ML090480162
| ML090480162 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/02/2009 |
| From: | Operations Branch IV |
| To: | Entergy Operations |
| References | |
| AN-2009-01 | |
| Download: ML090480162 (31) | |
Text
ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
Date: Facility/Unit: ANO-1 Region: I II III IV Reactor Type: W CE BW GE Start Time: Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination 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 RO exam; 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 taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicants Signature Results RO/SRO-Only/Total Examination Values _ / 25 / 25 Points Applicants Scores / / Points Applicants Grade / / Percent
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 1 QID: 753 Given:
- Reactor tripped due to a Pressurizer Vapor Space leak.
- CET temperatures 590 degrees and rising.
- 'A' & 'B' OTSG levels 13".
- RCS pressure 1200 psig and stable.
- Both EDGs are in emergency standby.
For these conditions, which operating procedure should be used?
A. 1202.002, "Loss of Subcooling Margin" B. 1202.004, "Overheating" C. 1202.005, "Inadequate Core Cooling" D. 1203.015, "Pressurizer Systems Failure"
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 2 QID: 0733 Given:
Reactor tripped 4 minutes ago, All four RCP are running, T-hot 590 degrees and rising, RCS pressure 2000 psig, A&B OTSG pressures at 900 psig, A&B OTSG levels at 32 inches and lowering, The following Annunciators were received:
- K12-A5, "EFW Actuation Signal"
- K12-B5, "P-7A Turbine Trip"
- K02-B6, "A3 L.O. Relay Trip" Considering current plant conditions and alarms, which of the following procedures should be used to mitigate this event?
A. Loss of Subcooling Margin (1202.002)
B. Overheating (1202.004)
C. Inadequate Core Cooling (1202.005)
D. Reactor Trip (1202.001)
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 3 QID: 754 Given:
- P7A, Steam Driven EFW Pump OOS
- AACDG, Blackout Diesel Generator OOS A tornado has touched down in the switchyard causing a Degraded Power event.
- EDG #1 trips on low lube oil pressure.
- 4160v bus A3 lockout occurs and cannot be reset.
- RCS pressure has risen to 2450 psig and the ERV is open.
For these conditions, which operating procedure should be used?
A. 1202.008, Blackout.
B. 1202.012, Repetitive Task 4 (HPI Cooling).
C. 1202.004, Overheating.
D. 1202.012, Repetitive Task 3 (Full HPI).
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 4 QID: 755 Given:
- All 4160 volt busses de-energized.
- Steam line high range radiation monitors RI-2681 and RI-2682 in alarm and rising.
- Pressurizer level is 30 inches and dropping.
- RCS Pressure is 1700 psig and lowering.
For these conditions, which operating procedure should be used?
A. 1202.008, Blackout.
B. 1202.007, Degraded Power.
C. 1202.006, Tube Rupture.
D. 1202.012, Repetitive Task 2 (Initiate HPI).
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 5 QID: 756
- REFERENCE PROVIDED ***
Given:
-RCS Temperature 450 degrees
-RCS Pressure 1600 psig
- During a battery charger swap, D03A and D03B chargers are damaged causing a loss of red train DC power.
Assuming no Operator actions, which two of the following Technical Specifications are most limiting?
A. 3.8.4, DC Sources Operating, and 3.8.7 Inverters Operating.
B. 3.8.5 DC Sources Shutdown, and 3.8.7 Inverters Operating.
C. 3.8.5 DC Sources Shutdown, and 3.8.9 Distribution Systems Operating.
D. 3.8.4, DC Sources Operating and 3.8.9 Distribution Systems Operating.
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 6 QID: 757 Given:
Plant is in mode 4.
A Decay Heat Pump in service with 2800 gpm flow.
All RCPs are secured.
RCS pressure is 180 psig.
The following is observed:
RCS temperature is 220 degrees and rising.
Train A CET TEMP HI (K09-D6) in alarm.
DH PUMP A/B SUCT TEMP HI (K09-C8) in alarm.
For these conditions, which operating procedure and actions are required?
A. 1203.028, Loss of Decay Heat section 5, Loss of Service Water Flow; Close Service Water Inlet to E-35A, CV-3822 and immediately open supply breaker B-5182.
B. 1203.028, Loss of Decay Heat section 5, Loss of Service Water Flow; Stop A DH Pump and close at least one DH Suction Valve.
C. 1203.028, Loss of Decay Heat section 9, Loss of Both DH systems, RCS pressure boundary intact; Close Service Water Inlet to E-35A, CV-3822 and immediately open supply breaker B-5182.
D. 1203.028, Loss of Decay Heat section 9, Loss of Both DH systems, RCS pressure boundary intact; Stop A DH Pump and close at least one DH Suction Valve.
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 7 QID: 758 Given:
-Plant is in Startup at 9% power.
-NI-503, Intermediate Range A is OOS.
- The A Main Feedwater Pump is in service.
The following indications are observed:
-Main Feedwater Pump A Trip.
-NI-504 indicates 5x10-5 Ion Chamber Amps and stable.
-All Control Rod green lights lit.
For these conditions, which operating procedure actions should be used?
A. 1202.001, Reactor Trip, perform Emergency Boration per RT-12.
B. 1202.001, Reactor Trip, start the Auxiliary Feedwater Pump, P-75.
C. 1203.027, Loss of Steam Generator Feed, perform Emergency Boration per RT-12.
D. 1203.027, Loss of Steam Generator Feed, start the Auxiliary Feedwater Pump, P-75.
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 8 QID: 0398
- REFERENCE PROVIDED ***
A fire in the T-57A Emergency Diesel Fuel Oil Storage vault has been in progress but is now extinguished.
The intensity of the fire warped the room access door so badly that it will not close.
The fire also contaminated the smoke detection in the room so that the smoke detectors are inoperable.
What are the MINIMUM compensatory measures required for the Technical Requirements Manual?
A. Restore the inoperable door and detection to operable status within 14 days or initiate a condition report.
B. Within one hour establish an hourly fire watch since flame detection for this room is still operable.
C. Immediately test T-57B vault's fire detection and suppression equipment to prove operability.
D. Within one hour establish a continuous fire watch with standby suppression equipment.
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 9 QID: 760
- REFERENCE PROVIDED ***
Given:
The unit has been operating at 100% for 100 days.
A LOCA occurred four hours ago.
HPI flow is 975 gpm total.
Both Containment High Range Radiation Monitors are indicating 4000 R/hr.
Failed Fuel Iodine process monitor reads 9E5 cpm.
SPING 2, "Unit 1 Radwaste Area" monitor, High Radiation is in alarm on RDACs.
What Emergency Direction and Control checklist should you use?
A. 1903.011J, NUE B. 1903.011M, Alert C. 1903.011P, SAE D. 1903.011S, GE
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 10 QID: 0331 Following a controlled plant shutdown per 1202.006, Tube Rupture, the following conditions exist:
- RCS Thot is 460 °F
- RCS pressure is 900 psig
- Both OTSGs have ruptured tubes
- Both OTSGs have been isolated.
- BWST level drops below 23' What is the final Emergency Operating Procedure the CRS will be using?
A. 1202.002, Loss of Subcooling Margin B. 1202.010, ESAS C. 1202.011, HPI Cooldown D. 1202.006, Tube Rupture
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 11 QID: 759 Given:
- Plant is at 57% power with power escalation to 70% in progress
- RCPs P-32B, P-32C and P-32D are in service, P-32A was secured due to motor fault Subsequently, K02-A4, "H1 L.O. Relay Trip" alarms.
Which of the following procedural actions should be performed for these conditions?
A. Go to Reactor Trip, 1202.001.
B. Go to Reactor Coolant Pump and Motor Emergency, 1203.031.
C. Electrical System Operaton, 1107.001.
D. Verify main feedwater loop flow ratio responding to match RCS loop flow ratio per Reactor Coolant Pump Trip, 1203.022.
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 12 QID: 761 Given:
The plant is at 1600 psig and 450 degrees F.
Decay Heat Removal Pump (P34A) is tagged out for mechanical seal replacement.
Emergency Diesel Generator (K4B) fails its surveillance and is declared INOPERABLE.
Emergency Diesel Generator (K4B) was subsequently returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
What Technical Specifications would have been entered?
A. LCO 3.5.2 ECCS Operating, LCO 3.8.9 Distribution Systems Operating.
B. LCO 3.5.2 ECCS Operating, LCO 3.8.1 AC Sources Operating.
C. LCO 3.5.3 ECCS Shutdown, LCO 3.8.9 Distribution Systems Operating.
D. LCO 3.5.3 ECCS Shutdown, LCO 3.8.1 AC Sources Operating.
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 13 QID: 762 Given:
-Unit 1 is operating at 40% power.
-The Unit is in three pump ops due to the failure of P-32B.
-The Pressurizer Spray Control valve (CV-1008) fails open.
The ATC attempts to close the Pressurizer Spray Isolation valve (CV-1009) and it will NOT close
-Reactor Coolant Pressure is at 2100 psig and slowly lowering with all Pzr Heaters on.
What is the correct procedure and correct action for this condition?
A. 1202.001 Reactor Trip, and trip the Reactor.
B. 1202.001 Reactor Trip, and stop P-32C.
C. 1203.015 PZR System Failure, and trip the Reactor.
D. 1203.015 PZR System Failure, and stop P-32C.
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 14 QID: 763 Given:
- RCS pressure 2350 psig and stable.
- RCS temperature 589 °F and rising.
- ERV opened by CBOR
- "A" & "B" EFIC low range level = 15" and steady
- EFW is NOT available What is the correct procedure and correct action for this condition?
A. 1202.005, Inadequate Core Cooling; Start the third HPI pump.
B. 1202.004, Overheating; Reduce the SG pressure and feed with the Service Water Pump.
C. 1202.013, Repetitive Task 4, Initiate HPI Cooling; Start the ES Standby HPI pump.
D. 1202.013, Repetitive Task 16, Feeding an intact, dry SG; Feed with P-75 Aux. Feedwater Pump.
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 15 QID: 0649 Given:
- VCH-4A North Emergency Switchgear Room Chiller has failed
- No other cooling failures are present What are the impacts and which of the following references should be used as a result of these conditions?
A. Switchgear and Battery Chargers are inoperable, 1104.027, Battery and Switchgear Emergency Cooling System.
B. Switchgear and Battery Chargers are inoperable, Technical Specifications.
C. Switchgear and Battery Chargers are operable, 1104.027, Battery and Switchgear Emergency Cooling System.
D. Switchgear and Battery Chargers are operable, Technical Specifications.
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 16 QID: 764 Given
- Plant 100% power,
- Rod 5 in Group 6 has a faulty API, has been found to be 60 inches inserted Which of the following Technical Specification actions should be performed first due to the misaligned rod?
A. Restore CONTROL ROD alignment B. Reduce THERMAL POWER to < 60% of the ALLOWABLE THERMAL POWER C. Verify SDM to be within the limit provided in the COLR D. Perform SR 3.2.5.1 LHR within limits by using INCORE DETECTOR SYSTEM
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 17 QID: 0744 Given:
Plant power 100%
TE-1014 "A" Loop Narrow Range T-hot INSTANTLY fails low What procedure should be used for this condition?
A.1203.001, "ICS Abnormal Operation" B. 1203.012F, "SASS Mismatch" ACA C. 1202.001, "Reactor Trip" D. 1105.006, "Reactor Coolant System NNI"
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 18 QID: 765 Given:
- Unit is at 350 MWe in preps for start of P-1B MFW pump.
- Condensate Pumps P-2A and P-2C are in service
- Startup Xfmr #2 Feed to A1 (A-111) is inadvertently closed.
- P-1A MFW pump is in service.
What procedure and what actions are correct for this condition?
A. 1203.012E ACA for Condensate Pump Trip; Verify auto start of P-2B Condensate Pump on A2.
B. 1203.012E ACA for Condensate Pump Trip; Verify P-1A Main Feedwater Pump running.
C. 1203.027 Loss of Steam Generator Feed; Verify auto start of P-2B Condensate Pump on A2.
D. 1203.027 Loss of Steam Generator Feed; Verify P-1A Main Feedwater Pump running.
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 19 QID: 0250 Movement of a fuel assembly that does NOT follow the sequence in the approved fuel shuffle procedure requires prior approval of:
A. SRO in Charge of Fuel Handling and Shift Manager B. Shift Manager and Reactor Engineer C. Reactor Engineer and SRO in Charge of Fuel Handling D. SRO in Charge of Fuel Handling and Reactor Building Coordinator
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 20 QID: 767 Given:
During core alterations the Control Room notices VEF-15 Reactor Building Purge Exhaust Fan has tripped.
As SRO in charge of fuel handling your actions should be?
A. Continue core alterations and set building closure per attachment G of 1015.002, Decay Heat Removal and LTOP System Control.
B. Continue core alterations and isolate Reactor Building Purge System.
C. Suspend core alterations and set building closure per attachment G of 1015.002, Decay Heat Removal and LTOP System Control.
D. Suspend core alterations and isolate Reactor Building Purge System.
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 21 QID: 766 Which ONE (1) of the following describes Linear Heat Rate Hot Channel Factor (FQ(Z)), and which ONE (1) of the following is the most limiting accident for determining maximum FQ(Z) values?
A. Maximum / Average Fuel Rod Linear Heat Rate; Large Break LOCA B. Average Fuel Rod Linear Heat Rate; Large Break LOCA C. Maximum / Average Fuel Rod Linear Heat Rate; Loss of Forced Circulation D. Average Fuel Rod Linear Heat Rate; Loss of Forced Circulation
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 22 QID: 0122 A WCO is assigned to align "A" Decay Heat Removal during a shutdown.
It is estimated the job will take 40 minutes.
High RCS activity has created a TEDE dose rate of 4.5 R/hr in this area.
The WCO has an accumulated exposure of 0.525 Rem for the year.
The WCO makes the statement that he can complete the job without exceeding exposure limits.
Based on the above information would you allow the WCO to perform the alignment and why or why not?
A. Yes, I would allow the WCO to perform the alignment. The WCO will NOT receive a dose sufficient to exceed the Administrative Dose Control Level.
B. No, I would not allow the WCO to attempt to perform the alignment. The WCO will exceed the Administrative Dose Control Level within 20 minutes.
C. Yes, I would allow the WCO to perform the alignment. The WCO is allowed to exceed the Administrative Dose Control Level as long as the federal limit is not exceeded.
D. No, I would not allow the WCO to attempt to perform the alignment. The WCO will exceed the Administrative Dose Control Level within 15 minutes.
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 23 QID: 0123 Given:
- Plant shutdown and cooldown in progress
- RCS Tave 185°F
- RB Purge in progress to lower RB atmospheric activity
- RB Purge projected release duration is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- RB Purge release commenced two (2) hours ago
- Nuclear Chemistry stated gaseous releases projected to exceed quarterly objectives by 30%
- Release report preliminary release rate 4.1 E4 cfm
- Design flow rate 3.6 E4 cfm to 4.1 E4 cfm Which of the following would violate the RB Purge permit and require RB Purge termination?
A. Loss of Decay Heat Removal results in RCS temperature at 220°F.
B. RB Atmosphere Gaseous Detector slowly trending upward.
C. Maintenance personnel defeat the Personnel Hatch door interlocks.
D. Actual (stable) RB purge flow rate of 3.9 E4 cfm.
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 24 QID: 0126 Given:
- N-16 monitor R-2691 in alarm
- Small SG Tube Leak AOP in progress
- Letdown at 45 gpm
- Makeup at 66 gpm and rising The CBOR announces SCM is 30°F.
Which of the following EOPs would provide guidance to best mitigate this event?
A. Reactor Trip 1202.001 B. Loss of Subcooling Margin 1202.002 C. Tube Rupture 1202.006 D. ESAS 1202.010
ANO Unit 1 - 2009 SRO NRC Written Retake Examination Question No. 25 QID: 0130 For which EAL is a PAR required to be made?
ANO Unit 1 - 2009 SRO NRC Written Retake Examination ANO Unit 1 - 2009 SRO NRC Written Retake Exam KEY Question No. 1 QID: 753 Point Value: 1 Answer:
C. 1202.005, "Inadequate Core Cooling" Question No. 2 QID: 0733 Point Value: 1 Answer:
B. Overheating (1202.004)
Question No. 3 QID: 754 Point Value: 1 Answer:
B. 1202.012, Repetitive Task 4 (HPI Cooling).
Question No. 4 QID: 755 Point Value: 1 Answer:
A. 1202.008, Blackout.
Question No. 5 QID: 756 Point Value: 1 Answer:
D. 3.8.4, DC Sources Operating and 3.8.9 Distribution Systems Operating.
Question No. 6 QID: 757 Point Value: 1 Answer:
A. 1203.028, Loss of Decay Heat section 5, Loss of Service Water Flow; Close Service Water Inlet to E-35A, CV-3822 and immediately open supply breaker B-5182.
Question No. 7 QID: 758 Point Value: 1 Answer:
A. 1202.001, Reactor Trip, perform Emergency Boration per RT-12.
Question No. 8 QID: 0398 Point Value: 1 Answer:
D. Within one hour establish a continuous fire watch with standby suppression equipment.
ANO Unit 1 - 2009 SRO NRC Written Retake Exam KEY Question No. 9 QID: 760 Point Value: 1 Answer:
D. 1903.011S, GE Question No. 10 QID: 0331 Point Value: 1 Answer:
C. 1202.011, HPI Cooldown Question No. 11 QID: 759 Point Value: 1 Answer:
A. Go to Reactor Trip, 1202.001.
Question No. 12 QID: 761 Point Value: 1 Answer:
B. LCO 3.5.2 ECCS Operating, LCO 3.8.1 AC Sources Operating.
Question No. 13 QID: 762 Point Value: 1 Answer:
D. 1203.015 PZR System Failure, and stop P-32C.
Question No. 14 QID: 763 Point Value: 1 Answer:
D. 1202.013, Repetitive Task 16, Feeding an intact, dry SG; Feed with P-75 Aux. Feedwater Pump.
Question No. 15 QID: 0649 Point Value: 1 Answer:
C. 1104.027, Battery and Switchgear Emergency Cooling System.
Question No. 16 QID: 764 Point Value: 1 Answer:
C. Verify SDM to be within the limit provided in the COLR
ANO Unit 1 - 2009 SRO NRC Written Retake Exam KEY Question No. 17 QID: 0744 Point Value: 1 Answer:
B. 1203.012F, "SASS Mismatch" ACA Question No. 18 QID: 765 Point Value: 1 Answer:
B. 1203.012E ACA for Condensate Pump Trip; Verify P-1A Main Feedwater Pump running.
Question No. 19 QID: 0250 Point Value: 1 Answer:
C. Reactor Engineer and SRO in Charge of Fuel Handling Question No. 20 QID: 767 Point Value: 1 Answer:
D. Suspend core alterations and isolate Reactor Building Purge System.
Question No. 21 QID: 766 Point Value: 1 Answer:
A. Maximum / Average Fuel Rod Linear Heat Rate; Large Break LOCA Question No. 22 QID: 0122 Point Value: 1 Answer:
B. No, I would not allow the WCO to attempt to perform the alignment. The WCO will exceed the Administrative Dose Control Level within 20 minutes.
Question No. 23 QID: 0123 Point Value: 1 Answer:
A. Loss of Decay Heat Removal results in RCS temperature at 220°F.
Question No. 24 QID: 0126 Point Value: 1 Answer:
C. Tube Rupture 1202.006
ANO Unit 1 - 2009 SRO NRC Written Retake Exam KEY Question No. 25 QID: 0130 Point Value: 1 Answer:
D. GE