ML032580312
| ML032580312 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/29/2003 |
| From: | NRC/RGN-II |
| To: | Progress Energy Florida |
| References | |
| 50-302/03-301 50-302/03-301 | |
| Download: ML032580312 (27) | |
See also: IR 05000302/2003301
Text
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~~~ ~~ Final Submittal
~~
CRYSTAL RIVER AUGUST
EXAM 50-382/2003 -301
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AUGUST 25 29,2003
1. Senior Operator Written Examinatlon
Name: Region: II
Date: 08/22/03 FacilityIUnit: Crystal River
License Level: SRO Reactor Type: B&W
Start Time: Finish Time:
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Applicant Certification
All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature
Results
RO I SRO-Only I Total Examination Values I I Points
Applicant's Scores I I Points
Applicant's Grade: I I Percent
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Crystal River 2003-301
SRO lnital Exam
08/22/03
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1. The following initial plant conditions exist at 100 EFPD:
NI-5 100% Imbalance at 0
NI-6 100% Rod Index of 292%
NI-7 100%
NI-8 100%
Fifteen minutes later the following conditions are observed
NI-5 54% Imbalance at -10
NE6 50% Rod Index of 250%
NI-7 50%
NI-8 50%
Which of the following is the most likely condition to cause these indications?
A. Stuck rod.
x- B. Dropped rod.
C. Boration event in progress.
D. Loss of one reactor coolant pump.
Crystal River 2003-301
SRO lnital Exam
08/22/03
2. A crud burst has occurre ~ w COI impact the plant and what actions can -2 taken to
help mitigate this problem?
A. The makeup pre-filters and post-filters will absorb most of the contaminants and
their radiation levels will increase. A hydrogen peroxide flush per OP-403H,
Hydrogen Peroxide Addition, will help reduce radiation levels.
B. The makeup pre-filters and post-filters will absorb most of the contaminants and
their radiation levels will increase. Decreasing letdown flow will help lower
radiation levels in the purification loop.
C. The makeup demins and post-filters will absorb most of the contaminants and their
radiation levels will increase. A hydrogen peroxide flush per OP-403H, Hydrogen
Peroxide Addition, will help reduce radiation levels.
D. The makeup demins and post-filters will absorb most of the contaminants and their
radiation levels will increase. Decreasing letdown flow will help lower radiation
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levels in the purification loop.
Crystal River 2003-301
SRO lnital Exam
08/22/03
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3. While operating at power RM-A6 is observed t o be trending up. MUV-31is taken
t o manual and the following data is gathered for evaluation.
Time 0900 Pzr Lvl - 220" MUT Lvl - 80"
Time 0902 Pzr Lvl - 216" MUT Lvl - 81"
The following data is provided:
Pressurizer level = 12.2 gayinch MUT level = 30.8 gayinch
Based on these indications, which of the following describes current RCS leakage
and procedural/TS requirements? (disregard controlled bleedoff flow)
Conditions indicate RCS leakage:
A. is less than 1gpm; CP-152, Primary to Secondary Leakage Operating
-2 Guideline, will apply.
B. is less than 1gpm; SP-317, RCS Water Inventory Balance, will apply.
C. is greater than 5 gpm but less than 10 gpm; TS entry is required
because unidentified leakage is greater than 1gpm.
D. is greater than 5 gpm but less than 10 gpm; TS entry is not required
because identified leakage is less than 10 gpm.
Crystal River 2003-301
SRO lnital Exam
08/22/03
4. While the unit is operating a t 100% the following sequence of events occurs:
- "SASS MISMATCH annunciator alarms and does not clear.
- Investigation reveals the amber "MISMATCH" lamp t o be lit on the
PRESSURIZER LEVEL channel. All other lamps in that channel and all other
"MISMATCH' lamps are off.
- Control board readings for PZR level are as follows:
LT1 222"
LT2 160"
LT3 227"
- All readings are stable.
Which of the following statements is correct concerning these conditions?
A. The alarm is valid. SASS has functioned properly. No operator action is
required.
B. The alarm is valid, however, SASS should have transferred to LTl. The
operator should select LT1 and issue a work request on LT3.
C. The alarm is NOT valid. The operator should depress the "AUTO"
pushbutton to return the channel t o normal operation.
D. The alarm is NOT valid. The operator should issue a wprk request on
the SASS channel.
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Crystal River 2003-301
SRO lnital Exam
08/22/03
5. At 80% power maintenance testing determines that two channels of the control oil
pressure for loss of MFW Pumps actuation are set at 52 psig. Which of the
following Technical Specification actions are required?
Place:
A. both channels in bypass in one hour.
B. one channel in bypass in one hour and place the second channel in trip
in one hour.
C. one channel in bypass in one hour and restore one channel t o operable
status in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. one channel in trip in one hour and restore one channel to operable
status in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Crystal River 2003-301
SRO lnital Exam
08/22/03
6. The following plant conditions exist:
- TS required plant shutdown to Mode 4 is in progress due to a broken shaft on
DHP-1A.
- RCS temperature is 285°F.
- RCP-1A and 1B are running.
While checking DHP-1B for start the PPO reports an oil spill around the motor and the oil
bubbler empty.
Which of the following describes the appropriate action(s) to be taken?
A. Remain in this mode until either DHP-1A or 1B are repaired.
B. Remain in this mode and declare an Unusual Event based on the "Inability to reach
required mode within ITS time limits".
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C. Continue to Mode 4, invoke lOCFR 50.54 X & Y, and remain in Mode 4 until
either DHP-1A or 1B are repaired.
D. Continue to Mode 5 since LCO 3.0.3 now applies due to the inoperability of both
DH removal trains.
Crystal River 2003-301
SRO lnital Exam
08/22/03
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7. The following plant conditions exist:
- SW surge tank, SWT-1, is at 9 ft and lowering.
- "A" DC surge tank, DCT-lA, is at 9 ft and steady.
- "B" DC surge tank, DCT-IB, is at 9 ft and steady.
- Auxuliary Building sump is steady.
- Turbine Building sump is rising.
Which of the following could be the cause o f the Iowering level in SWT-l?
A. A tube leak in the "B" letdown cooler, MUHE-1B.
B. A crack in the SW supply piping near the CRDM filters.
C. A crack in the suction header near the normal duty SW pump, SWP-1C.
D. Improper valve alignment for cooling water t o the "C" Makeup pump,
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MUP- 1C.
L...'
Crystal River 2003-301
SRO lnital Exam
08/22/03
8. The following plant conditions exist:
- The plant is at 55% reactor power.
- The ICs +24 volt DC bus has degraded to +I8 volts.
- RPS high reactor coolant system pressure setpoint has been exceeded.
Assuming no operator actions what would be the plant's response to this situation?
A. ATWS removes power from the safety rods and initiates EFIC.
B. AMSAC trips the main turbine and initiates EFlC.
C. DSS opens the "E" and "F'contacts to the safety rods.
D. RPS trips the reactor due to the trip of both MFW pumps.
Crystal River 2003-301
SRO lnital Exam
08/22/03
9. The plant is operating at 100% power. Fuel shuffle is in progress in the Spent Fuel Pool.
Water level in the spent fuel pool is normal at 158.5 ft. The suction line to SFP-IA ruptures
and cannot be isolated. Movement of spent fuel in the spent fuel pool:
A. Must stop due to insufficient volume for cooling to maintain pool temperature less
than 190' F.
B. May continue because adequate level will still be maintained for shielding
requirements.
C. Must stop due to insufficient volume for iodine retention if a fuel handling accident
were to occur.
D. May continue because level will not drop below the minimum Technical
Specification value.
Crystal River 2003-301
SRO lnital Exam
oa122103
10. A step in EOP-5, Excessive Heat Transfer, states:
IF at any time, ES systems have,
OR should have actuated,
THEN ensure ES equipment is properly aligned.
Details 1. Ensure applicable ES actuations:
RBIC (4psig RB PRESS)
2. Bypass or reset ES actuations:
Auto
Manual
3. Control ES systems as required.
[Rule 2, HPI Control]
[Rule 5, EDG Control]
4. IF RBIC has actuated, AND adequate SCM exists,
THEN stop all RCPs: RCP-lA, lB, 1 C & 1D
What is the purpose of Detail #4?
Because it is not reasonable t o expect the operating crews to be able t o adequately
evaluate the safety implications of: bypassing the ES actuation and
A. restoring seal injection within 5 minutes.
B. reopening the CBO valves within 5 minutes.
C. reopening the SW cooling valves within 5 minutes.
D. the effect on OTSG tube stresses in the isolated OTSG within 5 minutes.
Crystal River 2003-301
SRO lnital Exam
08/22/03
11. A step in EOP-12, Station Blackout, states the following:
"Stop DC motors."
Partial details of this step have the Reactor Operator:
- Select MUP backup lube oil pumps (MUP-3A, B, C) to "Pull To Lock."
- Select MUP backup gear oil pumps (MUPdA, B, C) t o "Stop."
Which of the following describes why the DC motors should be stopped?
This is necessary for the 1E batteries t o meet their:
A. 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> coping requirement.
B. 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> coping requirement.
L-, C. 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> coping requirement.
D. 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> coping requirement.
Crystal River 2003-301
SRO lnital Exam
08/22/03
12. With the plant at 100% power a catastrophic failure of VBlT-IC rendered itself inoperable and
caused both of the VBXSs that it feeds to fail "as is" .
Which of the following describes the EOP/AP action(s), if any, that should be taken?
A. AP-58 1, Loss of "I-X, should be entered.
B. AP-582, Loss of "1-Y, should be entered.
C. AP-430, Loss of Control Room Alarms, should be entered.
D. Trip both MFW pumps and the reactor due to the loss of ICs power. EOP-2, Vital
System Status Verification, and Rule 3, EFW Control, should be entered.
Crystal River 2003-301
SRO lnital Exam
08/22/03
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13.
With the plant at 35% power AUIU MAN AurO MAN
you notice the "EFW MAN" light
flashing on the Emergency
Feedwater Initiation and
Control (EFIC) module
shown. A few seconds later the "FULL' light
starts to flash. Select the statement
below which describes these indications
and required action(s), if any, which
should be taken.
A. These indications are expected during low power operation. No additional actions
are required.
B. These lights are memory lights only. They will normally stay flashing until the test
pushbutton in the lower right comer of this module is depressed. Maintenance
should be contacted
C. An EFIC actuation has occurred due to the loss of both MFWPs. Since the "EFW
MAN" light was on prior to the actuation it should continue to flash. EOP-2, Vital
System Status Verification, and EOP-13, Rule 3, EFWIAFW Control, should be
entered.
D. An EFIC actuation has occurred due to the loss of all RCPs. The "EFW MAN"
light should have stopped flashing and the "EFW AUTO" should have started
flashing. EOP-2, Vital System Status Verification, and EOP-13, Rule 3,
EFW/AFW Control, should be entered.
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Crystal River 2003-301
SRO lnital Exam
08/22/03
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14.Which of the following describes a condition that requires notification of all plant
personnel?
A. RM-A2 particulate monitor goes into high alarm.
B. RM-A2 iodine monitor goes into high alarm.
C. RM-A5 particulate monitor goes into high alarm.
D. RM-A5 iodine monitor goes into high alarm.
Crystal River 2003-301
SRO lnital Exam
08/22/03
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15. Assume the "B" EDG is the sole power supply available t o the "B" ES 4160V bus.
Which of the following activities would produce the lowest diesel load that would
cause the EDGs elapsed time meter (MCB) to start? (disregard starting currents)
AHF-17AIB 51 kW DCP-lA/B 79 kW
AHF-18AIB 50 kW EFP-1 698 kW
AHF-19AIB 18 kW MUP-lA/B/C 694 kW
BSP-1AIB 222 kW RwP-2AIB 554 kW
CHP-1AIB 19 kW RWP-3AIB 198 kW
CHHE-1AIB 196 kW SWP-1AIB 497 kW
A. Initial EDG loading of 2440 kW. MUP-1C and its associated cooling
water pumps are started.
R. Initial EDG loading of 2850 kW. BSP-1B and its associated cooling
water pumps are started.
b C. Initial EDG loading of 1800 kW. EFP-1 and its associated cooling water
pumps are started.
D. Initial EDG loading of 2920 kW. "B" train normal control complex
cooling fans and chiller are started.
Crystal River 2003-301
SRO lnital Exam
08/22/03
16. The following plant conditions exist:
- EOP-3, Inadequate Subcooling Margin, was entered following a LOCA.
- Reactor Coolant (RCS) pressure was 850 psig.
- EFP-2 is the only operating and the only available EFWIAFW pump.
Tincore temperature is currently 900" F and RCS pressure is 1000 psig. Which of
the following methods would be used t o maintain the OTSGs as a heat sink?
A. Lower OTSG pressure t o 200 psig using the Turbine Bypass valves
(TBVs).
B. Lower OTSG pressure t o 380 psig using the Turbine Bypass valves
(TBVs).
C. Lower OTSG pressure t o 200 psig using the Atmospheric Dump valves
(ADVS).
.L-'
D. Lower OTSG pressure t o 380 psig using the Atmospheric Dump valves
(ADVs).
Crystal River 2003-301
SRO lnital Exam
08/22/03
17. The plant has experienced a loss of NNI-X power which causes a spurious closure of MUV-49,
letdown isolation valve. Pressurizer level is increasing due to the loss of letdown. Which of
the following actions, by procedure, should be directed to decrease seal injection flow in order
to slow down the increase in PZR level?
Direct the:
A. PPO to manually reduce flow by throttling MUV-16, seal injection control valve.
B. RO to reduce MUV-16 valve demand using the setpoint knob with the hand/auto
station in auto.
C. RO to reduce MUV-16 valve demand using the toggle switch with the hand/auto
station in manual.
D. PPO to isolate MUV-16 and use the manual bypass valve to allow continued seal
injection.
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Crystal River 2003-301
SRO lnital Exam
08/22/03
18. After performance of a surveillance procedure on the "A" EDG the diesel is determined to be
Which of the following actions should be taken to ensure troubleshooting activities will not
render the redundant train inoperable?
A. Electronically lock the doors to the "B" EDG so that only personnel approved by
the Superintendant of Shift Operations will have access.
B. Electronically lock the doors to the "B" ES 4160V switchgear room so that only
personnel approved by the Superintendant of Shift Operations will have access.
C. Perform an EOOS evaluation, change the "Plant Condition" color to red and have
flyers produced.
D. Post protected train signs and conduct a field walkdown of the appropriate opposite
train equipment.
Crystal River 2003-301
SRO lnital Exam
08/22/03
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19. The following plant conditions exist:
- The plant is in a refueling outage and the reactor is defueled.
- One of the two available PPOs assigned to the Auxiliary Building slips and
severely sprains his ankle while performing a walkdown of the Reactor
Building.
- The PPO is contaminated and is escorted to the hospital by both available
Health Physics technicians.
Which of the following describes the required minimum staffing for this situation?
A. No action is required. Minimum staffing levels are still met
B. If it is two hours or less until shift turnover is scheduled to occur no
action is required.
C. Another PPO should be called in immediately and should arrive within
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two hours.
D. Another HP technician should be called in immediately and should
arrive within two hours.
Crystal River 2003-301
SRO lnital Exam
08/22/03
20. The following plant conditions exist:
- Plant is at 100% power.
- RWPSA tagged out for shaft alignment 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago.
- TS 3.7.9 was entered when RWP-2A was tagged out.
- The PPO has just reported the trip mechanism for the "B" EDG is broken.
Which of the following actions should be performed when "B" EDG is declared
A. Perform SR 3.8.1.1 within 1hour, declare "A" EDG inoperable within 4
hours.
B. Immediately declare both RWP-2A and 2B inoperable, enter LCO 3.0.3,
be in Mode 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, Mode 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> and Mode 5 within
37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
W C. Perform SR 3.8.1.1 within 1hour, declare RWPSB inoperable within 4
hours, and determine the " A EDG is not inoperable due t o a common
cause failure within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
D. Perform SR 3.8.1.1 within 1hour, declare all "B" train ES components
inoperable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and determine the "A"EDG is not inoperable
due t o a common cause failure within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
Crystal River 2003-301
SRO lnital Exam
08/22/03
21. During three RCP operation (RCP-1D secured) the following readings are recorded:
- RCS total flow 1.14 x lo8 l b d h r
- RCSThot "A"loop 603" F "B" Loop 603" F
- RCS pressure "A"loop 2070 psig "B" Loop 2090 psig
Based on the above conditions what action(s), if any, are required to be taken?
A. No action required. All parameters are within limits for three RCP operation.
B. The DNBR Safety Limit has been exceeded. Be in Mode 3 within one hour.
C. One DNB parameter is not within limits. Restore the parameter to within limits in
two hours.
D. Two DNB parameters are not within limits. Restore the parameters to within limits
in two hours.
Crystal River 2003-301
SRO lnital Exam
08/22/03
22. Refueling is in progress with eight (8) fuel assemblies in the core. As the ninth
assembly is being placed in the core the following NI readings are observed:
- NI-1 increases from a base count of 203 t o 430 cps.
- NI-14 increases from a base count of 9.3 x t o 2.3 x
- NI-2 and NI-15 are out-of-service.
Which of the following actions, if any, should be taken by the refueling supervisor?
A. No action is required. This is an expected NI response.
B. Once the assembly is placed in the core, reactor engineering should be
contacted t o perform a subcritical multiplication calculation.
C. Cease insertion of the fuel assembly and submit a sample request for
boron concentration of the reactor coolant system.
-. D. Withdraw the fuel assembly, stop any other core alterations in progress,
perform Co/Ci calculations, and obtain a boron analysis.
Crystal River 2003-301
SRO lnital Exam
08/22/03
23. The following plant conditions exist:
- Plant is in Mode 5.
- The "A' DHR train is in service.
- SDT-I, Secondary Drain Tank, recirc is complete and ready for release.
- RWP-I is running.
- RWV-150 is closed.
- CWP-IA and 1D are running.
- RM-L2/7 "Bypass" switch is selected to "Bypass".
- Minimum RW dilution flow rate is 11,800 gpm per the release permit.
Which of the following action(s), if any, must be taken before the release can be started?
A. Adequate dilution flow exists. No further actions required.
E. Adequate dilution flow exists as long as a minimum of two (2) CWPs remain in
operation.
C. Inadequate dilution flow exists. RWP-2A or 2B must be started prior to release.
D. Inadequate dilution flow exists. RWP-3A or 3B must be started prior to release.
Crystal River 2003-301
SRO lnital Exam
08/22/03
24. The plant has experienced a Rx trip and now no source of main, emergency or
auxiliary feedwater is available. The crew has entered EOP-04, Inadequate Heat
Transfer. Step 3.12 of EOP-04 states:
WHEN any of the following exist:
RCS pressure approaches the NDT limit
PORV opens automatically
RCS press > 2400 psig
THEN continue in this procedure.
w h y are we required t o wait t o initiate HPI / PORV cooling when the RCS is in a n
Inadequate Heat Transfer condition?
A. To allow the crew t o wait for the appropriate amount of time t o
determine if Natural Circulation will develop.
i
B. To prevent the plant from entering into a Pressurized Thermal Shock
condition.
C. To ensure the highest RCS level is being maintained once RCS
inventory starts being lost.
D. To allow for the natural decrease in the post trip decay heat level.
Crystal River 2003-301
SRO lnital Exam
08/22/03
25. The following plant conditions exist:
- Rx tripped on low RCS pressure from 100% power.
- OTSG tube rupture on the 'A' OTSG (estimated at 250 gpm).
- HPI actuation on low RCS pressure.
- Main Steam Safety Valve on 'A' OTSG will not close.
Use only the above information t o classify the event. (Do NOT use EC judgement)
A. Unusual Event
B. Alert
C. Site Area Emergency
D. General Emergency