ML13161A063
| ML13161A063 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/10/2013 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| ES-401-7 50-327/13-301, 50-328/13-301 | |
| Download: ML13161A063 (79) | |
Text
ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:
Date:
Facility/Unit: Sequoyah Station Units I & 2 Region:
ii x iii iv Reactor Type: W X CE BW LI GE LI 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. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.
Applicant Certification All work done on this examination is my own.
I have neither given nor received aid.
Applicants Signature Results Examination Value Points Applicants Score Points Applicants Grade Percent
Name:
1305 NRC RO Exam Form: 0 Version: 0
- 1. Given the following plant conditions:
Unit 1 is operating at 100% at EOL (15,000 MWD/MTU)
Subsequently a reactor trip occurs on Unit 1.
Shutdown Bank B rod G3 remains at 228 steps.
Control Bank D rod M8 sticks at 10 steps while inserting.
Tavg dropped to 539°F and stable.
Which ONE of the following completes the statement below?
Based on the given conditions, in accordance with ES-0.1, Reactor Trip Response, Emergency Boration is A. NOT required B.
required due to the RCS temperature only C.
required due to the stuck control rods only D.
required due to both the RCS temperature and the stuck control rods Wednesday, May22, 2013 12:04:43 PM
1305 NRC RO Exam
- 2. Given the following plant conditions:
A safety injection has occurred.
RCS pressure is 1720 psig and still dropping.
Pressurizer level is rising.
All reactor coolant pumps are in operation.
Which ONE of the following identifies the leak location?
A. Pressurizer safety valve B. Reactor Vessel Head vent line C. Incore Instrument Guide Tube D. Pressurizer heater well Wednesday, May 22, 2013 11:16:30AM 2
1305 NRC RO Exam
- 3. Given the following plant conditions:
The crew is performing ES-i.2, Post LOCA Cooldown and Depressurization.
Core Exit Temperature is 546°F and lowering.
RCS Thot is 531°F and lowering.
RCS wide range pressure is 1520 psig.
RCPs have been removed from service.
Which ONE of the following identifies the current RCS subcooling margin and the operational impact if subcooling is reduced to 0°F during the depressurization?
A. 53°F; The RCS cooldown will stop until minimum required subcooling is restored.
B. 68°F; The RCS cooldown will stop until minimum required subcooling is restored.
C. 53°F; Pressurizer level will rapidly rise.
D. 68°F; Pressurizer level will rapidly rise.
Wednesday, May 22, 2013 11:16:30 AM 3
1305 NRC RO Exam
- 4. Given the following plant conditions:
Unit I is initially at 100% power when an event occurred.
The crew has just restored power to FCV-63-1 at step 6 of ES-i.3, Transfer to RHR Containment Sump.
RWST level is 20% and lowering.
CNTMT pressure is 1.5 psig and lowering.
CNTMT sump level is 41% and rising.
1-HS-63-72A, CNTMT Sump Suct To RHR Pump 1A, Red light LIT i-HS-63-73A, CNTMT Sump Suct To RHR Pump IB, Red light LIT 1-HS-72-39A, CNTMT Spray Hdr 1A Isol, Green light LIT i-HS-72-2A, CNTMT Spray Hdr lB Isol, Green light LIT Which ONE of the following completes the statement below?
Based on the above indications the RHR CNTMT Sump suction valves (1) in the expected positions and the CNTMT Spray Header isolations (2) in the expected positions.
A. (1)are (2) are B. (i)are (2) are NOT C. (1)are NOT (2) are D. (i)are NOT (2) are NOT Wednesday, May 22, 2013 11:16:31 AM 4
1305 NRC RO Exam
- 5. Given the following plant conditions:
Unit 2 is operating at 100% power.
FS-62-1 1 REAC COOL PMPS SEAL LEAKOFF HIGH FLOW alarm is LIT.
LS-62-45A REAC COOL PMP 4 STANDPIPE LVL HIGH-LOW alarm is LIT No. 1 seal leakoff flow recorder for RCP #4 indicates 7 gpm.
Which ONE of the following completes the statements below:
(1)
The #2 seal on RCP #4 becomes a (1) in response to these conditions.
(2)
In accordance with AOP-R.04, Reactor Coolant Pump Malfunctions, the minimum No. 1 Seal Leakoff flow that would require an immediate reactor trip and shutdown of #4 RCP is when flow exceeds (2)
?
A. (1) film riding seal (2) 8 gpm B. (1) film riding seal (2) 9 gpm C. (1) rubbingfaceseal (2) 8 gpm D. (1) rubbing face seal (2) 9 gpm Wednesday, May22, 2013 11:16:31 AM 5
1305 NRC RD Exam
- 6. Given the following plant conditions:
While operating at 100% power, the Unit 1 operators entered AOP-M.09, Loss of Charging, and secured the IA CCP pump due to indications of gas binding.
After stopping the CCP, a Turbine Runback occurs due to the trip of 1 B MFPT.
The operators stabilized the Unit at 60% power with the following conditions:
Pressurizer level at 37%.
Annunciator B-7, ZB-412B ROD CONTROL BANKS LIMIT LOW-LOW, in ALARM on I-XA-55-4B.
Tavg is 568°F.
RCP lower bearing temperatures 150°F.
RCP seal water temperature 160°F.
No CCP5 are running.
Based on the current plant conditions, which ONE of the following identifies the reason that the Unit is required to be immediately tripped?
A. RCS boration is required to comply with Tech Spec action B. Pressurizer level deviation from program C. Loss of RCP seal injection flow D. Tavg -Tref difference Wednesday, May 22, 2013 11:16:31 AM 6
1305 NRC RO Exam
- 7. Given the following plant conditions:
Unit I was operating at 100% power when a LOCA occurred.
The crew is implementing ES-i.3, Transfer to RHR Containment Sump.
Both trains of ECCS and Containment Spray pump suctions have been transferred to the containment sump.
The lB RHR pump begins to cavitate.
Containment pressure is 4.1 psig and slowly trending down.
In accordance with ES-I.3, which ONE of the following completes the statements below?
The conditions above require the operating crew to ensure (1) are stopped and placed to Pull to Lock.
After stopping required pumps in (1) above, if the remaining Containment Spray pump amps start fluctuating, (2) is/are required to be stopped.
A. (1) only the 1 B RHR pump and one Containment Spray pump (2) all running ECCS and Containment Spray pumps B. (1) only the 1 B RHR pump and one Containment Spray pump (2) only the running Containment Spray pump C. (1) 1 B RHR, one CCP, one SI pump and one Containment Spray pump (2) all running ECCS and Containment Spray pumps D. (1) 1 B RHR, one CCP, one SI pump and one Containment Spray pump (2) only the running Containment Spray pump Wednesday, May22, 201311:16:31 AM 7
1305 NRC RO Exam
- 8. Given the following plant conditions:
Unit 1 is in Mode 3 with RCS cooldown in progress.
Unit 2 is operating at 100% power.
Spent Fuel Pool Cooling is being supplied from Unit I Train A CCS.
A leak upstream of the IA CCS heat exchangers required all Unit I Train A CCS to be shutdown.
Which ONE of the following completes the statement below?
In accordance with AOP-M.03,Loss of Component Cooling Water, the cooling supply to the Spent Fuel Pool Cooling System is jt required to be realigned to be supplied from (1)
After CCS is restored to the in-service Spent Fuel Pool Heat Exchanger, if the CCS flow rate is 3400 gpm through the heat exchanger, the flow rate (2) required to be adjusted in accordance with 0-SO-78-1, Spent Fuel Pit Coolant System.
Li)
A.
Unit I CCS Train B is B.
Unit I CCS Train B is NOT C.
Unit2CCSTrainA is D.
Unit 2 CCS Train A is NOT Wednesday, May 22, 2013 11:16:31 AM 8
1305 NRC RD Exam
- 9. Given the following:
Unit 2 is operating at 100% power when a turbine trip occurs.
Control rods begin inserting with 2-HS-85-5110, ROD CONTROL MODE SELECTOR, in AUTO.
Control Rods are inserting at maximum rate.
The reactor fails to trip and cannot be tripped from the MCR reactor trip handswitches.
The crew enters the EOP network and has transitioned to FR-S.1, Nuclear Power Generation I ATWS.
Which ONE of the following completes the statement below in accordance with FR-S.1?
FR-S.1 A. allows ROD CONTROL to remain in AUTO until the rod insertion rate first drops to less than 64 steps/mm before requiring manual rod insertion B. allows ROD CONTROL to remain in AUTO until the rod insertion rate first drops to less than 48 steps/mm before requiring manual rod insertion C. requires ROD CONTROL to be immediately placed in MAN and insertion continued resulting in the ROD SPEED indicating 64 steps/mm D. requires ROD CONTROL to be immediately placed in MAN and insertion continued resulting in the ROD SPEED indicating 48 steps/mm Wednesday, May 22, 2013 11:16:31 AM 9
1305 NRC RO Exam
- 10. Given the following plant conditions:
Unit 1 is operating at 67% power steady state conditions with Rod Control in Manual.
A steam leak in the west valve vault room results in the following:
Rx Power Turb Power Tavg RCS Press MWe 0700 67%
67.0%
567°F 2235 psig 785 MWe 0701 68%
66.5%
566°F 2231 psig 761 MWe 0702 69%
66.5%
564°F 2227 psig 761 MWe 0703 70%
65.5%
563°F 2223 psig 755 MWe 0704 71%
65.0%
561°F 2219 psig 750 MWe Which ONE of the following completes the statement below?
The earliest time the conditions require an immediate reactor trip to be initiated in accordance with AOP-S.05, Steam or Feedwater Leak, is A.
0701 B.
0702 C.
0703 D.
0704 Wednesday, May 22, 2013 11:16:31 AM 10
1305 NRC RO Exam
- 11. Given the following plant conditions:
Unit 2 is at 100% RTP.
SIG #4 main feedwater line develops a leak inside containment at the containment penetration wall.
The S/G #4 level is able to be maintained with increased feedwater flow.
Containment pressure is 1.4 psig and rising.
Condenser hotwell level is 20 and lowering.
The operating crew enters AOP-S.05, Steam or Feedwater Leak.
While performing AOP-S.05, the AOP directs the operating crew to trip the reactor, initiate SI and close the MSIVs.
Based on the given conditions, which ONE of the following completes the statements below?
The AOP-S.05 criteria used to trip the reactor, initiate SI and close the MSIVsisdueto (1)
After these actions have been taken, SG #4 pressure (2) lower uncontrolled.
A. (1) hotwell level (2) will B. (1) hotwell level (2) will NOT C. (1) containment pressure (2) will D. (1) containment pressure (2) will NOT Wednesday, May22, 2013 11:16:31 AM 11
1305 NRC RO Exam
- 12. Given the following plant conditions:
Unit I was operating at 100% rated thermal power when a reactor trip occurs The following annunicators are observed in alarm:
0-M26-A, A-5, Diesel GEN lA-A Running > 40 RPM.
0-M26-B, A-5, Diesel GEN 1 B-B Running > 40 RPM.
0-M26-C, A-5, Diesel GEN 2A-A Running > 40 RPM.
0-M26-D, A-5, Diesel GEN 2B-B Running > 40 RPM.
i-Mi-B, B-2, 6900V Unit BD lB Failure Or Undervoltage.
0-M26-A, C-7,6900V SD BD lA-A Failure or Bus Feeder UV alarms and clears.
Which ONE of the following completes the statement below?
The crew is required to perform (1) in parallel with applicable EOPs, and the Emergency Diesel status is (2) based on the above conditions.
A. (1) AOP-P.01, Loss of Offsite Power (2) expected B. (1) AOP-P.01, Loss of Offsite Power (2) NOT expected C. (1) AOP-P.05, Loss of Unit 1 Shutdown Boards (2) expected D. (1) AOP-P.05, Loss of Unit 1 Shutdown Boards (2) NOT expected Wednesday, May 22, 2013 11:16:31 AM 12
1305 NRC RO Exam
- 13. Given the following plant conditions:
Both Units are at 100% power.
ERCW is in normal alignment.
ERCW header 1A & 2A are indicating LOW flow.
The following MCR alarms are LIT:
M-15A Window B-6, MECH EQUIP SUMP LVL HI.
M-27A Window A-i, UNIT 1 HEADER A PRESSURE LOW.
M-27A Window B-3, UNIT 2 HEADER A PRESSURE LOW.
NO OTHER alarms are lit associated with the ERCW system.
Which ONE of the following ERCW conditions accounts for the above indications?
A.
Supply header 1AI2A has ruptured in the Yard Area.
B.
A discharge header has ruptured in the Yard Area.
C.
A rupture has occurred upstream of the 2A strainer.
D.
A rupture has occurred in the CCW Intake Pumping Station.
Wednesday, May 22, 2013 11:16:31 AM 13
1305 NRC RO Exam
- 14. Given the following plant conditions:
Unit 1 is in Mode 3 following a manual reactor trip required due to a control air line break in the non-essential control air header.
The operating crew performed the applicable emergency instructions and has stabilized the plant.
The crew has implemented AOP-M.02, Loss of Control Air, to address the loss of air.
Based on the given conditions, which ONE of the following identifies a local action that is required during the performance of AOP-M.02 for this loss of non-essential control air?
A. control RCS pressure B. control RCS temperature C. control SG levels D. control PZR level Wednesday, May22, 2013 11:16:31 AM 14
1305 NRC RO Exam
- 15. Given the following plant conditions:
Unit 1 isat 100% power.
The Transmission Operator requests the plant to take in the maximum value of MVARs.
Which ONE of the following transmission lines out of service affects the maximum allowed MVAR incoming value on Unit 1, and how is the adjustment made in accordance with 0-GO-5, Normal Power Operation?
TRANSMISSION LINE METHOD OF ADJUSTMENT A.
A 161 KV line Exciter Voltage Auto Adjuster B.
A 161 KV line Exciter Voltage Base Adjuster C.
A 500 KV line Exciter Voltage Auto Adjuster D.
A 500 KV line Exciter Voltage Base Adjuster Wednesday, May 22, 2013 11:16:31 AM 15
1305 NRC RO Exam
- 16. Given the following plant conditions:
Following a reactor trip, abnormal radiation was noted in the Aux. Building due to a loss of RCS inventory outside containment.
Which ONE of the following identifies a required action and the subsequent check used to determine whether or not the leak is isolated in accordance with ECA-1.2, LOCA Outside Containment?
A. Isolate SI pump Cold Leg Injection; Pressurizer level or RVLIS level rising B. Isolate SI pump Cold Leg Injection; RCS pressure rising C. Isolate RHR Cold Leg Injection; Pressurizer level or RVLIS level rising D. Isolate RHR Cold Leg Injection; RCS pressure rising Wednesday, May 22, 2013 11:16:31 AM 16
1305 NRC RO Exam
- 17. Given the following plant conditions:
The crew is implementing FR-H.1, Loss of Secondary Heat Sink.
CST level is 25%.
No Steam Generator is Intact.
Which ONE of the following identifies, (1) the preference for restoring a SG as a heat sink and (2) which AFW pump is required to be used first in the attempt to establish feed to aSG?
A. (1) Feed a ruptured SG before feeding a faulted SG; (2) TDAFW pump.
B. (1) Feed a ruptured SG before feeding a faulted SG; (2) MDAFW pump.
C. (1) Feed a faulted SG before feeding a ruptured SG; (2) TDAFW pump.
D. (1) Feed a faulted SG before feeding a ruptured SG; (2) MDAFW pump.
Wednesday, May 22, 2013 11:16:31 AM 17
1305 NRC RO Exam
- 18. Given the following plant conditions:
At 0900 the Unit 1 Reactor Trips.
At 0920 a small break LOCA occurs.
At 0950 the crew transitioned to ECA-1.1, Loss of RHR Sump Recirculation, due to the failure of both RHR pumps.
Crew has established one train of ECCS flow per ECA-1.1.
SI flow cannot be terminated due to lack of subcooling.
At 1030 the crew is performing ECA-1.1 Step 20.b, Monitor if ECCS flow should be terminated:
Which one of the following:
(1) identifies the minimum ECCS flow rate per Curve 9 of ECA 1.1 that meets the intent of ECA-1.1, Step 20.b RNO, and (2) the reason for the minimum ECCS flow rate?
REFERENCE PROVIDED A. (1) 325 gpm EGGS flow.
(2) To delay RWST depletion.
B. (1) 325 gpm ECCS flow.
(2) To ensure adequate RVLIS level.
C. (1)400 gpm ECCS flow.
(2) To delay RWST depletion.
D. (1) 400 gpm ECCS flow.
(2) To ensure adequate RVLIS level.
Wednesday, May22, 2013 11:16:31 AM 18
1305 NRC RO Exam
- 19. Given the following plant conditions:
Attime=T0 Tavg
- Tref deviation is 0°F.
Pressurizer level is 45% and stable.
Reactor Power is approximately 75% and stable.
Control Bank D step counters are at 166 steps.
Attime=T+2 mm Tavg is 2°F > Tref and rising.
Pressurizer level 46% and slowly rising.
Pressurizer spray valves have throttled open.
Reactor Power is approximately 76% and slowly rising.
Control Bank D step counters are at 178 steps and rising at 8 steps per m iflute Which ONE of the following identifies (1) the procedure required to be entered and (2) the FIRST action that must be performed?
A. (1)
AOP-C.01, Rod Control System Malfunctions.
(2)
Trip the reactor and enter E-0, Reactor Trip or Safety Injection.
B. (1)
AOP-C.01, Rod Control System Malfunctions.
(2)
Place the rod control mode selector switch to MANUAL.
C. (1)
AOP-C.02, Uncontrolled RCS Boron Concentration Changes.
(2)
Trip the reactor and enter E-0, Reactor Trip or Safety Injection.
D. (1)
AOP-C.02, Uncontrolled RCS Boron Concentration Changes.
(2)
Place the rod control mode selector switch in MANUAL.
Wednesday, May 22, 2013 11:16:31 AM 19
1305 NRC RO Exam
- 20. Given the following plant conditions:
Refueling is in progress on Unit I when a report is made to the control room that an irradiated fuel assembly has been dropped.
The following is the status of alarms on 0-XA-55-1 2A:
1-RA-90-1 12A CNMT BLDG UP COMPT AIR MON HIGH RAD is Lit.
1-RA-90-59A RX BLDG AREA RAD MON HIGH RAD is Lit.
1-RA-90-131A CNTMT PURGE AIR EXH MON HIGH RAD is NOT Lit Based on the given conditions, which ONE of the following correctly completes the statements below?
(1)
A containment ventilation isolation (1) automatically occurred.
and (2)
In accordance with AOP-M.04, Refueling Malfunctions, Auxiliary Building Isolation (2) required to be initiated.
A. (1)has NOT (2)is B. (1)has (2) is NOT C. (1)has (2)is D. (1)has NOT (2) is NOT Wednesday, May 22, 2013 11:16:31 AM 20
1305 NRC RO Exam 21.
Given the following:
Unit 2 was at 100% RTP when a reactor trip occurred due to a sheared shaft on
- 1 RCP.
While the crew was in ES-0.1, Reactor Trip Response, with the plant stable, chemistry reports that #2 SG has developed a tube leak.
Normal letdown is in service.
PZR Level is dropping very slowly with the 2A CCP at 114 gpm.
AOP-R.01, Steam Generator Tube Leak, was entered and the crew is evaluating step 1, Monitor if PZR Level can be maintained.
The crew is required to first (1) and the crew will use (2) during the follow on step to depressurize the RCS in AOP-R.01.
A. (1) isolate letdown (2) auxiliary spray B. (1) isolate letdown (2) normal spray C. (1) start the 2B CCP (2) auxiliary spray D. (1)start the 2B CCP (2) normal spray Wednesday, May 22, 2013 11:16:31 AM 21
1305 NRC RO Exam
- 22. Given the following plant conditions:
Initial conditions:
A reactor startup is in progress on Unit 2 in accordance with 0-GO-2, Unit Startup From Hot Standby To Reactor Critical.
Nuclear Instrumentation indications are:
N-31 = 32 cps N-32 = 36 cps N-35 = 1.3X10-8%
N-36 = 1.5X10-8%
Current plant conditions:
Control bank rods have been withdrawn to the estimated first count doubling position.
Reactor power is stable Nuclear Instrumentation indications are:
N-31 32 cps N-32 5 cps N-35 = 3.1X1O-8%
N-36 = 3.4X10-8%
The SRO declares both N-31 AND N-32 INOPERABLE, and enters AOP-I.01, Nuclear Instrumentation Malfunction.
Based on the given conditions, which ONE of the following completes the statements below?
In accordance with 0-GO-2, the earliest time the crew is required to declare the plant in MODE 2 is when the (1)
Based on the current conditions, in accordance with AOP-I.01, a manual Reactor Trip (2) required.
A. (1) control banks are first withdrawn (2) is B. (1) control banks are first withdrawn (2) is NOT C. (1) reactor is declared CRITICAL (2) is D. (1) reactor is declared CRITICAL (2) is NOT Wednesday, May 22, 2013 11:16:31 AM 22
1305 NRC RO Exam
- 23. ODCM 1.1.1 states that Liquid Radwaste Effluent Line radiation monitor 0-RM-90-122 shall be operable with its alarm setpoint set at a particular value.
Which one of the following completes the statement below?
The alarm setpoint of 0-RM-90-122 is based on (1) and upon alarming, the radiation monitor (2) terminate the release.
A. (1)the limits of 10 CFR 20, Standards for Protection Against Radiation (2) will B. (1) the limits of 10 CFR 20, Standards for Protection Against Radiation (2) will NOT C. (1) the limits of 10 CFR 100, Reactor Site Criteria (2)will D. (1) the limits of 10 CFR 100, Reactor Site Criteria (2)will NOT Wednesday, May 22, 2013 11:16:31 AM 23
1305 NRC RO Exam
- 24. Given the following plant conditions:
A Reactor Trip and Safety Injection has occurred on Unit 1.
While transitioning from E-0, Reactor Trip or Safety Injection, the following plant conditions are noted:
Containment pressure is 6.5 psig and stable.
All RCPs are stopped.
RVLIS Lower Range is indicating 40%.
Core Exit Thermocouples are indicating 710°F.
PZR level is off scale low.
PZR pressure is 400 psig.
RCS Wide Range Hot Leg Temperatures are indicating 680°F.
Which ONE of the following identifies the accident that has occurred and the required procedure to be entered?
A.
A PZR steam space break has occurred and a transition to FR-C.1, Response to Inadequate Core Cooling is required.
B. A PZR steam space break has occurred and a transition to FR-C.2, Response to Degraded Core Cooling is required.
C. An RCS hot or cold leg break has occurred and a transition to FR-C.1, Response to Inadequate Core Cooling is required.
D. An RCS hot or cold leg break has occurred and a transition to FR-C.2, Response to Degraded Core Cooling is required.
Wednesday, May 22, 2013 11:16:31 AM 24
1305 NRC RO Exam
- 25. Given the following plant conditions:
The crew is implementing ES-i.2, Post LOCA Cooldown and Depressurization.
The lA-A Centrifugal Charging Pump (CCP) is running.
Both Safety Injection Pumps (SIPs) are running.
The crew has determined that one SIP can be stopped.
Which ONE of the following completes the statements below?
(1)
After the SIP is stopped, the subcooling value will stabilize at a (1) value when break flow and ECCS flow equalize.
And (2)
If subcooling is adequate, the next required procedure action is to _(2).
A. (1)Lower (2) establish normal charging B. (1) Higher (2) establish normal charging C. (1) Lower (2) stop the 2nd SIP D. (1) Higher (2) stop the 2nd SIP Wednesday, May 22, 2013 11:16:31 AM 25
1305 NRC RO Exam
- 26. Which one of the following identifies the interlocks that must be met before valve FCV-72-23 (Train A Containment Spray Suction from Containment Sump) can be opened from the MCR?
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.
Wednesday, May 22, 2013 11:16:31 AM 26
1305 NRC RO Exam
- 27. Given the following plant conditions:
A large break LOCA has occurred on Unit 1.
Accumulators have discharged and are isolated.
ES-i.3, Transfer to Containment Sump, has been completed.
Containment sump level is now at 84% and slowly rising.
FR-Z.2, Containment Flooding, is in progress.
Based on the given conditions, in accordance with FR-Z.2, which ONE of the following describes; (1) where the required sample is taken, and (2) the reason for sampling?
A. (1)RHRsystem (2) To determine the level of activity, to allow the TSC to determine if excess sump water can be transferred to tanks outside of containment.
B. (1) Containment sump (2) To determine the level of activity, to allow the TSC to determine if excess sump water can be transferred to tanks outside of containment.
C. (1)RHRsystem (2) To ensure shutdown margin is being maintained, since non-borated water has entered the containment sump.
D. (1) Containment sump (2) To ensure shutdown margin is being maintained, since non-borated water has entered the containment sump.
Wednesday, May 22, 2013 11:16:31 AM 27
1305 NRC RO Exam
- 28. Given the following plant conditions:
Unit 1 is at 100% rated thermal power.
1-FCV-62-93, Charging Flow Control Valve is in Manual.
1-FCV-62-89, Charging Seal Water Flow Control Valve, is operating at 60%
open.
Due to a positioner failure, I -FCV-62-89 throttles close, and sticks at the 30% open position.
What effect will this malfunction have on charging pump discharge pressure and RCP seal injection flow?
Charging Pump RCP Seal Discharge Press Injection Flow A.
Lowers Rises B.
Rises Lowers C.
Rises Rises D.
Lowers Lowers Wednesday, May 22, 2013 11:16:31 AM 28
1305 NRC RO Exam
- 29. Given the following plant conditions:
Unit us operating at 100% power after restart following a refueling outage.
U21 18, instantaneous thermal power is within applicable limits.
Rod Control in MANUAL.
VCT level is currently at 32%.
An AUO places an un-borated mixed bed demineralizer in service.
Which ONE of the following completes the statements below?
Assuming NO operator action is taken, the VCT level over time will (1)
In accordance with AOP-C.02, Uncontrolled RCS Boron Concentration Changes, the first corrective action the RO will take that will stop the event in progress is to L2) c)
A.
remain constant place 1-HS-62-79A, Mixed Bed Hi Temp Bypass, to V.C. TK position B.
remain constant perform RCS boration using 0-SO-62-7 C.
rise place 1-HS-62-79A, Mixed Bed Hi Temp Bypass, to V.C. TK position D.
rise perform RCS boration using 0-SO-62-7 Wednesday, May 22, 2013 11:16:31 AM 29
1305 NRC RO Exam
- 30. Given the following plant conditions:
Unit 1 is at 100% rated thermal power.
A routine dilution has just occurred.
The integrater has automatically counted out, however the OATC has NOT returned the CVCS Makeup Selector Switch to the AUTO position.
Which ONE of the following identifes the expected positions of the following valves?
Note:
1-FCV-62-140D, Boric Acid Valve to the Blender 1-FCV-62-128, Inlet to the Top of the VCT 1 -FCV-62-1 40D 1 -FCV-62-1 28 A.
Closed Open B.
Closed Closed C.
Open Closed D.
Open Open Wednesday, May 22, 2013 11:16:31 AM 30
1305 NRC RO Exam
- 31. Given the following plant conditions:
Unit 1 is shutdown with RCS temperature stable at 140°F.
RHR Train A in service at a flow rate of 2800 gpm.
CCS temperature going into the 1A RHR Heat Exchanger 85°F.
The operating crew initiates a RCS heatup at a rate of 20°F/hr in accordance with 0-GO-I, Unit Startup From Cold Shutdown To Hot Standby.
Current plant conditions:
The operating crew has just established an initial stable 20°F/hr heatup.
The operating crew has çjy operated components on the 1-M-6 panel.
CCS temperature going into the 1A RHR Heat Exchanger is 85°F.
Based on the given conditions, which ONE of the following completes the statements below?
Compare the current stable conditions to the initial stable conditions before starting the heatup.
(1)
The current Train A CCS ESF Header flow rate will be (I) the initial Train A CCS ESF flow rate before starting the heatup.
and (2)
The current CCS temperature leaving the 1A RHR Heat Exchanger will be (2) the initial CCS temperature leaving the 1A RHR Heat Exhanger before starting the heatup.
A. (1) lowerthan (2) lower than B. (1) approximately the same as (2) lower than C. (1) lowerthan (2) greater than D. (1) approximately the same as (2) greater than Wednesday, May 22, 2013 11:16:31 AM 31
1305 NRC RO Exam
- 32. Given the following plant conditions:
Unit 2 is at 100% power An inadvertent Safety Injection Actuation has occurred.
In accordance with EPM-3-E-0, Basis Document for E-0 Reactor Trip or Safety Injection, which ONE of the following identifies the reason for the time critical action following an inadvertent SI?
A. to prevent Safety Injection Pumps from running for extended time periods at minimum flow.
B. to reset SI to allow air to be restored to Containment.
C. to secure Centrifugal Charging Pumps running in Injection Mode to prevent filling the PZR solid.
D. to re-establish RCP seal injection flow to prevent RCP seal damage.
Wednesday, May 22, 2013 11:16:31 AM 32
1305 NRC RO Exam
- 33. Which ONE of the following identifies the pressure that relief valve 63-637, RHR Pump Discharge, will start relieving and the tank where the flow through the valve will be routed?
Pressure Tank A.
550 psig RCDT B.
550 psig PRT C.
600 psig RCDT D.
600 psig PRT Wednesday, May 22, 2013 11:16:31 AM 33
1305 NRC RO Exam
- 34. Given the following plant conditions:
Unit 2 is at 90% power.
Due to a leaking PORV, 2-FCV-68-332 PORV block valve was closed.
PRT level is 80%
PRT pressure is 7 psig PRT Temperature is 145°F Which ONE of the following describes the action(s) to be taken first, and the reason for the action(s), in 2-SO-68-5, Pressurizer Relief Tank, to return the PRT to normal?
A.
Start a Waste Gas Compressor, open 2-PCV-68-301, PRT VENT TO WDS VENT HDR, to restore PRT pressure.
B. Align the B RCDT pump, open FCV-68-305, N2 SUPPLY TO PRT, open 2-LCV-68-310, PRT DRAIN TO RCDT, to restore PRT level.
C. Open 2-FCV-68-303, PRIMARY WATER TO PRT, to restore PRT level.
D. Open 2-FCV-68-303, PRIMARY WATER TO PRT, to restore PRT temperature.
Wednesday, May 22, 2013 11:16:31 AM 34
1305 NRC RO Exam
- 35. Given the following plant conditions:
Unit 1 is operating at 100% power.
1-RA-90-123A CCS LIQ EFF MON HIGH RAD Alarm is LIT.
The red HIGH light is LIT on CCS LIQUID EFFLUENT RADMON 0-RM-90-1 23A.
CCS surge tank level was increasing but is now stable.
RC PUMPS THRM BARRIER RETURN HEADER FLOW LOW Alarm is LIT.
Which ONE of the following completes the statement below concerning the automatic actions that are designed to occur?
The thermal barrier heat exchanger containment isolation inlet and outlet valves to (1) close and the thermal barrier booster pumps (2)
A. (1) the affected RCP ONLY (2) trip B. (1) the affected RCP ONLY (2) continue to run C. (1) all four (4) RCPs (2) trip D. (1) all four (4) RCPs (2) continue to run Wednesday, May 22, 2013 11:16:31 AM 35
1305 NRC RO Exam
- 36. Given the following plant conditions:
Unit 1 is operating at 100% RTP.
Pressure Control Channel Selector Switch, 1-XS-68-340D is selected to PT-68-340 & 334 position.
1-PT-68-334, Pressurizer Pressure Transmitter, fails LOW.
The operating crew enters AOP-l.04, Pressurizer Instrument and Control Malfunctions.
Which ONE of the following completes the statements below?
Before any operator actions occur the failure (1) result in the pressurizer back-up heaters being energized.
When AOP-l.04 performance is completed (2) of the PORVs will be able to automatically open if pressurizer pressure begins rising.
c)
A.
will both B.
will only one C. will NOT both D. will NOT only one Wednesday, May 22, 2013 11:16:31 AM 36
1305 NRC RO Exam
- 37. Given the following plant conditions:
Unit 2 was operating at 100% power.
The Loop 1 pressurizer spray valve controller failed causing the spray valve to fully open.
If NO operator actions are taken, which ONE of the following identifies:
(1) The Master pressurizer pressure controller output would and (2) This failure lead to an automatic reactor trip.
A. (1) INCREASE (2) will NOT B. (1) INCREASE (2) will C. (1) DECREASE (2) will NOT D. (1) DECREASE (2) will Wednesday, May 22, 2013 11:16:31 AM 37
1305 NRC RO Exam
- 38. Which ONE of the following identifies the plant electrical boards that supply power to the listed components on Unit 1?
SSPS Train B Reactor Reactor Trip Bypass Breaker A Trip Breaker 48V UV coil (BYA) Control Power Circuit A.
120V AC Vital Instrument 125V DC Vital Battery Board I
Power Boards 1-Il and 1-IV B.
120V AC Vital Instrument 125V DC Vital Battery Board II Power Boards 1-Il and 1-IV C. 120V AC Vital Instrument 125V DC Vital Battery Board I
Power Board 1-Il ONLY D. 120V AC Vital Instrument 125V DC Vital Battery Board II Power Board 1-li ONLY Wednesday, May 22, 2013 11:16:31 AM 38
1305 NRC RO Exam
- 39. Given the following plant conditions:
Unit 1 is operating at 100% power.
The operating crew is responding to a loss of 120V AC Vital Instrument Power Board 1-I.
PZR pressure transmitter 1-PT-68-334 (Channel II) fails LOW.
If NO operator actions are taken, which ONE of the following identifies how SSPS and ECCS will respond?
A.
Both trains of SSPS SI master relays will actuate AND both trains of ECCS equipment auto start.
B.
Both trains of SSPS SI master relays will actuate BUT only B train ECCS equipment auto starts.
C. Only the B train SSPS SI master relays will actuate BUT both trains of ECCS equipment auto start.
D. Only the B train SSPS SI master relays will actuate AND only B train ECCS equipment auto starts.
Wednesday, May 22, 2013 11:16:31 AM 39
1305 NRC RO Exam
- 40. Which ONE of the following Containment Cooling System fans will trip and isolate as a DIRECT result of a Containment Isolation Phase-A Signal?
A.
Lower Compartment Coolers B.
Upper Compartment Coolers C. Incore Instrument Room Coolers D.
Control Rod Drive Motor Coolers Wednesday, May 22, 2013 11:16:31 AM 40
1305 NRC RO Exam
- 41. Given the following plant conditions:
Unit 1 at 100% RTP when a LOCA occurs.
A Safety Injection occurs due to containment pressure rising.
The containment pressure has continued to rise and is now 3.2 psig.
Which ONE of the following completes the statements below?
The Containment Air Return Fans would automatically start 10 minutes after the (1) signal.
If the lA-A Air Return Fan tripped on excessive current when the start was attempted, the (2) indicating lights on the MCR handswitch would be LIT?
A.
Phase A Isolation GREEN and WHITE only B.
Phase A Isolation GREEN, WHITE and RED C.
Phase B Isolation GREEN and WHITE only D.
Phase B Isolation GREEN, WHITE and RED Wednesday, May 22, 2013 11:16:31 AM 41
1305 NRC RO Exam
- 42. Given the following plant conditions:
Unit 1 was operating at 100% power.
The operating crew is performing E-1, Loss of Reactor or Secondary Coolant.
RCS temperature is 220° F and stable.
Lower Containment temperature is 120 °F Based on the given conditions, which ONE of the following completes the statements below?
In accordance with Tech Spec 3.6.1.5, Containment Systems-Air Temperature, Lower Containment temperature (1) above the maximum technical specification limit.
After an automatic initiation of the Containment Spray System, E-1 first allows the containment spray pumps to be stopped and placed in A-AUTO after the containment pressure drops to less than (2)
L)
A.
is 2.8 psig B.
is NOT 2.0 psig C. is NOT 2.8 psig D. is 2.0 psig Wednesday, May 22, 2013 11:16:31 AM 42
1305 NRC RO Exam
- 43. Which ONE of the following identifies a direct electrical interlock associated with opening 1-FCV-72-40, RHR Spray Header A Isolation?
1-FCV-72-40 cannot be opened from the MCR unless A. 1-FCV-74-33, RHR Crosstie, is fully open B. 1-FCV-63-1, RWST to RHR Suction, is fully open C. 1-FCV-74-3, RHR Pump lA-A Suction, is fully open D. 1-FCV-63-72, Containment Sump to RHR Pump IA-A Isolation, is fully open Wednesday, May 22, 2013 11:16:31 AM 43
1305 NRC RO Exam
- 44. Given the following plant conditions:
Unit 1 reactor power is stable at 90%.
Turbine Impulse pressure transmitter 1-PT-i -72 fails LOW.
Which ONE of the following identifes the status of the white lights on I -M-4 for (1) 1-Xl-1-103D, STEAM DUMPS ACTUATED D FSVS ENERGIZED and (2) 1-Xl-1-103A/B, STM DUMPS ARMED?
1-Xl-l-103D 1-Xl-1-1O3AIB A.
DARK DARK B.
DARK LIT C.
LIT DARK D.
LIT LIT Wednesday, May 22, 2013 11:16:31 AM 44
1305 NRC RO Exam
- 45. Given the following plant conditions:
Unit 2 startup in progress.
The Main Generator has just been synchronized and loaded to 40 MWe.
The Steam Pressure (2-PT-i -33) input to the steam dump controller fails HIGH.
Assuming NO action by the crew, which ONE of the following describes (1) which time in core life the effect on core reactivity is greatest, and (2) how many of the steam dump valves would be responding to the failure?
Li)
A.
MOL 3 valves only B.
MDL All l2valves C.
EOL 3 valves only D.
EOL All 12 valves Wednesday, May 22, 2013 11:16:31 AM 45
1305 NRC RO Exam
- 46. Given the following plant conditions:
Unit 1 is at 72% power.
PT-I -33, Steam Header Pressure to DCS, indicates 920 psig.
PT-I -33A, Steam Header Pressure to DCS, indicates 900 psig.
PT-I -33B, Steam Header Pressure to DCS, indicates 890 psig.
PT-I -33 fails Low.
Which ONE of the following describes the effect this failure will have on Unit I the steam header pressure portion of DCS?
The steam header pressure DCS control will be in A. median select B. average C. manual D. single element Wednesday, May 22, 2013 11:16:31 AM 46
1305 NRC RD Exam
- 47. Which ONE of the following is the Alternate power supply for the Unit 2 TDAFW pump Trip and Throttle valve, 2-FCV-1-51A-S?
A.
125V DC Vital Board I
B.
125V DC Vital Board II C. 125V DC Vital Board Ill D. 125V DC Vital Board IV Wednesday, May 22, 2013 11:16:31 AM 47
1305 NRC RO Exam
- 48. Given the following plant conditions:
Unit 1 is at 3% power making preparations for Main Turbine warm up.
The monthly surveillance for lA-A DIG is in progress and the D/G is paralleled to the board.
The normal supply breaker to the I B 6.9kV Unit Board inadvertently trips.
Consequently, lA-A 6.9kV Shutdown Board DG Supply breaker trips on overcurrent.
Unit I remains at power.
Based on the given conditions, which ONE of the following completes the statements below?
The operation of the overcurrent relay will cause 1 A-A 6.9kV Shutdown Board DG supply breaker to automatically trip open and (1)
An immediate reactor trip (2) required.
A. (1) lock-out (2) is B. (1) lock-out (2) is NOT C. (1) subsequently reclose in automatic (2) is D. (1) subsequently reclose in automatic (2) is NOT Wednesday, May22,2013 11:16:31 AM 48
1305 NRC RO Exam
- 49. Given the following plant conditions:
A station blackout occurs.
The hydrogen pressure has been reduced to less 3 psig on both units generators.
Which ONE of the following completes the statements below?
EA-250-1, Load Shed of Vital Loads After Station Blackout, requires the I 25v DC loads to be stripped within (1) following a loss of power to three of the 6900V AC shutdown boards.
EA-250-2, Load Shed of 250V Loads After Station Blackout, requires the DC circuit seal oil pump breakers to be opened within (2) w A. 45 minutes 45 minutes B. 45 minutes 90 minutes C. 90 minutes 45 minutes D. 90 minutes 90 minutes Wednesday, May 22, 2013 11:16:31 AM 49
1305 NRC RO Exam
- 50. Given the following plant conditions:
Unit 1 was operating at 100% power when a Safety Injection occurred.
A station blackout has NOT occurred.
Eighteen (18) seconds after the Safety Injection, a loss of 1 25V Vital DC Power Channel II occurs.
Which ONE of the following identifies the current status of RHR pump 1 B-B?
A. RHR pump I B-B is NOT running but can be started from the MCR handswitch.
B. RHR pump lB-B is NOT running and can NOT be started from the MCR handswitch.
C. RHR pump lB-B is running and can be stopped from the MCR handswitch.
D. RHR pump 1 B-B is running but can NOT be stopped from the MCR handswitch.
Wednesday, May 22, 2013 11:16:31 AM 50
1305 NRC RO Exam
- 51. Given the following plant conditions:
Unit 1 is at 100% rated thermal power Diesel Generator (DG) lA-A is being tested for its monthly surveillance test which requires loading to 4400 kw.
Current load is 2000 kw.
Subsequently, 2B-B 6.9KV SDBD experiences a complete loss of voltage.
No SI signal is present on either unit.
Based on the given conditions, which ONE of the following correctly completes the statements below:
(1) Manual control of the lA-A DG load (1) be retained in the control room.
and (2) The reverse power trip for the IA-A DG (2) be functional.
A. (1)will (2) will B. (1)will (2)will NOT C. (1)will NOT (2) will D. (1)will NOT (2) will NOT Wednesday, May 22, 2013 11:16:31 AM 51
1305 NRC RO Exam
- 52. Given the following plant conditions: RA-90-125A, MAIN CNTRL RM INTAKE MON HIGH RAD is LIT RA-90-126A, MAIN CNTRL RM INTAKE MON HIGH RAD is NOT LIT Based on the conditions given, which ONE of the following completes the statements below?
(1)
Main Control Room (MCR) Isolation (1) automatically occurred.
and (2)
The MCR is currently being maintained at a positive pressure by the (2)
A. (1) has (2)
Main Control Room Air Handling Units B. (1) has NOT (2)
Main Control Room Air Handling Units C. (1) has (2)
Control Building Emergency Air Pressurization Fans D. (1) has NOT (2)
Control Building Emergency Air Pressurization Fans Wednesday, May 22, 2013 11:16:31 AM 52
1305 NRC RO Exam
- 53. Which ONE of the following identifies how 1-FCV-67-66A, ERCW HDR IA SUP TO DG1A-A HX Al &A2 responds to a normal start and stop of Diesel generator lA-A?
The ERCW valve will automatically open after the start signal when the DG speed risesto (1)
When the diesel generator is stopped, the ERCW valve (l-FCV-67-66A) will be closed (2) w START STOP A.
40 rpm using the handswitch on 0-M-26 B.
40 rpm automatically when DG stops following the idle speed run C.
200 rpm using the handswitch on 0-M-26 D.
200 rpm automatically when DG stops following the idle speed run Wednesday, May 22, 2013 11:16:31 AM 53
1305 NRC RD Exam
- 54. Given the following plant conditions:
Unit I was at 100% power when a LOCA occurred.
AUOs are performing EA-32-1, Establishing Control Air to Containment, Appendix A, Re-establishing Air to Containment on Unit 1.
FCV-32-80, Rx Bldg Train A Essential Air, is closed.
FCV-32-110, Rx Bldg Nonessential Air, is closed.
Based on the given conditions, which ONE of the following completes the statements listed below?
(1) must be opened to restore air to PCV-68-340D, Pressurizer Spray Valve.
and In accordance with EA-32-1, the test pushbutton must be depressed for approximately 30 seconds while holding the applicable control switch in OPEN to ensure downstream air pressure is greater than a minimum of (2) psig in order for the valve to remain open.
A. (1) FCV-32-80 (2) 50 B. (1) FCV-32-80 (2) 69 C. (1) FCV-32-110 (2) 50 D. (1) FCV-32-110 (2) 69 Wednesday, May 22, 2013 11:16:31 AM 54
1305 NRC RO Exam
- 55. Given the following plant conditions:
Both Units in service at 100% RTP.
Upper Compartment Cooling Units A-A and B-B are in service on both units.
Compare the effects of the inadvertent closing of the Lower Compartment Cooling Unit (LCCU) valves listed:
Unit 1, LCCU lA-A ERCW Inlet FCV (Outboard), 1-FCV-67-107 Unit 2, LCCU 2A-A ERCW Inlet FCV (Outboard), 2-FCV-67-107 Based on the given conditions, if both of the -107 valves were closed, which ONE of the following answers the statements below?
(1) Upper Containment temperature would RISE on (1) and (2) Additional Upper Containment Cooling Units are available to be placed in service for ONLY (2)
A.
(1) both Units I and2 (2) Unit 1 B.
(1) both Units I and 2 (2) Unit 2 C.
(1) Unit 1 only (2) Unit 2 D.
(1) Unit 2 only (2) Unit 1 Wednesday, May 22, 2013 11:16:31 AM 55
1305 NRC RO Exam
- 56. Given the following plant conditions:
A Unit I reactor start up following a refueling outage is in progress lAW O-GO-2, Unit Startup from Hot Standby to Reactor Critical.
RCS boron concentration was 1390 ppm for the ECP calculation.
Just prior to beginning rod withdrawal for the startup chemistry reports the following boron concentrations:
RCS boron concentration: 1380 ppm Pressurizer boron concentration: 1325 ppm Which ONE of the following completes the statements below?
Actual critical rod height will be (1) than the ECP.
PZR boron concentration (2) required to be raised before the startup can continue.
A. (1) higher (2)is B. (1) higher (2) is NOT C. (1)lower (2)is D. (1)lower (2) is NOT Wednesday, May 22, 2013 11:16:31 AM 56
1305 NRC RO Exam
- 57. Given the following plant conditions:
A reactor start up without Physics Testing is in progress lAW 0-GO-2, Unit Startup from Hot Standby to Reactor Critical.
The crew has blocked P-6.
Reactor power is 5 X I 0- % and slowly rising.
Which ONE of the following is the lowest of the listed values that exceeds the maximum SUR limit allowed per 0-GO-2?
A. 0.4 dpm B. 0.6 dpm C. 0.8 dpm D.
1.1 dpm Wednesday, May 22, 2013 11:16:31 AM 57
1305 NRC RO Exam
- 58. Given the following plant conditions:
Unit 1 is operating steady state at 60% reactor power.
Rod control is in MANUAL.
Charging flow control valve 1-FCV-62-93A is in MANUAL.
The failure of a temperature instrument results in greater than a 5% difference between the pressurizer Program Level and Actual pressurizer level.
Based on the given conditions, assuming NO operator action, which ONE of the following completes the statements below?
The (1) failing HIGH will result in the above condition.
The Pressurizer backup heaters (2) be automatically energized.
LIJ A.
Thot RTD #1 will NOT B.
Thot RTD #1 will C.
Tcold RTD #1 will NOT D.
Tcold RTD #1 will Wednesday, May 22, 2013 11:16:32 AM 58
1305 NRC RO Exam
- 59. Given the following conditions:
Unit 1 is in Mode 3 when a Safety Injection occurs.
Following the Safety Injection, both the lA-A 6.9KV Shutdown Board and the 2B-B 6.9 KV Shutdown Boards trip on differential.
Which ONE of the following describes the status of the EGTS and ABGTS systems?
A.
A EGTS fan and A ABGTS fan are running.
B.
B EGTS fan and A ABGTS fan are running.
C. A EGTS fan and B ABGTS fan are running.
D. B EGTS fan and B ABGTS fan are running.
Wednesday, May 22, 2013 11:16:32 AM 59
1305 NRC RO Exam
- 60. Given the following plant conditions:
Unit 1 is in Mode 6.
The current Spent Fuel Pool boron concentration is 2120 ppm.
Refueling Water Storage Tank (RWST) is being used as the TRM borated water source and is at the lowest boron concentration allowed as identified in S0-78-1,Spent Fuel Pit Coolant System.
A leak on the Spent Fuel Pool cooling system results in the need for makeup from the RWST.
Which ONE of the following completes the statement below relative to the Spent Fuel Pool?
Using the RWST to makeup to the Spent Fuel Pool will result in a/an (1) in the Spent Fuel Pool boron concentration.
To meet LCO 3/4.7.13, SPENT FUEL MINIMUM BORON CONCENTRATION, requires a minimum boron concentration of (2) ppm.
Li)
A. decrease 1950 B. decrease 2000 C. increase 1950 D. increase 2000 Wednesday, May 22, 2013 11:16:32 AM 60
1305 NRC RO Exam
- 61. Given the following plant conditions:
Unit 1 is at 100% RTP.
Fuel Assembly shuffles are being made in the Spent Fuel Pit.
0-RM-90-102, Spent Fuel Pit Radiation Monitor, has been declared INOPERABLE and removed from service due to an instrument malfunction.
Which ONE of the following completes the statements below?
Technical Specification 3.9.12, Auxiliary Building Gas Treatment System, would (1) continued movement of fuel assemblies in the Spent Fuel Pit.
If 0-RM-90-103, Spent Fuel Pit Radiation Monitor, subsequently detects a high Radiation condition, 2) of Auxiliary Building Isolation equipment will actuate with no operator actions.
cj A.
allow pjjjy one train B.
allow both trains C.
NOT allow QDJY one train D.
NOT allow both trains Wednesday, May 22, 2013 11:16:32 AM 61
1305 NRC RO Exam
- 62. Given the foHowing plant conditions:
Unit us operating at 100% power.
ABGTS Train A is running for its 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> surveillance.
Waste Gas Decay Tank J relief valve develops a flange leak and the tank contains high activity gas.
Which ONE of the following completes the statement below?
The flange leak will be detected by Note:
0-RE-90-1 18, Waste Gas Rad Monitor 0-RE 101, Auxiliary Building Ventilation Monitor 1-RE-90-400, Unit I Shield Building Vent Monitor A. Only 0-RE-90-101 B. Only 0-RE-90-1 18 C. Both 0-RE-90-101 and 1-RE-90-400 D. Both 0-RE-90-1 18 and 1 -RE-90-400 Wednesday, May 22, 2013 11:16:32 AM 62
1305 NRC RO Exam
- 63. Given the following plant conditions:
1-RA-90-IC AUX BLDG AREA RAD MON INSTR MALFUNC (M12A, B-7) is LIT Which ONE of the following completes the statements below?
1-RA-90-1C INSTR MALFUNC alarm (1) result in an automatic action.
Source checking 1 -RA-90-1 C, (2) cause the rad monitor to alarm.
A. (1) will (2) will B. (1) will (2) will NOT C. (1) will NOT (2) will D. (1) will NOT (2) will NOT Wednesday, May 22, 2013 11:16:32 AM 63
1305 NRC RD Exam
- 64. Given the following plant conditions:
Maintenance personnel report that a Service Air connection providing air to a pneumatic grinder has broken and cannot be isolated.
Air Header Pressure indications are as follows: Pl-32-104A, AUX CONT AIR HDR A PRESS Pl-32-105A, AUX CONT AIR HDR B PRESS PI-32-200, CONT AIR HDR PRESS PI-33-199, SERV AIR HDR PRESS 92 psig 92 psig 94 psig and slowly lowering 90 psig and slowly lowering Which ONE of the following completes the statements below?
(1)
At the current pressures, PCV-33-4, SERVICE AIR ISOL (1) open.
(2)
If PCV-33-4 automatically closes, once the Service Air Header is repressurized, the valve (2) is A. (1)
(2) must be reset before it will open B. (1) is NOT (2) must be reset before it will open C. (1)
(2)
D. (1)
(2) is will reopen automatically is NOT will reopen automatically Wednesday, May 22, 2013 11:16:32 AM 64
1305 NRC RO Exam
- 65. Given the following plant conditions; Unit 1 is in Mode 4.
AOP-N.03, External Flooding, has been implemented.
Which ONE of the following completes the statements below?
(1)
In accordance with AOP-N.03, once Stage I preparation has been initiated, the Stage I actions must be completed within a maximum of (1) and (2)
If river level continues to rise, HPFP must be connected to the piping on the discharge of the (2)
AFW pump.
A.
10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Motor Driven B.
10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Turbine Driven C.
14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> Motor Driven D.
14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> Turbine Driven Wednesday, May 22, 2013 11:16:32AM 65
1305 NRC RO Exam
- 66. In accordance with ODM-Y, Standing Orders and Shift Orders, which ONE of the following completes the statements below?
(1)
The maximum time a Standing Order for administrative issues can remain inaffectforis (1) and (2) A Standing Order L2j be used to circumvent an operating procedure.
A. (1) 30 days (2) can B. (1) 30 days (2) can NOT C. (1) 1 year (2) can D. (1) 1 year (2) can NOT Wednesday, May 22, 2013 11:16:32AM 66
1305 NRC RO Exam
- 67. Given the following plant condition:
Unit I is conducting an EOL coastdown in accordance with GO-5, Normal Power Operation.
Which ONE of the following identifies...
(1) how the unit will be operated during the coastdown, and (2) why, in accordance with GO-5, reactor power changes should be limited to 1% per hour?
A. (1) The crew will reduce turbine load as needed to maintain Tavg on program.
(2) To prevent MTC from exceeding Tech Spec limits.
B. (1) The crew will reduce turbine load as needed to maintain Tavg on program.
(2) To avoid xenon peaking which could force a plant shutdown.
C. (1) The crew allow Tavg to drop while maintaining reactor power as stable as possible with AFD being maintained less than the positive limit.
(2) To prevent MTC from exceeding Tech Spec limits.
D. (1) The crew allow Tavg to drop while maintaining reactor power as stable as possible with AFD being maintained less than the positive limit.
(2) To avoid xenon peaking which could force a plant shutdown.
Wednesday, May 22, 2013 11:16:32AM 67
1305 NRC RO Exam
- 68. Given the following plant conditions:
Unit I is in MODE 1 with RCS pressure at 2235 psig.
The following RCS leakages were determined per 1-Sl-OPS-068-1 37.0, Reactor Coolant System Water Inventory.
Total RCS leakage
=
12.41 gpm PRT leakage
=
5.32 gpm CLA #1 leakage
=
0.88 gpm RCDT leakage
=
3.18 gpm S/G #2 leakage
=
0.07 gpm S/G#1,#3,#4 leakage
=
0.00 gpm
[Note: Assume leakages other than those given as zero (0) gpm].
Which ONE of the following completes the statement below?
LCO 3.4.6.2, Reactor Coolant System Operational Leakage, action is required to be entered because the limit(s) has/have been exceeded?
- 1. IDENTIFIED LEAKAGE
- 3. PRIMARY-TO-SECONDARY LEAKAGE A.
I only B.
2 only C.
2 and 3 only D.
1 and 3 only Wednesday, May 22, 2013 11:16:32AM 68
1305 NRC RO Exam
- 69. Given the following plant conditions:
While performing a cooldown on Unit 1 from Mode 3 to Mode 4 the following parameters were logged:
Time RCS Press RCS Temp PZR LIQ Space Temp 0200 2200 psig 553°F 650°F 0230 1550 psig 527°F 606°F 0300 1135 psig 505°F 560°F 0330 765 psig 447°F 494°F 0400 400 psig 402°F 440°F Which ONE of the following describes the Tech Spec I TRM implications of these conditions?
A. RCS cooldown rate limits were exceeded; Tech Spec action is required within a maximum of 30 minutes.
B. RCS cooldown rate limits were exceeded; Tech Spec action is required within a maximum of 60 minutes.
C. PZR cooldown rate limits were exceeded; TRM action is required within a maximum of 30 minutes.
D. PZR cooldown rate limits were exceeded; TRM action is required within a maximum of 60 minutes.
Wednesday, May 22, 2013 11:16:32 AM 69
1305 NRC RO Exam
- 70. Given the following plant conditions:
A main control room annunciator, 2-M15-A, A-4, PdS-27-13B TRAV SCREEN 2B DIFF PRESS HI, has alarmed repeatedly over the past hour.
Traveling Screen delta P on 2-PDI-27-13A reads 1.5 in H 2
0 and steady.
An AUO is dispatched to CCW pumping station several times and reports:
local screen delta P reads 1.5 in H 2
0 there are NO visible obstructions.
Screen wash pumps and traveling screens are NOT running.
Based on the given conditions, which ONE of the following completes the statements below?
In accordance with OPDP-4, Annunciator Disablement, this alarm (1) the definition of a nuisance alarm.
and An annuciator that is disabled due to being a nuisance alarm, (2) required to be logged in the narrative log.
A. (1)meets (2)is B. (1) meets (2) is NOT C. (1)doesNOTmeet (2) is D. (1) does NOT meet (2) is NOT Wednesday, May22, 2013 11:16:32AM 70
1305 NRC RO Exam
- 71. Given the following plant conditions:
A Reactor Trip and safety injection have occurred on Unit 1 due to SGTR on #3 SG.
The crew has just entered E-3, Steam Generator Tube Rupture.
SG #3 pressure is 1030 psig.
PCV-1-23 SG 3 (Atmospheric Relief) is reported to be cycling open and close.
PCV-1-23 setpoint is 85%.
In accordance with E-3, which ONE of the following is the first action required to be taken to minimize the radiation release?
A. Place PCV-1-23 Atmospheric Relief valve handswitch to CLOSE.
B. Adjust PCV-1-23 Atmospheric Relief valve setpoint to 87%.
C. Place controller for PCV-1-23 in MANUAL and adjust Atmospheric Relief valve setpoint to 0%.
D. Isolate Atmospheric Relief PCV-1-23 isolation valve VLV-1-621 using EA-1-2, Local Control of S/G PORVs.
Wednesday, May 22, 2013 11:16:32AM 71
1305 NRC RO Exam
- 72. Given the following plant conditions:
A source check is to be performed on CCS radiation monitor 1-RE-90-123.
Which ONE of the following completes the statements below?
The source check is verified by observing the CU The isolation function of the Surge Tanks vent be manually blocked during the source check in accordance with I -SO-90-1, Liquid Process Radiation Monitors.
A.
(1) analog rate meter trending upscale (2) can B. (1) analog rate meter trending upscale (2) can NOT C. (1) bargraph display responds upscale (2) can D. (1) bargraph display responds upscale (2) can NOT Wednesday, May 22, 2013 11:16:32 AM 72
1305 NRC RO Exam
- 73. Given the following plant conditions:
Unit 2 at 100% power.
Panel 2-M-1 Annunciator Window 125V DC VITAL CHGR III FAILNITAL BAT III DISCHARGE alarms.
The crew enters AOP-P.02, Loss Of 125V DC Vital Battery Board.
A reactor trip 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 (1) because (2)
A. (1) allowed after the crew enters ES-0.1, Reactor Trip Response (2)
EPM-4 states that AOP-P.02 has priority over ES-0.1 B. (1) allowed after the crew enters ES-0.1, Reactor Trip Response (2) restoring power could have an impact on meeting the goals of the EOP C. (1)
NOT allowed until the crew exits the EOPs and enters a normal ops procedure such as 0-GO-6, Power Reduction from 30% Reactor Power to Hot Standby (2) the procedure reader must remain dedicated to the EOP in effect until the EOP5 are exited D. (1)
NOT allowed until the crew exits the EOPs and enters a normal ops procedure such as 0-GO-6, Power Reduction from 30% Reactor Power to Hot Standby (2) the actions taken in AOP-P.02 could conflict with the performance of the EOP Wednesday, May22, 2013 11:16:32AM 73
1305 NRC RO Exam
- 74. Given the following picture of various SG#1 pressure indications:
SG ESSE J 4 S0 HEADE PESS!
As identified in EPM-4, Users Guide, which ONE of the following identifies Post Accident Monitoring (PAM) indications?
A.
1-PI-1-2A is a PAM indication.
1-PRI-1-2 is NOT a PAM indication.
B.
1-Pl-1-2A is NOT a PAM indication.
1-PR-1-2 is a PAM indication.
C. Both 1-Pl-1-2A AND 1-PR-1-2 are PAM indications.
D. Neither 1-Pl-1-2A NOR 1-PR-1-2 are PAM indications.
Wednesday, May 22, 2013 11:33:08 AM 74
1305 NRC RO Exam
- 75. Given the following plant conditions:
Unit I reactor is shutdown.
RCS in solid water operation.
All RCS temperatures are approximately 125°F.
RCS pressure is 330 psig.
RHR Train A is in service.
1 A-A CCP is operating.
Subsequently:
RCS pressure increases to 600 psig.
Which ONE of the following describes:
1) the effect the pressure increase would have on the PORVs, AND 2) the action(s) which is/are directed to be taken in accordance with AOP-R.03, RHR System Malfunction if RCS pressure is NOT promptly reduced below 600 psig?
REFERENCE PROVIDED L1 A.
Only ONE PORV OPENS Stop the Charging pump B.
Only ONE PORV OPENS Stop A Train RHR pump C.
BOTH PORVS OPEN Stop the Charging pump D.
BOTH PORVS OPEN Stop A Train RHR pump You have completed the test!
Wednesday, May 22, 2013 11:16:32 AM 75
References for 1305 NRC RO Exam 1.
Steam Tables 2.
Mollier Diagram 3.
ECA-1.1 Loss of ECCS Sump Recirculation; Curve 9 Minimum ECCS Flow for Decay Heat vs. Time After Trip, rev 12 4.
Pressure Temperature Limits Report; Sequoyah Unit 1 LTOPS Selected Setpoints pg 11
ANSWER KEY REPORT for 1305 NRC RO Exam Test Form: 0 ID Points Type 0
1 007 EK1.02 301 1.00 MCS B
2 008 AK2.01 302 1.00 MCS A
3 009 EK1.02 503 1.00 MCS C
4 011 EG2.1.31 4 1.00 MCS A
5 015 AG2.1.28 305 1.00 MCS A
6 022 AK3.05 306 1.00 MCS A
7 025 AK2.05 707 1.00 MCS D
8 026 AA1.06 308 1.00 MCS C
9 029 EA1.09 309 1.00 MCS B
10 040 AA2.02 310 1.00 MCS C
11 054AK1.01 711 1.00 MCS C
12 056 G2.4.4 312 1.00 MCS A
13 062 AA2.01 13 1.00 MCS C
14 065AK3.08714 1.00 MCS D
15 077 AA1.03 15 1.00 MCS C
16 W/E04 EA2.2 316 1.00 MCS D
17 W/E05 EK2.2 317 1.00 MCS B
18 W/E11 EK3.4 318 1.00 MCS A
19 001 AA2.05 19 1.00 MCS B
20 036 AK2.02 720 1.00 MCS A
21 037AG2.2.44 321 1.00 MCS B
22 032 AG2.1.23 722 1.00 MCS A
23 059 AK3.01 23 1.00 MCS A
24 074 EA2.07 324 1.00 MCS C
25 W/E03 EK1.1 325 1.00 MCS C
26 W/E14EA1.1 326 1.00 MCS C
27 W/E15 EK3.1 727 1.00 MCS A
28 003 K6.02 28 1.00 MCS C
29 004 A2.06 329 1.00 MCS C
30 004 A4.12 30 1.00 MCS B
31 005 A1.03 831 1.00 MCS B
32 006 K5.05 832 1.00 MCS C
33 007 A3.01 33 1.00 MCS D
34 007 G2.1.20 334 1.00 MCS D
35 008 A3.01 335 1.00 MCS C
36 010 K6.01 336 1.00 MCS C
37 010 K6.03 337 1.00 MCS D
38 012K2.01 738 1.00 MCS A
39 013 K4.07 39 1.00 MCS B
40 022 K4.03 40 1.00 MCS C
41 025 A4.02 541 1.00 MCS D
42 026 A1.02 742 1.00 MCS B
43 026K1.01 343 1.00 MCS D
44 039K3.0644 1.00 MCS B
45 039 K5.08 545 1.00 MCS D
46 059 A3.04 546 100 MCS B
Thursday, May 30, 2013 3:58:25 PM
ANSWER KEY REPORT for 1305 NRC RO Exam Test Form: 0 ID Points Type 0
47 061 K2.01 47 1.00 MCS B
48 062 A2.09 748 1.00 MCS C
49 063 A1.01 349 1.00 MCS B
50 063 K3.02 350 1.00 MCS D
51 064 K3.03 551 1.00 MCS A
52 073 K1.01 852 1.00 MCS C
53 076 A4.02 53 1.00 MCS A
54 078 G2.4.35 754 1.00 MCS A
55 103 K1.0I 855 1.00 MCS C
56 002 K5.07 356 1.00 MCS C
57 015 A1.02 357 1.00 MCS D
58 016 A3.01 758 1.00 MCS C
59 027 K2.01 259 1.00 MCS B
60 033 A2.01 60 1.00 MCS D
61 034 K6.02 361 1.00 MCS A
62 071 K3.05 362 1.00 MCS C
63 072 A4.01 363 1.00 MCS D
64 079 K4.01 364 1.00 MCS A
65 086 K1.03 365 1.00 MCS A
66 G2.1.15366 1.00 MCS D
67 G 2.1.43 567 1.00 MCS B
68 G 2.2.22 368 1.00 MCS B
69 G 2.2.42 69 1.00 MCS A
70 G 2.2.43 770 1.00 MCS A
71 G2.3.11371 1.00 MCS B
72 G 2.3.5 372 1.00 MCS D
73 G 2.4.8 573 1.00 MCS B
74 G 2.4.3 774 1.00 MCS C
75 G 2.4.9 375 1.00 MCS D
SECTION 1 (75 items) 75.00 Thursday, May 30, 2013 3:58:25 PM 2