-327/09-301, 50-328/09-301, ES-401, ES-401-8 | |
| Download: ML090690051 (105) | |
See also: IR 05000327/2009301
Text
Name:
Date: 02/04/2009
Site-Specific SRO Written Examination
Cover Sheet
u.s. Nucle.ar Re*gulatory Commission
Site-Specific SRO Written Examination
Applicant Information
Facility/Unit: Sequoyah 1 &2
Form ES-401-8
Region:
Start Time:
1D II *[81111 D IvD
Reactor Type: W ~ CED BWD GED
Finish Time:
Instructions
Use the answer sheets provided to document your answers. Staple this cover sheet
on top of the answer sheets. To pass theexa'mination you must achieve a final grade
of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items
if given in conjunction with the ROexam; SRO-only exams given alone require a final grade
of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination,
and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only tak"ing the SRO portion.
Applicant Certification
All work done on this examination is my own.
1have neither given nor re'ceived aid.
Applicant's Signature
Results
RO/SRO..,OnlylTotal Examination Values
-- 1-- / --
Points
Applicant's Scores
/ -- / --
Points
--
Applicant's Grade
/
I --
Percent
-- --
1/2009 Sequoyah SRO NRC Exam
2/4/2009
1. Given the following:
Unit2 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, "STM GEN LO-OP 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 cause 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 reactor tripped due to the turbine trip;
The Reactor Trip First Out panel has NOT been acknowledged and the SG
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 trip-ped due to the SG low level;
The Reactor Trip First Out panel has been acknowledged and the P-9 Turbine Trip
Reactor Trip window c-ame in after the panel was acknowledged.
Page 1
1/2009 Sequoyah SRO NRC Exam
2/4/2009
2. Given the following:
-
Unit2 operating at 100% 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 pstg and rising
0,-" Qd £k.~ l,~aNAl
Given the above conditions, which ONE of the following annunciators would indicate-a-
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 COMPT MOISTURE HIGH
D. LS-68-335D/E PRESSURIZER LEVEL HIGH-LOW
Page 2
1/2009 SequoyahSRO NRC Exam
2/4/2009
3. In accordance with AOP-R.05, "ReS Leak and Leak Source Identification", which ONE
of the following changes in conta-inment conditions discriminates between a small
break LOCA and a steam line break inside containment?
A~
Radiation
B.
Humidity
C. Pressure
D. Temperature
Page 3
1/2009 Sequoyah SRO NRC Exam
2/4/2009
4. In accordance with AOP-R.04, "Reactor Coolant Pump Malfunction", 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?
Page 4
1/2009 Sequoyah SRO NRC Exam
2/4/2009
5. Given the following:
-
Unit 2 is operating at 100% power.
-
The crew entered AOP-R.05, "ReS Leak and Leak Source Identification".
-
The crew is re-establishing charging flow in accordance with EA-62-5,
"Establishing Normal Charging and Letdown".
-
RCP seal injection flows are as follows:
~-
9.2 gpm
10.5 gpm
11.9 gpm
13.4 gpm
Which ONE of the foUowing id.entifies 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-F*CV-62-S9 needs
Charging Flow to the
to be throttled
Regen Heat Exchanger WILL
A.
OPEN
Increase
B.
OPEN
Decrease
C.
CLOSED
Increase
D.
CLOSED
Decrease
Page 5
1/2009 Sequoyah SRO NRC Exam
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
Off but
available
- 2
Running
- 3
Off &
tagged
- 4
Off &
tagged
-
All SlG levels are between 28 - 34%
narrow range.
-
The operating crew is in the process of placing 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
Page 6
1/2009 Sequoyah SRO NRC Exam
2/4/2009
7. Given the* following:
-
Both Units are at 100%
RTP.
-
1A-A Containment Spray Pump is tagged for mainten*ance.
-
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".
W.hich ONE of the following identifies the Containment Spray Pump(s) to be
locked out and the compensatory alignment required prior to restoring the
pumps?
Containment Spray Pump(s)
Locked .Out
A. 2B-B only
B.
C. 28-B only
D. 1B-B and 28-'B
Compensatory
Alignment Required
Realign 28-B CCS Pump for "B" Train cooling.
Realign 28-B CCS Pump for "B" Train cooling.
Realign 1B-BCCSPump for "B" Train cooling.
Realign 1B-B CCS Pump for liB" Train cooling.
Page 7
1/2009 SequoyahSRO NRC Exam
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 psig and dropping.
For the above conditions, which ONE of the following identifies the existing
flowpath for emergency boration and correct status of the Pressurizer PORVs?
Emergency Boration
Pressurizer
Flow Path
A. Through CePIT
Manually OPENED
B. Through CCPIT
In AUTO and CLOSED
c. Through charging line
Manually OPENED
D. Through charging line
In AUTO and CLOSED
Page 8
1/2009 Sequoyah SRO NRC Exam
2/4/2009
9. Given the following:
Unit 2 is at 100% power.
-
SG#3 main steam line 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 intact SG and how the intact SG levels will be maintained while
responding to*the event in progress?
Continue to feed the
intact SGs with....
A. > 440 gpm AFW flow until
one SG narrow range level> 10%
B. > 440 gpm AFW flow until
one SG narrow range level> 25%
c. > 880 gpm AFW flow until
one SG narrow range level> 10%
D. > 880 gpm AFW flow until
one SG narrow range level> 25%
Then, maintain intact
SG levels between ...
100/0 and 500/0 Narrow Ra.nge.
25% and 500/0 Narrow Range.
10°10 and 50°10 Narrow Range.
25%
and 50%
Narrow Range.
Page 9
1/2009 Sequoyah SRO NRC Exam
2/4/2009
10. Given the following:
FR-H.1 J "Loss Of Se*condary Heat Sink", is in progress.
RCS bleed and feed had been initiated when Auxiliary Feedwater (AFW)
capability was restored.
-
All Steam generators (SGs) indicate approximately 8%
Wide Range level and
approximately 90 psig.
Incore TC temperatures are stable at 552°F.
Which ONE of the following identifies an acceptable method of re-establishingfeed
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
negative rate signal.
B. FeedONLYone 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 SGs at maximum rate to establish minimum steam generator level
requirements to allow termination of RCS bleed and feed.
Page 10
1/2009 Sequoyah SRO NRC Exam
2/4/2009
11. Given the following:
-
The crew is performing ECA-O.O, "Loss Of All AC Power".
ECA-O.O, Appendix A, Locking Out Shutdown Board Loads has been completed.
Offsite power has been restore*d and the crew is ready to re-energize the
Shutdown Boards.
Which ONE of the following identifies the pumps that will remain in A-AUTO and
available to start when power is restored to the Shutdown Boards?
A. Centrifugal Charging Pumps
B. Compone*nt Cooling Water Pumps
C. Essential Raw Cooling Water Pumps
D. Motor Driven Auxiliary Feedwater Pumps
Page 11
1/2009 Sequoyah SRO NRC Exam
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 offsite power?
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 SI pumps.
C. Ensure theRHR pumps auto start.
Restart the SI pumps.
Ensure the CCPs auto start.
D. Place the CCPsin Pull-To-Lock.
Ensure the RHR and 81 pumps auto start.
Restart CC*Ps.
Page 12
1/2009 Sequoyah SRO NRC Exam
2/4/2009
13. Given the following:
-
Unit 1 is at 100%
RTP.
-
MeR alarms received indicate that an electrical board has failed.
-
All trip status lights on Panel 1-XX-55-5 (1-M-5) are OFF.
-
The crew responds 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.
B. 120 VAC Vital Instrument Board 1-1.
G. 120 VAC Vital Instrument Board 1-11.
D. 120 VAG Vital Instrument Board 1-11.
To prevent overcooling due to excessive
AFW flow due to the LCVs failing open.
To allow the turbine driven AFW pump to
be operated above minimum speed.
To prevent Qvercooling due to excessive
AFW flow due to the LCVs failing open.
To allow the turbine driven AFW pump to
be operated above minimum speed.
Page 13
1/2009 Sequoyah SRO NRC Exam
2/4/2009
14. Given the following conditions:
-
Unit 1 is at 100% power.
-
Unit 2 is in Mode 6 with upper internals removal in progress~
-
125V DC Vital Battery III output breaker tripped and can NOT be reclosed.
In accordance with 0-80-250-1, "125 Volt DC Vital Power System", which ONE of the
following describes the alignmenlwhen 125V 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 Bank V and Spare Charger 2-S aligned to the board.
C. 125V DC Vital Battery Bank V and Spare Charger 1-S ali.gned to the board.
D. 125V DC Vital Battery Bank V and 125vDC Battery Charger III to the board.
Page 14
1/2009 Sequoyah SRO NRC Exam
2/4/2009
15. Given the following:
Unit 1in service at 90%
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
1000/0 power for the past 360 days.
Unit2 in service at 100% 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 ide*ntifies which Unit should have the CCP temporary
cooling established first and the reason why?
A.
B.
c.
D.
Unit to have CCP temporary
Cooling Established First
Unit 1
Unit 1
Unit 2
Unit 2
Re.ason
Because Unit has higher decay
heat due to operating longer.
Because Unit is aligned
to supp.ly Spent Fuel Pit cooling.
Because Unit will have a faster CCS
heat up rate and is more time critical.
Because Unit has higher decay heat
since tripped from a higher power level.
Page 15
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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 Station 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 a*nd
wiU require manual alignment locally when needed.
D. Allows the LCVs to be OPENED during a Station Blackout event and
automatically supplied when air pressure drops below regulator setpoint.
Page 16
1/2009 Sequoyah SRO NRC Exam
2/4/2009
17. G*iven the following:
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 maximum allowable outgoing reactive load.
Which ONE of the following identifies the MAXIMUM outgoing reactive load in
accordance with GOI-5, "Apparatus. Operation", and the correct operation of th'e Exciter
Voltage Adjuster?
Maximum Outgoing.
Reactive Load
Exciter Voltage Adjuster
A.
240 MVARs
Lower
B.
240 MVARs
Raise
c.
300 MVARs
Lower
D.
300 MVARs
Raise
Page 17
1/2009 Sequoyah SRO 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 and 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.
Page 18
1/2009 Sequoyah SRO NRC Exam
2/4/2009
19. Given the following.:
Unit 1 is operating near EOl at 800/0 power.
Rod control is in AUTOMATI*C with Control Ban.k "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
individual rod RPls to be +/- 12 steps of the respective group step counter?
Direction
A.
Insert
B.
Insert
c.
Withdraw
O.
Withdraw
TIS Requirement to be +/- 12 steps o*t Step Counter
To maintain acceptable power distribution limits.
To ensure moderator-temperature coefficient remains
negative.
To maintain acceptable power distribution limits.
To ensure moderator temperature coeffi'cient remains
negative.
Page 19
1/2009 Sequoyah SRO NRC Exam
2/4/2009
20. Given the following:
Following a load reduction to 700/0 power, Contro*1 Bank "0" Rod M-8 was found
misa*ligned from its bank 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 how the Rod Control System will be operated to
realign the control rod in accordance with AOP-C.01?
Operators will disconnect the lift coil(s) for ...
A. the misaligned rod' and adjust the affected9IQ!!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 group (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 group step
counter to match the misaligned rod position.
Page 20
1/2009 Sequoyah SRONRC Exam
2/4/2009
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
GATe released thehandswitch after observing flow indicated on
1-FI-62-137A, Emerg Boration Flow.
-
Two minutes later, the DATC observed both 1-HS-62-138A RED and
GREEN lights LIT and flow stable at 50gpm.
Which ONE of the following identifies the status of FCV-62-138, Emergency
Boration FCV and the corresponding 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 a*nd the flow
rate is BELOW the minimum required.
D. should be full open but has stopped due to thermal overload and the flow
rate is ABOVE the minimum required.
Page 21
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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 Shutdown" alarms
Which ONE of the following indicates the rise in count rate required to cause the
alarm of the "Source Range High Flux Level At Shutdown" a-nnunciator and the
action(s) required if the alarm is valid?
A.
B.
c.
D.
Alarm
Setpoint
9 cps;
\\
9 cps;
18 cps;
18 cps;
Required Actions
Announce Qverthe PA system to evacuate containment
and notify the Refueling SRO to immediately suspend
ONLY notify the Refueling SRO to immediately suspend
Announce over the PA system to evacuate containment
and notify the Refueling SRO to immediately suspend
ONLY notify the Re-fuelin-g SRO to immediately suspend
core a-Iterations
Page 22
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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 mRlhr at 30 cm
Highest contamination reading of 3.6E3 dpm/1 00 cm2
Which ONE of the following describes the co*mbination of postings required for the area
and the radiological concern associated with the types of radiation?
Postings Required
A. Radiation Area;
Contamination Area
B. Radiation Area;
High Contamination Area
Contamination Area
High Contamination Area
Radiological Concern
Radiation is a ga*mma concern;
Contamination is a beta concern.
Radiation is a beta concern;
Contamination is a gamma concern.
Radiation is a gamma concern;
Contamination is a beta concern.
Radiation is a beta concern;
Contamination is a gamma concern.
Page 23
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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 combinations shows the expected status of the
indicating lights on 1-HS-26-75A after actuating the HPFP System?
A.
B.
c.
D.
OFF
LIT
LIT
LIT
WHITE
LIT
OFF
LIT
LIT
RED
LIT
LIT
OFF
LIT
Page 24
1/2009 Sequoyah SRO NRC Exam
2/4/2009
25. Given the following:
Unit 1 reactor tripped and a natural circulation cooldownwas required.
-
The LTOPs system was placed in service in accordance with ES-O.2, "Natural
Circulation Cooldown".
-
Su*bsequently, a faulted steam generator resulted in 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 Temperature fails LOW.
Which ON*E of the following describes the effect on the unit?
A.
PORV PCV-68-334 will open and remain open unless it is manuaHy closed.
B. PORV PCV-68-340 will open and remain open unless it is manually closed.
c. PORV PCV-68-334 will open until RCS pressure drops below the minimum LTOP
setpoint.
D. PORV PCV-68-340 will open .until ReS pressure drops below the minimum LTOP
setpoint.
Page 25
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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 ReS depressurization steps in ES-0.4, which ONE of the
following explains a function served by -using the Pressurizer heaters to
repressurize the RCS by 100 psig when Pres-surizer level exceeds 900/0?
A.
Promotes heat removal from the upper head re-gion of the vessel by
collapsing the steam void.
B.
Maintains Pressurizer conditions that allow restarting the Reactor Coolant
Pumps when power is restored.
c.
Provides exchange of liquid in the pressurizer to maintain Press-urizer and
ReS boron concentrations within 50 ppm.
D. Allows transfer of the upper head void into theRCS hot legs where the
ReS subcooledmass will collapse the void.
Page 26
1/2009 Sequoyah SRO NRC Exam
2/4/2009
27. Which one of the following states interlocks that must be met before valve FCV-72-23
(Train A ContainmentS*pray 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 FCV-72-22* (Containment
Spray Suction from RWST) must be closed.
Page 27
1/2009 Sequoyah SRO NRC Exam
2/4/2009
28. Given the following:
Unit 1 is at 100°/6 power.
-
Annunciator Panel 1-XA-55-5B, Window 8-5: "LS-68-34A1B REAC COOL
PMP 2 OIL RESERVOIR LEVEL HI-LOW" alarms.
Rep #2 motor bearing temperatures are within limits, stable, and being
monitored.
Reactor Building Pocket Sump level is 52%.
Which ONE of the following identify actions required by the Annunciator Response
Procedure?
A. Pump pocket sump level down and mO'nitor pocket sump level for significant
change in rate of rise.
Request Electri*cians 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 leve*1.
D. LO'ckout the pocket sump pumps to prevent pumping oil until status of Rep motor
bearing oil levels can be determined.
Place RCPLift Oil Pump in service until oil levels can be verified.
Page 28
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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.
-
VeT temperature is 115°F.
-
- 2RCP as the only RCP 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.
Page 29
1/2009 Sequoyah SRO NRC Exam
2/4/2009
30. Given the following:
-
Operators are responding to a small break LOCA on Unit 1 in
acc.ordance 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 cves charging and letdown isolation
valves automatically respond to the given plant conditions?
1-FCV-62-90
1-FCV-62-69
Charging F*CV Isolation
Letdown Isolation
A.
OPEN
OPEN
B.
OPEN
CLOSED
C.
CLOSED
OPEN
D.
CLOSED
CLOSED
Page 30
1/2009 Sequoyah SRO NRC Exam
2/4/2009
31. Plant conditio'ns are as follows:
-
Unit 1 is in Mode 4.
RHR*Train "A" is in service per 0-80-74-1, "Residual Heat Removal
Syste~".
-
ReS temperature is stable at the current RHR flow rate.
Wh.ich ONE of the following 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 Instrument Power Board 1-11.
D. 480V Shutdown Board 1A1-A.
Page 31
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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?
VALVE
POSITION
A.
FCV-63-25, CCPIT Outlet Valve
Closed
B. LCV-62-133, VeT Outlet Valve
Open
C. FCV-62-98, CCP Miniflow Valve
Open
D. FCV-74-16, RHR Heat Excho. Outlet Valve
Closed
Page 32
1/2009 Sequoyah SRONRC Exam
2/4/2009
33. Given the following:
-
Unit 1 is operating at 100% power.
-
Annun*ciator Panel 1-XA-55-5A, Window D-1: "PS-68-301 PRESSURIZER
RELIEF TANK PRESS HIGH" alarms.
-
The OATCobserves the following conditions:
-
PRT pressure is 8.5 psig and slowly rising.
-
PRT temperature is 104°F and stable.
-
PRT level is 72%.
Which ONE of the following describes (1) the reason for the h:igh pressure and (2) the
action required?
A. Nitrogen re*gulator leak
B. Nitrogen regulator leak
c. Letdown relief lifted
D. Letdown relief lifted
Reduce PRT pressure by reducing level
Vent the PRT to the Waste Gas Vent Header
Reduce PRT pressure by reducing level
Vent the PRT to the Waste Gas Vent Header
Page 33
1/2009 Sequoyah SRO NRC Exam
2/4/2009
34. Given the following:
-
Both Units are at 100% RTP.
-
The CCS System is in a normal alignment with the 1A-A, C-S, and 2B~B
pumps in service.
-
CCS Pumps 1B-B and 2A-A are in A-AUTO.
-
6.9kvShutdown 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 pum*ps that are load shed and the
pum*ps that are running after load sequencing is complete?
Load Shed
Following Load Sequencing
A.
Only the 1A-A
Only 1A-*A, C-S, and 2B-B
B.
Only the 1A-A
1A-A, 18-8, C-S, and 2B-B
C.
Both 1A-A & C-S
D.
Both 1A-A &C-S
Page 34
1/2009 Sequoyah SRO NRC Exam
2/4/2009
35. Given the following:
-
Unit 1 is at 100%
power.
-
VCT pressure is at 18 psig.
Which ONE of the following identifies the location of a CCS leak that would
result in the condition listed below?
LEAK LOCATION
CONDITION
A. RCP Thermal Barrier
TBBP in A-P auto starts
B. Letdown Heat Exchanger
CCS Rad Monitor rising
CCS Surge Tank level rising
D. Seal Return Heat Exchanger
VeT level dropping
Page 35
1/2009 Sequoyah SRO NRC Exam
2/4/2009
36. Given the following:
Unit 1 is at 100% 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 tripout alarm
and
(2) the actio*n associated with 1-PIC-68-340A, "Pressurizer Pressure Control"
that could be taken to restore Pressurizer pressure?
A. (1) Centrifug*al 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) Press'urizer heater Control Group D.
(2) Lower the controller output.
Page 36
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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. MCBindication is lost and the reactor trip breaker trips OPEN due to loss of
power to the SHUNT coil.
C. MCB indication remains lit. The* reactor trip breaker is NOT capable of
tripping on a SHUNT trip.
D. MCB ind*ication remains lit. The reactor trip breaker trips OPEN due to loss
of power to the SHUNT coil.
Page 37
1/2009 Sequoyah SRO NRC Exam
2/4/2009
38. Given the following:
Unit 2 was in Mode 3 performing Shutdown Bank withdrawal.
-
Three (3) minutes ago, Safety Injection actuated when a Pressurizer PORV
inadvertently opened before the PORV block valve was closed.
B-oth reactor trip breakers failed to OPEN.
-
The reactor was tripped locally by opening theM-G set motor supply
breakers per FR-S.1, "Response to Nuclear Power Generation/ATWS".
Pressurizer pressure is currently 1940 psig.
Bypa-ss and Permissive 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
re-presents the correct annunciator status and associated reason following the
reset of Safety Injection for the above conditions?
A.
81 ACTUATED will remain LIT because P-11 Perm-issive has NOT been met.
B.
81 ACTUATED will remain LIT because Pressurizer pressure is less than the SI
setpoint.
C. AUTO SI 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.
Page 38
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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
Page 39
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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 SRO NRC Exam
2/4/2009
41. Which ONE of the following identifies an ice condenser door that would require
entering a1 hour Technical*Specification LeO 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
physically restrai.ned from opening
A. Only an inlet door
B. Only an inlet door
c. Either an inlet or
intermediate deck door
D. Eith:er an inlet or
intermediate deck door
Doors equipped with
flow proportioning springs
Inlet doors
Intermediate doors
Inlet doors
Intermediate doors
Page 41
1/2009 Sequoyah SRO NRC Exam
2/4/2009
42. Given the following:
Unit 1 and Unit 2 6.9kV Shutdown Boards are aligned as follows:
1A-A from normal feed
1B-B from normal feed
-
2A-A from alternate fe*ed
-
28-8 from normal feed
Diesel Generator 28-8 is tagged for maintenance.
-
6.9kV Unit 8oard2C is de-energized due to a fire.
Which ONE of the following has lost power?
C. Containment Spray Pump 28-8
D. Residual Heat Removal Pump 2A-A
Page 42
1/2009 Sequoyah SRO NRC Exam
2/4/2009
43. Given the following conditions:
Unit 1 is operating at 100% power.
1A-A Conta*inment Spray (CS) Pump is out of service.
-
A large break LOCA occurs
1B-B RHR Pump trips on instantaneous overcurrent and is damaged.
-
60 minutes later, the following conditions exist:
-
Containment pressure is1 0 psig.
-
FR-Z.1, "High Containment Pressure" is in progress.
-
ES-1.3, "Transfer To RHR Containment Sump" has been completed.
-
The crew observes 1B-B CS Pump running 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 and RHR spray should be placed in service.
B. Containment spray flow is normal and RHR spray s*hould NOT be placed in service.
C. Containment spray flow is LOWER than normal and RHR spray should be placed in
service.
D. Containment spray flow is LOW*ER than normal and RHR spray should NOT be
placed in service.
Page 43
1/2009 Sequoyah SRO NRC Exam
2/4/2009
44. Given the following:
Plant startup in progress with MSIVs and bypass valves closed.
RCS at 2235 psig and 547°F.
-
The crew began warming the main steam lines and observed the following
ReS 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
A.
Tech Spec limit was exceeded
B.
Tech Spec limit was exceeded
C.
Maintained within the Tech Spec limit
D.
Ma*intained within the Tech Spec limit
Limiting Component
Reactor*Vessel
Steam Generator Tube Sheet
Reactor Vessel
Steam Generator Tube Sheet
Page 44
1/2009 Sequoyah SRO NRC Exam
2/4/2009
45. Given the following:
Unit 1 is at 100% 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, RCS Tcold will decrease, and reactor power will
increase.
B.
SG NR levels wiU decrease, RCS Tcold will decrease, and reactor power will
decrease.
C.
SG NRlevels will increase, RCS Tcold will increase, and reactor power will
increase.
D.
SG NR levels will increase, RCS Tcold will increase, and reactor power will
decrease.
Page 45
1/2009 Sequoyah SRO NRC Exam
2/4/2009
46. Given the following conditions:
Unit 2 is initially at 1000/0 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 followi.ng 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 high primary-to-secondary differential pressure.
c. Challenge to PZR PORVsand safety valves due to overpressure transient
in the RCS.
D. Overpower condition due to the failure of the turbine to receive a trip
signal.
Page 46
1/2009 Sequoyah SRO NRC Exam
2/4/2009
47. Given the fol.lowing:
i
. I
f
't
'.
+ I\\'iUa~
Dowe(l
-
A reactor trip occurred on Unit 1;
,:.,Jh' Ie
T~l U"'/
tVA $. A
f"
"
-
The only operator action taken was to manually close the LCVs to 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 co*ndenserhotwell
c. 165 GPM to the CST
D. 165 GPM to the condenser h*otwell
Page 47
48.
1/2009 Sequoyah SRO NRC Exam
2/4/2009
Given the fol*lowing:
-
Loss of off site power occurred on Unit 1 resulting in a Reactor Trip
and Safety Injection.
-
The Emerge*ncy Diesel Generators (DGs) started and DG 1A-A
loaded to 4.6 MWs.
In accordance with AOP-P.01, "Loss of Offsite Power", which ONE of the
following describes the 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 SRO NRC Exam
2/4/2009
49. Given the following:
Unit 2 at 100% power.
PaneI2-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 occurs on high PZR pressure.
Which ONE of the following identifies the- allowed usage of AOP--P.02 after
the Emergency Operating Procedure network is entered following the reactor
trip?
Continued performance of AOP-P.02 is ...
A. all-owed after the crew enters ES-0.1, "Reactor Trip Response" because
ES-0.1 is NOT an accident mitigation EOP.
B. allowed after the crew enters ES-0.1, "Reactor Trip Response" 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 ded-icated to the EOP in
effect until the EOPs are exited.
D. NOT allowed until the crew exits ES-0.1, "Reactor Trip Response"
bec-ause actions taken in AOP-P.02 could degrade the performance of
the EOP.
Page 49
1/2009 Sequoyah SRO NRC Exam
2/4/2009
50. Given the following:
DIG 1A-A is running at 4.4 MW for surveilla.nce testing.
-
DIG Day Tank levels are as follows:
1A1 - 250 gallons
1A2 - 300 gallons
Neither Fuel Transfer Pump 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 SRO NRC Exam
2/4/2009
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 0-M-26.
B. Diesel Generator 2B~B could only be sh'utdown using the Local Panel
EME'RGENCY STOP pushbutton at the DG Building.
c. All engine trips except for overspeed 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
28-B would be disabled and ALL engine trips would remain enabled.
Page 51
1/2009 *Sequoyah SRO NRC Exam
2/4/2009
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 B" 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 "101B" 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 B" 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 "1018" position and pushed in.
(2) 1-RM-90~130A could NOT be blocked without pulling the HI RAD relay.
Page 52
1/2009 Sequoyah SRO NRC Exam
2/4/2009
53. Given the following Unit 1 conditions:
-
All ERCW pump controls are in a normal preferred alignmentper 0-SO-67-1,
"Essential Raw Cooling Water".
ERCW Pump L~~ trips.
-
Train "B" ERCW header stabilizes at 68 psig.
-
TheCRO 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 ERCW PumpN-B. Reposition O-XS-67-286, DG Power Selector
Switch.
B. Ma-nually start ERCW Pump N-B-. Do NOT reposition switch O-XS-67-286, DG
Power SelectorSwitch.
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
0-XS-67-286, DG Power Selector Switch.
Page 53
1/2009 Sequoyah SRO NRC Exam
2/4/2009
54. Given the following:
Unit 1 is in Mode 5 with 6.9kVShutdown Board 1A-A tagged for maintenance.
Subsequently, 6.9kV Shutdown Board2B-B trips and locks out due to
relay operation.
Which ONE of the following identifies the status of the 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 SRO NRC Exam
2/4/2009
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) thecondition(s) required prior to the valves being manually re~opened?
A. (1) Only.a containment pressure rise to 1.5 psid relative to the annulus;
(2) Containment pressure must be. less than 1.0 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) I*nitiation 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 press'ure must be less than 1.0 psid and safety
injection must be reset.
Page 55
1/2009 Sequoyah SRO NRC Exam
2/4/2009
56. Given the following:
Unit 1 is -at -850/0 -power steady-state.
Rod control is in MANUAL.
ReS 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
A.
Drops until letdown isolates.
B.
Drops until letdown isolates.
c.
Stabilizes before letdown
isolates.
D.
Stabilizes before letdown
isolates.
Pressurizer Pressure
Drops due to heaters deenergizing.
Rises due to level- rising after letdown
isolates.
Stabilizes with variable heaters energized.
Stabilizes with spray valves opening.
Page 56
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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, Window 0-7: "FULL LENGTH RODS RODS AT
BOTTOM" for the above conditions?
H-8 Rod Bottom Light
A. LIT before the rod dropped and
remained LIT after the rod dropped.
B. LIT before the rod dropped and
remained LIT after the rod dropped.
C. DARK before the rod dropped and
LIT after the rod dropped.
D. DARK before the rod dropped and
LIT after the rod dropped.
Annunciator 0-7
In alarm
NOT in alarm
In alarm
NOT in alarm
Page 57
1/2009 Sequoyah SRO NRC Exam
2/4/2009
58. Given the following:
Unit 1 is at 100°10 power.
Power Range Channel NI-44 fails due to a loss of instrument power.
Which ONE of the following identifies the impact the failure of NI-44 has on
Annunc'iator Panel 1-XA-55-4B, Window D-4: "COMPUTER ALARM ROD DEV& 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. An AFD alarm, but the window does NOT have reflash capability for alarms from
other sources.
C. A QPTR alarm and the window ha's reflash capability for alarms from other sources.
D. A QPTRalarm, but the window does NOT have reflash capability for alarms from
other sources.
Page 58
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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
(1-L-10)
A. Controller functions and the flow
indication reads only with Nor-Aux
switch in AUX.
B. Controller functions and the flow
indication reads o*nly with Nor-Aux
switch in AUX.
c. Controller functions only with
Nor-Aux switch in AUX.
Indication reads with Nor-Aux
switch in either position.
D. Controller functions only with
Nor-Aux s'witch in AUX.
Indication reads with Nor-Aux
switch in either position.
Locally in the Aux Building
(1-L-112A)
No control function on panel,
flow indication only
Panel has both controller
function and flow ind*ication
No control function on panel,
flow indication only
Panel has both controller
function and flow indication
Page 59
1/2009 Sequoyah SRO NRC Exam
2/4/2009
60. Given the fall-owing:
Unit2 operating at 100/0 reactor power.
-
CONDITION 1: Two hours following a reactor trip and trip of all RCPs.
-
CONDITION 2: Two hours following a reactor trip with all RCPs running.
W.hich 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?
CO*NDITION 1
CONDITION 2
(No Reps)
(ALL RCPs)
A. TCs only slightly
TCs only slightly
above Tcold
above Tcald
B. TCs only slightly
TCs several degrees
above Tcald
greater than Tcold
C. Tes several degrees
TCs only slightly
greater than Tcold
above Tcold
D. Tes several degrees
TCs several degrees
greaterthan Tcold
greater than Tcold
Page 60
1/2009 Sequoyah SRO NRC Exam
2/4/2009
61. Which ONE of the following is the powersupply to the Emergency Gas Treatment
System (EGTS) Fan B?
A.
C &A Vent Board 1B1-B
B. C & A Vent Board 281-8
c. Reactor Vent Board 1B-B
D. Reactor Vent Board 28-B
Page 61
1/2009 Sequoyah SRO NRC Exam
2/4/2009
62. Given the following:
Unit 1 is at 500/0 power and stable when a transient occurs.
-
The CRO reports the following parameters and trends for SG #1 with similar
trends on the other SG's:
- SG Pressure:
860 psig and lowering
- SG Level:
46%
and rising
- SGSteam Flow:
2.0 x106 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 SRO NRC Exam
2/4/2009
63. Given the following:
-
Unit 1 is at 100/0 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 SRO NRC Exam
2/4/2009
64. Given the following:
-
Unit 2 is operating at 1160 MWe.
-
Generator reactive load is 325 MVARs incoming.
-
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 SRO NRC Exam
2/4/2009
65. Given the following:
-
Waste Gas Decay Ta*nk A is "IN SERVICE".
-
Waste Gas Decay Tank D is in "STANDBY MODE".
-
An automatic transfer occurs from WGDT A to WGDT D.
-
An AUG dispatched to respond to the transfer reports the following:
-
WGDT A pressure is 120 psig.
-
WGDTD pressure is 9 psig.
Which ONE of the following describes BOTH the transfer from WGDT A to
WGDT 0 and the status of the WGDT 0 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 D pressure needs to be raised by adding nitrogen to the tank.
c. The transfer occurred past the automatic swapover setpoint .
WGDT D pressure is above the minimum pressure to be "IN SERVICE".
D. The transfer occurred past the automatic swapover setpoint.
WGDT 0 pressure needs to be raised by adding nitrogen to the tank.
Page 65
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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 from E-O, "Reactor Trip or Safety Injection" to
anoth-er ERG procedure.
c. W-hen directed to by a step in ES-O.1, "Reactor Trip Response".
D. When directed to by a step in ES-O.5, "Equipment Verifications".
Page 66
1/2009 Sequoyah SRO NRC Exam
2/4/2009
67. Which ONE of the following identifies the items in the list below that are
required to be reviewed by an oncoming OATC during Shift Turnover in
accordance with OPDP-1, "Conduct of Operations"?
1. Abnormal equipment lineup/conditions
2. SI/Test 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
Page 67
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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.
Page 68
1/2009 Sequoyah SRO NRC Exam
,2/4/2009
69. Given the following plant conditions:
U.nit 1 in Mode 5.
1-FCV-62-93, "Charging Flow Control Valve", is selected as a
boundary isolation valve for a clearance on the CVCS charging header.
In accordance with SPP-10.2, "Cle*arance 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 is*o*lation valve and the handswitch.
B.
Close the valve, install a jacking device, isolate the air supply and tag both
the jacking device and 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.
Page 69
1/2009 Sequoyah SRO NRC Exam
2/4/2009
70. Given the following:
Both Units are at 1000/0 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 average ERCW temperature
allowed without entering a Technical Specification LeO, and the LCO that would be
entered if the temperature was exceeded?
A.
B.
C.
D.
Maximum Allowed
Temperature
Leo
Entered
3.7.4, Essential Raw Cooling Water System
3.7.5, Ultimate Heat Sink
3.7.4, Essential Raw Cooling Water System
3.7.5, Ultimate Heat Sink
Page 70
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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.
S.
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 automaticallyisol*ate.
D.
RM-90-120/121 ,Steam Generator Slowdown Sample Monitor. The monitor
will NOT automatically isolate.
Page 71
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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 x105 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.
Site Emergency Director
C.
Plant Manager
D.
Site Vice President
Page 72
1/2009 Sequoyah SRO NRC Exam
2/4/2009
73. Given the following:
Unit 2 was at.1 00%
power when an 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. GATC
C. Unit Supervisor
D. Shift Manager
Page 73
1/2009 Sequoyah SRO NRC Exam
2/4/2009
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
following 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 FR-S.1.
C. Complete FR-H.1, then implementtoFR-Z.1.
D. Complete FR-H.1, then implement to FR-S.1.
Page 74
1/2009 Sequoyah SRO NRC Exam
2/4/2009
75. Given the following:
-
The Unit 1 CRO is 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 theCRO and the AUOfoliowing the initiation
of Assembly and Accountability.
A. CRO - Report to the Main Control Room, swipe badge in the MCR card reader.
A*UO - Swipe badge in the Cafeteria card reader, and report to the OSC.
B. CRO - Report to the Main Control Room, swipe badge in the MCR card reader.
AUO - Report to the Main Control Room, swipe badge in the MCRcard 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. CRG - 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
1/2009 Sequoyah SRO NRC Exam
2/4/2009
76. Given the following:
Unit 1 at 1000/0 power wh'en a pressurizer safety valve failed open.
-
The operator manually tripped the reactor and initiated a safety
injection.
-
While performing the step to determine if the RHR spray should
be placed in servi'ce in accordance with *E-1, "Reactor Trip or Safety
Injection", the crew determines the following:
-
When*pressurizer pressure drapped to 1280 psig, the safety valve
reclosed and pressurizer pressure started to rise.
Containment pressure rose to 2.6 psig, and began trending down.
Pressurizer level is 100%
RCS subcooling is 43°F.
-
All four SG levels at 33%
narrow range.
Which ONE of the following identifies the correct procedure implementation
and operation of the RCPs for the above conditions?
A. Transition from E-1 to ES-1.1, SITermination;
The RCPs will have. remained running throughout the event.
B. Transition fromE-1 to ES-1.1, SI Termination;
The RCPswould have been shutdown but wi-ll be restarted in ES-1.1, SI
Termination.
c. Continue E-1 until a transition is directed to ES-1.2, Post LOCA Cooldown;
The RCPs will have remained running throughout the event.
D. A transition will be made to ES-1.2, Post LOCA Cooldown;
The RCPs would have been shutdown but will be restarted in ES-1.2, Post LOCA
Cooldown.
Page 76
1/2009 Sequoyah SRO NRC Exam
2/4/2009
77. Given the following:
-
Unit 1 is operating at1 00%
power*when a loss of offsite power occurs.
-
The operators subsequently initiate Safety Injection due to a small break LOCA.
-
Th*irty minutes after the Safety Injection, the following conditions exist:
-
E-1, "Loss of Reactor or Secondary Coolant" is being performed.
-
All 4 SG pressures are approximately 1010 psig and stable.
-
ReS pressure is 2230psigand stable.
-
Thot is approximately 575°F in all 4 loops and lowering slowly.
-Core Exit Tes indicate approximately 580°F and slowly rising.
-
Tcold is approximately 560°F in all 4 loops and stable.
Based on the above indications, which ONE of the following identifies the condition of
the ReS and the procedure transition that will be directed?
A. Natural Circulation exists anda transition will be directed to ES-O.2, "Natural
Circulation Cooldown" as the E-1 procedure is continued.
B. Natural Circulation exists and a transition will be directed to ES-1.2, "Post LOCA
Cooldown" as the E-1 procedure is continued.
C. Natural Circulation does NOT exist and a transition will be directed to ES-O~2,
"Natural Circulation Cooldown" as the E-1 procedure is continued.
D. Natural Circulation does NOT exist and a transition will be directed to ES-1.2, "Post
LOCA Cooldown
ll as the E-1 procedure is continued.
Page 77
1/2009 Sequoyah SRO NRC Exam
2/4/2009
78. Given the following:
Unit 1 is at 100% power.
RHR Pump 1B-B is tagged for motor bearing maintenance.
-
A Safety Injection occurs due to a LOCA.
RHRPump 1A-A trips on instantaneous overcurrent.
-
Thirty minutes after the LOCA, the crew tran*sitions from E-1, "Loss of
Reactor or Secondary Coolant", to E*CA-1.1, "Loss of RHR Sump
Recirculation".
-
The following conditions are noted:
RCS pressure is currently 230 psig
RWST level is 5.4%
and .dropping
-
The lowest RCS Tcold is 228°F.
Which ONE of the following describes the required operator action?
A transition to FR-P.1, "Pressurized Thermal Shock" is...
A. NOT required due to the ECA-1.1 entry.
B. required but should NOT be made until transfer to the containment sump is
accomplished.
C. NOT required because RCS pressure is less than 300 *psig.
D. required but a transition back to ECA-1.1 will be directed due to no RHR
pump running.
Page 78
1/2009 Sequoyah SRO NRC Exam
2/4/2009
79. Given the fol*lowing:
-
Unit 1 is at 32%
power.
-
The following annunciator windows alarm on 1-M-6:
-
FS-68-48AREACTOR COOLANT LOOP 3 LOW FLOW
-
RCP BUS UNDERFREQUENCY / UNDERVOLTAGE
-
RCP #3 indications are:
-
Ammeter - '0' amps.
-
Gree'n and white lights above the handswitch are lit.
-
Flow - '0' on all 3 indicators.
-
The other Reps remain in service and the reactor trip breakers remain closed.
-
The GATC ma.nuaHy trips the reactor as directed by the SRO.
Which ONE of the follow*ing identifies the condition causing the RCP trip and the
earliest NRC notification required by1 OCFR50.72?
Condition causing Rep Trip
Notification Requirement
A.
Under voltage
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
B.
Under voltage
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
c.
Under frequency
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
D.
Under frequency
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
Page 79
1/2009 Sequoyah SRO NRC Exam
2/4/2009
80. Given the following:
Unit 1 is in Mid-Loop Operation in accordance with GO-13," Reactor
Coolant System Drain and FHI Operations" with the reactor core reloaded.
RHR Train A in service.
-
SG nozzle dams are installed.
-
SI pump 1"B-8 is tagged and disassembled for impeller replacement
-
CCP 1A-A trips due to motor failure.
RCS level begins to drop and the RHR pump 1A-A is stopped due to
cavitation.
-
Attempts to open 1-FCV-63-1, RHR Pum'p Suction from RWST, are
unsuccessful.
-
Core exit thermocouples have increased to 20SoF.
Which ONE of the following identifies the procedure to be used and how SI pump IA~A
will be aligned during performance of the procedure?
Sipumps will be aligned for Hot Leg injection.
SI pumps will be prevented from injecting due to LTOP requirements.
C. AOP-R.03, "RHR System Malfunction".
SI pumps will be aligned for Hot Leg injection.
D. AOP-R..03, "RHR System Malfunction".
SI pumps will be prevented from injecting due to LTOP requirements.
Page 80
1/2009Sequoyah SRO NRC Exam
2/4/2009
81. Given the following:
Unit 2 is operating at 1000/0 power with the: switchyard in a normal alignment.
-
Generator is operating at 24 KV and +150 MVAR.
-
An electrical'disturbance on the grid occurs causing the following annunciators
to alarm:
-
on 0-XA~55-ECB6-A;
"GEN 2 MVAR ABNORMAL OR MVAR RELAY FAILURE"
"OSCILLOGRAPH OPERATION OR FAILURE"
-
on 0-XA~55-ECB6-B;
-
on 2-XA-55-1A
"GEN VOLT REGULATOR TRIP"
-
The BLUE light on "161 KV CONCORD LINE CARRIER RECEIVED" is lit.
Rea.ctive power stabilized at +230 MVARS following the disturbance
and Concord line PCB in theswitchyard remains closed.
Which ONE of the following statements describes required actions?
A. Manually open the Concord line PCB.
Notify the Southeast Area Load Dispatcher to evaluate offsite power voltage
requirements.
B. Manually open the Concord line PCB.
Declare both trains of Offsite power inoperable until the Southeast Area Load
Dispatcher completes evaluation of offsite power voltage requirements.
c. Notify the Southeast Area Load Dispatcher to evaluate offsite power voltage
requirements.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the Operations Duty Spe'cialist of the time period the
unit was without automatic voltage control.
D. Declare both trains of *Offsite power inoperable until the Southeast Area Load
Dispatcher completes evaluation of offsite power voltage requirements.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the Operations Duty Specialist of the time period the
unit was without automatic voltage control.
Page 81
1/2009 Sequoyah SRO NRC Exam
2/4/2009
82. Given the following:
0900 -
0902 -
0915 -
0915 -
11-30 -
Conditions require the Unit 2 Main Control Room (MCR) to be
abandoned.
All MCR actions of AOP-C.04, "Shutdown From Auxiliary Control
Room" have been completed and the crew leaves the MCR.
The crew establis*hes control in the Auxiliary Control Room.
Tech Spec 3.0.3 is entered.
The crew initiates a natural circulation cooldown and* the following
5G pressure trends are observed.
Time
1130
-
1150
-
1210
-
1230
-
1250
-
SG Pressures
1040 psig
825 psig
550 psig
470 psig
385 psig
Which ONE of the following identifies...
(1) whether the ReS coolqown rate has violated the Tech Spec limit
and
(2) the latest time allowed by Tech Specs to place the unit*in Mode 5?
A. (1) Cooldown rate limit has been violated.
(2) 1515 the next day.
B. (1) Cooldown rate limit has been violated.
(2) 2215 the next day.
c. (1) Cooldown rate limit has NOT been violated.
(2) 1515 the next day.
D. (1) Cooldown rate limit has NOT been violated.
(2) 2215 the next day.
Page 82
1/2009 Sequoyah SRO NRC Exam
2/4/2009
83. Given the following conditions:
Unit 1 is in Mode 3 with RCS at normal operating pressure and
temperature awaiting secondary plant equipment repair to continue the
startup.
-
At 1300 on 01/25/09 RCS Activity was determined to be 0.38
microcuries/gram DOSE EQUIVALENT 1-131.
-
At 1300 on 01/27/09 Chemistry reports thatthe RCS Activity has been on
a continuous slow increase and is now 0.43 microcurieslgram DOSE
EQUIVALENT 1-131.
Which ONE of the following identifies actions that are required by 1900 on
01/27/09 and the bases for the RCS Specific Activity limit?
A. Reduce RCS Tavg below 500°F to limit doses at the site boundary in the event of a
LOCA in conjunction withO.25La leakage from containment.
B. Reduce RCS Tavg below 500°F to limit doses at the site boundary in the eventof a
SGTR in conjunction with steady state SG tube leakage of 1 gpm.
C. Reduce RCS Tavg below 350°F to limit doses at the site boundary in the event of a
LOCA in conjunction with O.25La leakage fro.m containment.
D. Reduce RCS Tavg below 350°F to limit doses at the site boundary in the event of a
SGTR in conjunction with steady state SG tube leakage of 1 gpm.
Page *83
1/2009 Sequoyah SRO NRC Exam
2/4/2009
84. Given the following:
Unit 2 is operating at 100% power when a loss of Train A CCS occurs.
-
The crew enters AOP-M.03, "Loss of Component Cooling Water", and
initiates a Reactor trip.
-
As the crew is performing the Immediate Operator Actions of E-O,
"Reactor Trip or Safety Injection", an automatic Safety Injection occurs.
-
The crew performs E-O to the last step without identifying a transition.
Which ONE of the following identifies both the correct use of the Emergency
Procedure 'and the proper crew action relative to the use of the Abnormal
Operating Procedure?
Emergency
Instructions
A.
Loop back in E-O to
re-perform steps to
identify a transition.
B.
Loop back in E-O to
re-perform. steps to
identify a transition.
c.
Transition to ES-O.O,
"Rediagnosis", and identify
the proper transition.
D.
Transition to ES-D.O,
"Rediagnosis", a.nd identify
the proper transition.
Abnormal Operating
Procedures
AOP-M.03 can NOT
be implemented in
in parallel with E-O.
AOP-M.03 can
be implemented in
parallel with E-O.
AOP-M.03 can NOT be
implemented in parallel
with ES-O.O, "Rediagnosis".
AOP-M.03 can be
implemented in parallel
with ES-O.O, "Rediagnosis".
Page 84
1/2009 Sequoyah SRO NRC Exam
2/4/2009
85. Given the following:
Unit 1 is at 100%
power.
-
A LOCA occurred inside containment.
-
The ctew has just implemented E-1, "Loss of Reactor or Secondary
Coolant".
-
The STA has completed the initial performance of the status trees and
reports the highest priority path exists on the CONTAINMENT status
tree.
Containment conditions are as follows:
Pressure is 2.6 psig and lowering.
Upper containment Rad Monitors read 85 Rlhr.
Lower containment Rad Monitors read 125 Rlhr.
Containment Sump Level is 58%.
Based on the above conditions, the Unit Supervisor ...
A. is required to IMMEDIATELY implement and complete FR-Z.2,
"Containment Flooding", then transition back toE-1.
B. will acknowledge entry criteria forFR-Z.2, "Containment Flooding", is met
but entry into the FR is optional.
C. is required to IMMEDIATELY implement and complete FR-Z.3, "High
Containment Radiation", then transition back to E-1.
D. will acknowledge entry criteria for FR-Z.3, "High Containment Radiation", is
met but entry into the FR is optional.
Page 85
1/2009 Sequoyah SRO NRC Exam
2/4/2009
86. Given the following:
Unit 1 in Mode 3 with RCS at normal operating temperature and
pressure.
Reps #1 , #2 and #3 'are running.
Following the start of RCP#4, the pump stabilizes as follows:
-
Motor current at 625 amps.
-
- 1 sealleakoff at 1.1 gpm.
-
AU 'pump and motor temperatures stable and within limits.
-
The operators implement AOP-R.04, "Reactor Coolant Pump
Malfunctions".
Which ONE of the following identifies why AOP-R~04 entry was required and
the action directed by the AOP?
A. The AOP was entered due to the high motor current and the AOPwill direct
removal of the Rep from service.
B. The AOP was entered due to the high motor current but the AOP will NOT
direct removal of the RCP unless bearing or stator temperatures are
increasing.
C. The AOP was entered due to the low #1sealleakoff flow and the AOP will
direct removal of the RCP from service.
D. The AOP was entered due to the low #1 sealleakoff flow but the AOP will
NOT direct removal of the Rep unless lower bearing or seal water
temperatures are increasing.
Page 86
1/2009 Sequoyah SRO NRC Exam
2/4/2009
87. Given the following:
Unit 1 at 100% power with, Containment Spray Pump 1A-A out of
service and tagged.
-
A LOCA results in a Reactor Trip and Safety Injection.
-
After transferring to the containment sump the crew observes the amps
fluctuating on Containment Spray Pump 1B-B.
In response; the crew stops the pump and transitions to
ECA-1.3, "Contai'nmentSump Blockage".
-
The STA reports a RED path to FR-Z.1, "High Containment
Pressure".
Which ONE of the following identifies the condition that results in the restartof
Containment Spray Pump 1B-B and what would be the desired flow rate?
A. Due to implementing FR-Z.1 , the pump will be restarted and the desired flow rate is
the DESIGN spray' flow due to the challenge to the Containment Barrier.
B. Due to implementing FR-Z.1 , the pump will be restarted and the desired flow rate is
the MINIMUM spray flow required to control containment pressure provided it does
not cause the RHR pump to cavitate.
C. Due to implem'enting ECA-1.3, the spray pump can be restarted after TSC
evaluation and the desired flow rate is the DESIGN spray flow due to the challenge
to the Containment Barrier.
D. Due to implementing ECA-1.3, the spray pump can be restarted after TSC
evaluation and the desired flow rate is the MINIMUM spray flow required to control
containment pressure provided it does not cause the RHR pump to cavitate.
Page 87
1/2009 Sequoyah SRO NRC Exam
2/4/2009
8'8. Given the following:
Unit 1 is at '1 00%
power when a LOCA occurs.
-
The reactor trips when the containment pressure rise causes a Safety Injection.
-
The EOP network is entered.
RCS pressure stabilizes at 1580 psig.
Containment pressure rises to 2.4 psig and stabilizes.
-
The crew is in the process of terminating Safety Injection.
-
When determining if the Sipumps should be stopped the following is noted:
Res pressure is now 1540 psig and trending down.
RCS subcooling is 43°F.
Pressurizer level is 19%
and dropping.
-
SG pressures:
- 1 - 590 psig and dropping.
- 2 - 600 psig and dropping.
- 3 - 580 psig and dropping.
- 4 - 605 psig and dropping.
Which ONE of the following identifies the status of the MSIVs and the propercrew
response to the conditions?
A. The MSIVs have failed to automatically close.
SI Reinitiation Criteria does NOT exist, a transition should be made to E-2, Faulted
Steam Generator Isolation.
B. The MSIVs have failed to automatically close.
SI Reinitiation Criteria exists, restart the CCP, establish CCPIT flow and Go To E-1,
Loss of Reactor or Secondary Coolant.
C. MSIV automatic closure signal should NOT have been initiated.
81 Reinitiation Criteria does NOT exist, a transition should be made to E-2, Faulted
Steam Generator Isolation.
D. MSIV automatic closure signal should NOT have been initiated.
SIReinitiation Criteria exists, restart the CCP, establish CePIT flow and Go to E-1,
Loss of Reactor or Secondary Coolant.
Page 88
1/2009 8equoyah 8RO NRC Exam
2/4/2009
89. Given the following:
Unit 1 is operating at 100% power
Diesel Generator 1B-B is out of service and is expected to return to
service in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Subsequently, the following events occur:
-
A loss of offsite power occurs.
The reactor trips and the crew enters the emergency procedures.
81 is NOT actuated.
The crew transitions toFR-H.1, "Loss of Secondary Heat Sink"
due to a RED Path condition and is performing the first step.
A fault on Shutdown Board 1A-A results in the emergency supply breaker
from Diesel Generator 1A-A tripping due a differential relay.
Which ONE of the following identifies the correct action to be taken and the bases for
the action?
A. Transition to ECA-O .0, "L*oss of All AC Power" because the ECA will direct
actions to establish heat sink with the TDAFW pump.
B. Remain in FR-H.1 to recover and establish a heat sink with the TDAFW
pump because restoring heat sink is the highest priority evolution in
progress.
c. Transition to ECA-O .0, "Loss of All AC Power" because all other procedures in the
EOPnetwork assume a minimum of at least one 6.9kV Shutdown Board is
available.
D. Remain in FR~H.1 and initiate EA-202-4, "Emergency Use of 6900 V
Shutdown Utility Bus" to energize Shutdown Board 1B-B because restoring
heat sink is the highest priority evolution in progress.
Page 89
1/2009 Sequoyah SRO NRC Exam
2/4/2009
90. Given the following plant conditions:
-
Both Units operating at 100% power.
-
ERCW system in normal alignment.
-
The following annunciators are LIT on Essential Raw Cooling
Water 0-XA-55-27A panel on 1-M-27:
-
"UNIT 1 HEADER A PRESSURE LOW".
-
"UNIT 2 HEADER A PRESSURE LOW".
-
"PUMP J-A DISCH PRESS LOW".
-
"PUMPQ-A DISCH PRESS LOW".
-
The following annunciator status on Miscellaneous
1-XA-55~15B panel on 1-M-15:
-
"ERCW DECK SUMP PUMP A RUNNING" is LIT.
-
ERCW headers 1A and 2A indicating LOW flow.
-
The crew implements AOP-M.01 , "Loss of Essential Raw Cooling Water".
Whic*h ONE of the following identifies the correct section of AOP-M.01 to be
implemented for the conditions and a mitigating action directed to be taken in
response to the conditions?
A. Section 2.7, "Supply Header 1AJ2A Failure in the Yard";
Start additional ERCW pumps to maintain pressure.
B. Section 2.7, "Supply Header 1AJ2A Failure in the Yard";
Stop and Lockout *out all A Train ERCW pumps.
C. Section 2.9, "Supply Header A Failure Upstream of Strainer Inlet Valves";
Start additional ERCW pumps to maintain pressure.
D. Section 2.9, "Supply Header A Failure Upstream of Strainer Inlet Valves";
Stop and Lockout out aU A Train ERCW pumps.
Page 90
1/2009 Sequoyah SRO NRC Exam
2/4/2009
91. Which ONE of the following correctly completes the statement below?
1-RM-90-255, "Condenser Vacuum Mid Range Radiation Monitor", is used in the
Radiological Emergency Plan (REP) to classify an event based on...
A. gaseous effluent release and is included in Tech Spec LCD 3.3.3.7,
"Accident Monitoring Instrumentation".
B. fission product barrier matrix and is included in Tech Spec LCD 3.3.3.7,
"Accident Monitoring Instrumentation".
C. gaseous effluent release and is NOT included in Tech Spec LCO 3.3.3.7,
"Accident Monitoring Instrumentation".
D. fission product barrier matrix and is NOT included in Tech Spec LeO 3.3.3.7,
"Accident Monitoring Instrumentation".
Page 91
1/2009 Sequoyah SRO NRC Exam
2/4/2009
92. Given the following:
-
A rele*ase of Waste Gas Tank B is in progress when power is lost to
0-RM-90-118, "Waste Gas Effluent Rad Monitor".
Which aNE of the following identifies (1) the effect the loss of power will have
on the release and (2) the requirement to allow any additional release of the
tank with the radiation monitor out of service?
A. (1) The release will automatically terminate;
(2) A new 0-SI-CEM-077-41 0.4, "Waste Gas Decay Tank Release", package
would be required for any additional release of the tank after aDCM
actions were met.
B. (1) The release will automatically terminate;
(2) The existing 0-SI-CEM-077-41 0.4, "Waste Gas Decay Tank Release",
package could be used for any additional release of the tank after aDeM
actions were met.
C. (1) A manual termination of the release will be required;
(2) A new 0-SI-CEM-077-41 0.4, "Waste Gas Decay Tank Release", package
would be required for any additional release of the tank after aDCM
actions were met.
D. (1) A manual termination of the release will be required;
(2) The existing 0-SI-CEM-077-41 0.4, "Waste Gas Decay Tank Release",
package could be* used for any additional release of the tank after aDCM
actions were met.
Page 92
1/2009 Sequoyah SRO NRC Exam
2/4/2009
93. Given the following:
Unit 1 operating at 100% power.
Unit 2 in MODE 6 with the core off-load in progress.
-
An internal electrical failure causes the output of O-RM-90-1 03, "Spent
Fuel Pit Area Radiation Monitor" to fail above the HI RAD setpoint.
Which ONE- of the following identifies the recovery required using 0-SO-30-10
"Auxiliary Building Ventilation Systems" as a result of the Auxiliary Building
Isolation (ASI) and whether the actuation is required to be reported to the
NRC in accordance with SPP-3.5, "NRC Reporting Requirements"?
A. Only Train B recovery is requ-ired;
8-hour notification required.
B. Only Train B recovery is required;
8-hour notification NOT required.
c. Only Train A recovery is required;
8-hour notification required.
D. Only Train A recovery is required;
8-hour notification NOT required~
Page 93
1/2009 Sequoyah SRO NRC Exam
2/4/2009
94. Given the following:
Unit 1at 100%
power with Boric Acid Tank (BAT) A aligned.
RWST Boric Acid concentration is 2575 ppm.
Which ONE of the following identifies BAT A Volume and Boric Acid Concentration that
will meet Operability requirements and when the maximum expected borationcapability
requirement occurs in accordance with the Technical Requirement Bases?
REFERENCE PROVIDED
A. 9600 gallons at-6500 ppm;
Near End of L-ife peak Xenon conditions.
B. 9600 gallons at 6500 ppm;
Near Beginning of Life peak Xenon conditions.
c. 9200 gallons at 6775 ppm;
Near End of Life peak Xenon conditions.
D. 9200 gallons at 6775 ppm;
Near Beg-inning of Life peak Xenon conditions.
Page 94
1/2009 Sequoyah SRO NRC Exam
2/4/2009
95. Given the following:
Unit 1 is at 100%power.
An air operated containment isolation valve has failed a stroke time
surveillance test.
-
All actions to comply with Tech Spec 3.6.3, "Containment Isolation Valves" have
been completed.
Which ONE of the following identifies if the penetration could be restored to
service to pe*rform troubleshooting activities or post maintenance testing?
The penetration could...
A. be restored to service to perform EITHER troubleshooting activities or post
maintenance testing.
B. ONLY be restored to service to perform troubleshooting activities.
C. ONLY be restored to service to perform post maintenance testing.
D. NOT be restored to service to perform EITHER troubleshooting activities or
post maintenance testing.
Page 95
1/2009 Sequoyah SRO NRC Exam
2/4/2009
96. Given the following:
Unit 1 is in MODE 5 during a refueling outage.
It is determined that procedure 1-S0-63-1, "Cold Leg Injection
Accumulators" needs an Urgent "Minor/Editorial Cha*nge" revision to
support system alignment changes due to system modification.
Which ONE ofthe following statements identifies the need for an Independent
Qualified Reviewer (lOR) and if the Unit SRO can be the approval authority for
the procedure revision?
A. An lOR is required.
The Unit SRO may sign as the approval authority.
B. An IQR is required.
The Unit SRO may NOT sign as the approval authority.
C. An lOR is NOT required.
The Unit SRO may sign as the approval authority.
D. An lOR is NOT required.
The Unit SRO may NOT sign as the approval authority.
Page 96
1/2009 Sequoyah SRO NRC Exam
2/4/2009
97. Given the following:
Unit 2 was shutdown for refueling on 01/20109 at 2400.
-
Today is 01/25/09 at 0200 and the Unit is in Mode 5.
Lower cavity fill has not been started.
-
2-78-610, "Transfer Tube Wafer Valve", is open for repair.
In accordance with O-GO-9, "Refueling Operations", which ONE of the following
identifies conditions both of which would be acceptable to minimize the potential
spread of airborne contamination?
A.
B.
c.
D.
Containment
Equipment Hatch...
open
open
held closed by a
minimum of 4 bolts.
held closed by a
minimum of 4 bolts.
Containment
Purge System...
in service and aligned
to upper containment
stopped.
in service and aligned
to upper containment.
stopped~
Page 97
1/2009 Sequoyah SRO NRC Exam
2/4/2009
98. Given the following conditions:
-
Both Units operating at 100% power.
-
0600
Due to extremely heavy rainfall, RSO/KEOC issues a Stage I flood
warning.
Which one of the following identifies the time the Stage 1 flood mode actions are
required to be completed, and if Stage II actions are required, how the Tritiated Drain
CoHectorTank would be prepared to prevent a possible release of radioactivity?
Time
Tritiated Drain Collector Tank
A.
1600
Pressurized to greater than 23 psig.
B.
1600
Filled with water.
c.
2300
Pressurized to greater than 23 psig..
D.
2300
Filled with water.
Page 98
1/2009 Sequoyah 'SRO NRC Exam
2/4/2009
99. Given the following:
Both units in service at 1000/0 power.
-
The p.lant is operating with minimum operations staffing.
-
A fire develops at the ERCW pumping station.
-
AOP-N.01, "Plant Fires", is implemented.
-
The Shift Manager declares an ALERT emergency and initiates
Assembly and Accountability.
Fire Ops actions to extinguish the fire continue.
Which ONE of the following identifies...
(1) the direction the AUOs are to be given
and
(2) if 10 minutes after the REP initiation, the Shift Manager determines
the need to implement AOP-N.08, "Appendix R Fire Safe Shutdown",
must both units enter the AOP or can the decision to enter the AOP
be made separately for each unit?
A. (1) Direct all AUOs to report to the Main Control Roo*m.
(2) Decision to enter AOP-N.08 can be made separately on e.ach unit.
B. (1) Direct aU AUOs to report to the Main Control Room.
(2) Decision to enter AOP-N.08must be made on both units at the same
time.
C. (1) Direct 2 AUOs to report to the OSC and the rest to report to the *Main
Control Room.
(2) Decision to enter AOP-N.08 can be made separately on each unit.
D. (1) Direct 2 AUOs to report to the GSC and the rest to report to the Main
Control Room.
(2) Decision to enter AOP-N.08 must be made on both units at the same
time.
Page 99
1/2009 Sequoyah SRO NRC Exam
2/4/2009
100. Given the following:
Both units trip from power operation due to a loss of offsite power.
Nuclear Security reports the following:
- Sabotage is suspected.
- An unexploded bo*mb has been discovered at the door of the Medical
Building.
- Concerns exist for the safety of oncoming emergency responders.
-
Nuclear Security recommends implementation of the Two-person line of
sight rule.
-
The Shift Manager declares an Alert.
Which ONE of the following describes...
(1) the selection the Shift Manager will make when activating the Emergency
Paging System (EPS)
and
(2) why EPIP-8, "Personnel Accountability and Evacuation" is required by the
emergency plan to be implemented?
A. (1) STAGING AREA will be selected on the EPS;
(2) Because an ALERT emergency has been declared.
B. (1) STAGING AREAwiHbe selected on the EPS;
(2) Because the Two-person line of sight rule has been implemented.
C. (1) EMERGENCY will be selected on the EPS;
(2) Because an *ALERT emergency has been declared.
D. (1) EMERGENCY will be selected on the EPS;
(2) Because the Two-person line of sight rule has been implemented.
Page 100
SRO Reference Package
1.
TI-28, Fig. A.14
2.
TRM Figure 3."1.2.6, Boric Acid Tank Limits Based on RWST Boron
Concentration
1/2009 Sequoyah SRO 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 AKl.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 AKl.06 9
B
10
054 AKl.02 10
B
11
055 EK2.0411
C
12
056 AAl.l1 12
B
13
057 AK3.01 13
A
14
058 AAl.0l 14
B
15
062 AK3.03 15
C
16
065 AK3.04 16
A
17
077 AAI.03 17
B
18
W/El1 EK2.1 18
C
19
001 AK3.02 19
C
20
005 AAI.OI 20
D
21
024 AA2.01 21
B
22
036 AK3.01 22
C
23
059 AKI.02 23
C
24
067 AG2.1.31 24
D
25
W/E08 EAI.I 25
c*
26
W/EIO EK 1.1 26
A
27
WEI4 EK2.1 27
C
28
003 Al.04 28
A
29
003 K4.02 29
D
30
004 A3.ll 30
D
31
005 K6.03 31
A
32
006 A3.06 32
C
33
007 Al.05 33
B
34
008 A3.04 34
B
35
008 KI.04 35
B
36
010 A.2.01 36
D
37
012 K2.01 37
A
38
013 G2.4.46 38
D
39
022 K4.03 39
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
Page 1
1/2009 Sequoyah SRO NRC Exam
2/4/2009
47
061 K5.03 47
A
48
062 Kl.02 48
B
49
063 G2.4.8 49
B
50
064 Al.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 AI.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
G 2.2.13 69
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 2.4.23 74
C
75
G 2.4.3975
A
76
008 AG2.4.2 76
A
77
009 EA2.37 77
D
78
011 EA2.14 78
D
79
015 AA2.01 79
B
80
022 AG2.1.28 80
C
81
077 AG2.4.5 81
C
82
068 AG2.4.7 82
C
83
076 AA2.02 83
B
84
W/EO 1 EG2.4.11 84
B
85
W/E16 EA2.1 85
D
86
003 A2.03 86
A
87
026 G2.4.20 87
D
88
039 Al.01 88
A
89
062 G2 4.18 89
C
90
076 A2.02 90
D
91
055 G2.4.3 91
C
92
071 A2.05 92
A
Page 2
1/2009 Sequoyah SRO NRC Exam
2/4/2009
93
072 A2~02 93
94
G 2.1.25 94
95-
G 2.2.21 95
96
G 2.2.6 96
97
G 2.3.13 97
98
G 2.3.14 98
99
G 2.4.27 99
100
G 2.4.28 100
Page 3
B
C
C
A
B
B
A
B