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H .B. Robinson ILC-13 NRC Licensing Exam SRO Written Exam Final Submittal
 
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:
Region:          I El ii El    III El iv El        Reactor Type: W    El CE El BW El GE El 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 hours to complete the combined examination, and 3 hours 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                                /        /        Points Applicants Scores                                                  /        /        Points Applicants Grade                                                    I        /        Percent
 
Name:                                                                          NRC Exam Form: 0 Version: 0
: 1. Given the following plant conditions:
                -Plant is at 100% RTP
                -RCS pressure is 2280 psig
                -PC-444J, PZR PRESSURE, is in Automatic at 65% ouput
                -PCV-455A, PZR SPRAY 444G, controller is in Automatic at 25% ouput
                -PCV-455C, PZR PORV, partially opens
                -The OAC takes action and manually closes PCV-455C
                -NO further operator actions have been taken
                -Current RCS pressure is 2150 psig Which ONE (1) of the following completes the statements below?
PCV-455A, PZR SPRAY 444G, controller output indication currently reads    (1)
PC-444J output indication currently reads    (2)
A. (1)25%
(2) 65%
B. (1)25%
(2) 0 C. (1)0 (2) 65%
D. (1)0 (2) 0 Thursday, June 13, 2013 4:26:18 PM
 
NRC Exam
: 2. Given the following plant conditions:
            -A EDG is OOS
            -Reactor power is at 100% RTP Subsequently:
            -A fault on 4Kv bus 2 leads to a reactor trip
            -Upon the reactor trip, a small break LOCA occurs
            -The crew is in EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT
            -CETCs read 547°F
            -Max. CV pressure reached was 3.4 psig
            -RCS Wide Range Pressure reads 1292 psig Which ONE (1) of the following completes the statements below?
The RCS subcooling is        (1)  . Based off the indications above, RCP trip criteria for EOP-E-1 Foldout is        (2)
A. (1) 29.6°F (2) NOT met B. (1) 31°F (2) met C. (1) 29.6°F (2) met D. (1) 31°F (2) NOT met Thursday, June 13, 2013 4:26:18 PM                                                                2
 
NRC Exam
: 3. Given the following plant conditions:
            -A Seismic Event coincident with a Large Break LOCA has occurred
            -CV pressure is currently 11 psig
            -B CV Spray Pump has tripped
            -All other ESF components operated properly
            -CV Sump level is 380 inches and rising
            -CV Radiation levels are <5 r/hr FRP-J.1, RESPONSE TO HIGH CONTAINMENT PRESSURE FRP-J.2, RESPONSE TO CONTAINMENT FLOODING Which ONE (1) of the following completes the statements below?
Based off the indications above, the crew meets entry conditions for    (1)    . One of the Major Action Categories of this procedure is      (2)
A. (1) FRP-J.1 (2) Verify Containment Isolation and Heat Removal B. (1) FRP-J.1 (2) Check for and Isolate Faulted Steam Generator C. (1) FRP-J.2 (2) Determine the radioactivity level of the sump fluid D. (1) FRP-J.2 (2) Try to Identify Unexpected Source of Sump Water and Isolate It if Possible Thursday, June 13, 2013 4:26:18 PM                                                            3
 
NRC Exam
: 4. Given the following plant conditions:
              -The following conditions are at time 12:30:00:
                  -The Reactor is at 100% RTP
                  -All control systems are in normal alignments
                  -Charging flow has been rising and is currently at 50 gpm
                  -Tl-140, REGEN HX LTDN OUTLET TEMP, is lowering
                  -VCT level is lowering
              -The following conditions are at time 12:45:00:
                  -RCS Pressure is 2235 psig
                  -Charging pump discharge pressure is 2100 psig Which ONE (1) of the following completes the statements below?
The leak is located        (1) of the Regenerative Heat Exchanger.
The crew takes action to close HIC-121, Charging Flow, lAW AOP-018, REACTOR COOLANT PUMP ABNORMAL CONDITIONS, Section C, LOSS OF SEAL INJECTION. The purpose of doing this is to (2)
A. (1) downstream (2) isolate the charging line leak B. (1) downstream (2) maintain minimum RCP Seal Injection Flow C. (1) upstream (2) isolate the charging line leak D. (1) upstream (2) maintain minimum RCP Seal Injection Flow Thursday, June 13, 2013 4:26:18 PM                                                  4
 
NRC Exam
: 5. Given the following plant conditions:
            -The plant is in mid loop operation to repair a SIG primary manway leak
            -RCS level is -68 inches and rising very slowly
            -RHR pump A is in service at 3500 gpm
            -The operator notices that RHR flow and pressure are oscillating Which ONE (1) of the following completes the statement below?
lAW AOP-020, LOSS OF RESIDUAL HEAT REMOVAL (SHUTDOWN COOLING), the crew will reduce RHR flow to            in an attempt to stabilize the RHR oscillations.
A. 3250 gpm B. 3000 gpm C. 2800 gpm D. 1500 gpm Thursday, June 13, 2013 4:26:18 PM                                                                5
 
NRC Exam
: 6. Given the following plant conditions:
            -The reactor is at 100% RTP
            -P1-444, CH I PRZR PRESS, reads 2310 psig and rising
            -P1-455, 456 and 457, PROT CH 1(11 and Ill) PRZR PRESS, all read approximately 2210 psig and lowering Which ONE (1) of the following completes the statements below?
To combat this, the OAC will take PC-444J to MANUAL and      (1)    its output to energize all PZR heaters.
After PC-444J is adjusted, P1-458, Calibration PZR Pressure, will indicate    (2)  psig for maximum proportional heater output.
A. (1) raise (2)-15 B. (1) raise (2) +15 C. (1) lower (2)-15 D. (1) lower (2) +15 Thursday, June 13, 2013 4:26:18 PM                                                            6
 
NRC Exam
: 7. Given the following plant conditions:
            -The crew attempted to trip the reactor and it failed to trip
            -They are initiating emergency boration of the RCS
            -The Boric Acid Pump aligned for blend failed to start Which ONE (1) of the following completes the statement below?
To initiate emergency boration, the crew will open (1)        . The emergency boration can be secured when PR Channels are <5%          (2)    a Negative IR Startup Rate.
A. (1) MOV-350 (2) or B. (1) MOV-350 (2) and C. (1) LCV-115B and close LCV-115C (2) and D. (1) LCV-115B and close LCV-115C (2) or Thursday, June 13, 2013 4:26:18 PM                                                            7
 
NRC Exam
: 8. Which ONE (1) of the following identifies the reason for securing the RCPs in EOP-E-3, STEAM GENERATOR TUBE RUPTURE?
A. Minimizes the impact upon core heat removal.
B. It insures against possible operator misdiagnosis.
C. Prevents excessive depletion of RCS water inventory.
D. Prevents the possiblity of RCP motor overspeed and catastrophic failure.
Thursday, June 13, 2013 4:26:18 PM                                                    8
 
NRC Exam
: 9. Given the following plant conditions:
            -The reactor is at 50% RTP
            -A small steam line leak has been reported
            -The CRS implements Attachment 10.4, CONTROL BAND AND TRIP LIMIT GUIDANCE, from OMM-022, EMERGENCY OPERATING PROCEDURES USERS GUIDE
            -APP-006-A2, S/G A STM>FW FLOW is in alarm lAW Attachment 10.4, at what NR S/G level is the crew required to manually trip the reactor?
A. 16%
B. 21%
C. 30%
D. 35%
Thursday, June 13, 2013 4:26:18 PM                                                          9
 
NRC Exam
: 10. Given the following plant conditions:
            -The reactor is at 100% RTP
            -A large Feedwater Line Break occurs at the piping connection to SIC A inside the Cv Which ONE (1) of the following completes the statements below?
Prior to the Reactor trip, RCS Tavg will  (1)    . The reactor will automatically trip on (2)
A. (1) rise (2) Low-Low S/G level B. (1) lower (2) Low-Low S/C level C. (1) rise (2) Low S/C Level with Steam Flow> Feed Flow D. (1) lower (2) Low S/G Level with Steam Flow> Feed Flow Thursday, June 13, 2013 4:26:18 PM                                                            10
 
NRC Exam
: 11. Given the following plant conditions:
            -The crew has just finished their immediate actions of EPP-1, LOSS OF ALL AC POWER
            -Narrow Range SIG levels are all 6%
            -Total FW Flow to the SIGs is 500 GPM Which ONE (1) of the following completes the statements below?
CSFSTs          (1)      being monitored for information only. A red path (2) exist on CSF-3, HEAT SINK.
A. (1) are NOT (2) does NOT B. (1)are (2) does NOT C. (1) are NOT (2) does D. (1)are (2) does Thursday, June 13, 2013 4:26:18 PM                                                          11
 
NRC Exam
: 12. Given the following plant conditions:
            -A Loss of off-site power occurs
            -Fifteen seconds later a Large Break LOCA occurs Which ONE (1) of the following completes the statements below?
The BOP will expect to see the SWBPs started on the (1)            . SWBP suction pressure (2)          have to be at least 30 psig for the SWBPs to start.
A. (1) Blackout sequencer (2) does B. (1) Blackout sequencer (2) does NOT C. (1) SI sequencer (2) does D. (1) SI sequencer (2) does NOT Thursday, June 13, 2013 4:26:18 PM                                                        12
 
NRC Exam
: 13. Given the following plant conditions:
            -The reactor is currently at 6% power with the turbine rolling at 1800 rpm lAW GP-005, POWER OPERATION
            -Power is lost to Instrument Bus (SB) #1 Which ONE (1) of the following completes the statements below?
The loss of lB #1      (1) cause a reactor trip. The turbine is  (2)
A. (1) will (2) tripped B. (1)will NOT (2) tripped C. (1) will (2) NOT tripped D. (1) will NOT (2) NOT tripped Thursday, June 13, 2013 4:26:18 PM                                                          13
 
NRC Exam
: 14. Given the following plant conditions:
            -Battery chargers A and B are in service
            -Battery chargers A-i and B-I are in standby
            -12:00 MCC-5 is de-energized
            -13:01 APP-036-D3, BATT A/B LO VOLT, alarm is illuminated
            -There are multiple indications of loss of control power to components Subsequently:
            -13:05:00 MCC-5 is re-energized Which ONE (1) of the following completes the statements below?
Battery charger(s) (1) will need to be manually restarted. As of 13:05:00 the following day, the batteries (2) be fully charged.
A. (I)A-1 only (2) will B. (1)A&A-1 (2) will C. (I)A&A-1 (2) will NOT D. (1)A-1 only (2) will NOT Thursday, June 13, 2013 4:26:18 PM                                                    14
 
NRC Exam
: 15. Given the following plant conditions:
            -The reactor is at 25% RTP
            -APP-009-F8, 4KV BUSES LO FREQ, is in alarm
            -The crew enters AOP-026, GRID INSTABILITY
            -Frequency is now at 58.3Hz Which ONE (1) of the following completes the statements below?
The crew will (1) trip the reactor. lAW AOP-026 basis document, the purpose of tripping the RCPs is to (2)
A. (1) immediately (2) prevent the automatic reactor trip from low flow B. (1) wait 5 minutes, and then (2) prevent the automatic reactor trip from low flow C. (1) immediately (2) prevent the automatic RCP trip at 58.2 Hz D. (1) wait 5 minutes, and then (2) prevent the automatic RCP trip at 58.2 Hz Thursday, June 13, 2013 4:26:18 PM                                                    15
 
NRC Exam
: 16. Given the following plant conditions:
            -The plant is in Mode 3
            -The crew has entered EPP-20, LOCA OUTSIDE CONTAINMENT SI-870 A & B, BIT INJ Valves RHR-744 A & B, RHR COLD LEG INJ Valves Which ONE (1) of the following completes the statement below?
In order to isolate a leak in the Cold Leg Injection piping, EPP-20 will have the crew shut (1) and monitior (2) to see if the leak is isolated.
A. (1)SI-870A&B (2) RCS pressure B. (1)Sl-870A&B (2) PZR level C. (1)RHR-744A&B (2) PZR level D. (1)RHR-744A&B (2) RCS pressure Thursday, June 13, 2013 4:26:18 PM                                                              16
 
NRC Exam
: 17. Which of the following is the FIRST mitigation strategy that FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, directs you to attempt?
A. Maximize charging flow to cool the RCS B. Depressurize the SIGs to raise subcooling C. Initiation of RCS Bleed and Feed Heat Removal D. Attempt Restoration of Feed Flow To Steam Generators Thursday, June 13, 2013 4:26:18 PM                                                    17
 
NRC Exam
: 18. Given the following plant conditions:
            -The crew has implemented EPP-15, Loss of Emergency Coolant Recirculation
            -The crew is initiating an RCS cooldown to cold shutdown
            -The following table is a plot of the RCS cooldown:
TIME          RCS TCOLD          TIME        RCS TCOLD 0800          547&deg;F            0945          425&deg;F 0815          530&deg;F            1000          395&deg;F 0830          520&deg;F            1015          382&deg;F 0845          505&deg;F            1030          364&deg;F 0900          498&deg;F            1045          340&deg;F 0915          478&deg;F            1100          320&deg;F 0930          447&deg;F            1115          300&deg;F Which ONE (1) of the following completes the statements below?
The cooldown rate limit      (1)    been exceeded. At  (2)    RWST level, the crew is required to secure all running ECCS pumps taking a suction from the RWST.
A. (1) has (2) 27%
B. (1)has (2)9%
C. (1) has NOT (2) 27%
D. (1) has NOT (2) 9%
Thursday, June 13, 2013 4:26:18 PM                                                        18
 
NRC Exam
: 19. Given the following plant conditions:
            -Reactor is at 100% RTP
            -A & B Charging pumps are OOS
            -HIC-121, CHARGING FLOW VALVE, controller indicates 100% output
            -CVC-297 A/B/C are full open
            -Seal Injection flow are all about 6.6 GPM CVC-297A, RCP A SEAL WATER FLOW CONTROL VALVE CVC-297 B, RCP B SEAL WATER FLOW CONTROL VALVE CVC-297 C, RCP C SEAL WATER FLOW CONTROL VALVE LT-459, CH I PRZR LEVEL LT-461, CH Ill PRZR LEVEL Which ONE (1) of the following completes the statements below?
Based off the conditions above, LT- (1)      has failed low. ITS LCO 3.4.17, Chemical and Volume Control System, requirements        (2)    met.
A. (1)461 (2) are NOT B. (1)459 (2) are NOT C. (1)461 (2) are D. (1)459 (2) are Thursday, June 13, 2013 4:26:18 PM                                                          19
 
NRC Exam
: 20. Given the following plant conditions:
            -The plant is in Mode 3 preparing for startup.
            -Several alarms are received and multiple controllers & indicators lose power.
            -Nl-32, Source Range Nuclear Instrument, is deenergized
            -The crew has entered AOP-024, LOSS OF INSTRUMENT BUS
            -An AO reports that an ILC student doing JPM walkdowns bumped into the supply breaker and the AO heard the breaker trip Which ONE (1) of the following completes the statement below?
In order to restore power to N 1-32, the crew will need to reset and close the supply breaker to Instrument Bus      (1)    at    (2)
A. (1)1 (2) InverterA B. (1)2 (2) InverterA C. (1)1 (2) MCC-5 D. (1)2 (2) MCC-5 Thursday, June 13, 2013 4:26:18 PM                                                            20
 
NRC Exam
: 21. Given the following plant conditions:
            -Power is above P-6
            -Power is below P-i 0
            -Power ascension is in progress
            -Nl-35, INTERMEDIATE RANGE NUCLEAR INSTRUMENT, fails as is
            -Nl-36, INTERMEDIATE RANGE NUCLEAR INSTRUMENT, fails as is Which ONE (1) of the following correctly completes the statement below?
The maximum time the crew has to      (1)    is    (2)    lAW LCO 3.3.1, REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION.
A. (1) suspend operations involving positive reactivity additions (2) 15 minutes B. (1) suspend operations involving positive reactivity additions (2) immediately C. (1) increase thermal power to >P-10 (2) 15 minutes D. (1) increase thermal power to >P-10 (2) immediately Thursday, June 13, 2013 4:26:18 PM                                                      21
 
NRC Exam
: 22. Given the following plant conditions:
            -High radiation alarms have just been received from R-20, FUEL HANDLING BUILDING LOWER LEVEL, and R-30, FUEL HANDLING BUILDING LOWER LEVEL HIGH RANGE
            -The Inside Auxiliary Operator reports the following:
                -WGDT A is at 40 psig and is in service
                -WGDT B is at 20 psig and is in standby
                -WGDT C is at 80 psig and is on cover gas
                -WGDT D is at 60 psig with pressure slowly lowering
            -AOP-009, ACCIDENTAL GAS RELEASE FROM A WGDT, has been entered
            -The crew has started HVE-5A, AUX BLDG CHARCOAL EXH FAN Which ONE (1) of the following completes the statements below?
The basis for starting HVE-5A lAW AOP-009 is to        (1)    . WGDT D will be placed on cover gas and equalized with WGDT          (2)
A. (1) minimize any radiological release (2) A B. (1) minimize any radiological release (2) B C. (1) limit the concentration of explosive gases (2) B D. (1) limit the concentration of explosive gases (2) A Thursday, June 13, 2013 4:26:18 PM                                                        22
 
NRC Exam
: 23. Given  the following plant conditions:
            -A fire breaks out on the RTGB
            -The crew has entered AOP-041, RESPONSE TO FIRE EVENT, and subsequently, DSP-OO1, ALTERNATE SHUTDOWN DIAGNOSTIC
            -The crew has tripped the reactor CVC-200 A/B/C, LTDN ORIFICE PCV-455C, PZR PORV PCV-456, PZR PORV Which ONE (1) of the following completes the statements below?
Prior to leaving the control room, the QAC will    (1) . This is performed to (2)
A. (1) Verify CVC-200 A/B/C closed (2) prevent spurious operation B. (1) Isolate PCV-456 & PCV-455C (2) prevent spurious operation C. (1) Verify CVC-200 A/B/C closed (2) allow for remote operation of these valves D. (1) Isolate PCV-456 & PCV-455C (2) allow for remote operation of these valves Thursday, June 13, 2013 4:26:19 PM                                                          23
 
NRC Exam
: 24. Given the following plant conditions:
            -A fire has broke out in the Hagan Room
            -It has spread to the Control Room
            -The crew is currently in DSP-002, HOT SHUTDOWN USING THE DEDICATED/ALTERNATE SHUTDOWN SYSTEM
            -Attachment 1, TURBINE BUILDING OPERATOR ACTIONS, are complete
            -The DS Bus is energized Which ONE (1) of the following completes the statements below?
One of the operators will start A CCW pump from  (1)  . MDAFW pumps (2) available.
A. (1) the Charging Pump room (2) are B. (1) the Charging Pump room (2) are NOT C. (1) the Rod Control room (2) are D. (1) the Rod Control room (2) are NOT Thursday, June 13, 2013 4:26:19 PM                                                24
 
NRC Exam
: 25. The reactor is at 100% RTP. Which of the following would indicate failed fuel?
A.
k      mRftr rL R-9 0
6                    LETDOWN LINE AREA B.
I I1 k        mRlhr ccl.
1*1.
R-2 0
CV AREA C.
499 K        CPM wI.                                            rAl.
R-11
* 6                  CV AIR && PLANT VENT PAR11CLJ LATE D.
ll              CPM I  IJ R-12 U
* V AIR && PLANT VENT RADIOACTIVE GAS 6
Thursday, June 13, 2013 5:12:17 PM                                                    25
 
NRC Exam
: 26. Given the following plant conditions:
              -A reactor trip has occurred
              -The turbine failed to trip
              -The MSIVs have failed to close
              -The crew is in FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK Which ONE (1) of the following completes the statements below?
lAW FRP-P.1, the crew will maintain (1)  . The crew will be required to perform a soak for (2) hour(s).
A. (1) between 80-90 gpm feed flow to each S/G (2) 1 B. (1) between 80-90 gpm feed flow to each S/G (2)29 C. (1) total feed flow> 300 gpm (2) 1 D. (1) total feed flow> 300 gpm (2) 29 Thursday, June 13, 2013 4:26:19 PM                                                          26
 
NRC Exam
: 27. Given the following plant conditions:
            -The crew has experienced a Loss of All A/C Power
            -They have transitioned to EPP-6, NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL Which ONE (1) of the following completes the statements below?
JAW EPP-6, the maximum RCS temperature at which RHR can be placed in service is LESS THAN            (1)  . Per EPP-6, the maximum cooldown rate is LESS THAN (2)    in the last 60 minutes.
A. (1) 350&deg;F (2) 100&deg;F B. (1) 250&deg;F (2) 100&deg;F C. (1) 350&deg;F (2) 25&deg;F D. (1) 250&deg;F (2) 25&deg;F Thursday, June 13, 2013 4:26:19 PM                                                    27
 
NRC Exam
: 28. Given the following plant conditions:
                -  The Plant is at 100% RTP
                -  APP-001-D2, RCP #1 SEAL LEAKOFF HI FLOW is in alarm
                -  RCP #1 Seal Leakoff Flows and Thermal Barrier D/Ps are as indicated (SEE REFERENCE ON NEXT PAGE)
Which ONE (1) of the following completes the statements below?
RCP A                    seal is failed. To prevent damage to the RCP A Seal Stack, the RCP A SEAL LEAKOFF Valve, CVC-303A should be closed                          after tripping RCPA.
A. (1)#1 (2) immediately B. (1)#2 (2) immediately C. (1)#1 (2) between 3 and 5 minutes D. (1)#2 (2) between 3 and 5 minutes Thursday, June 13, 2013 4:26:19 PM                                                              28
 
P1. 1 56A          I PI-155A PI-154A Thursday, June 13, 2013 5:15:08 PM            29
 
NRC Exam
: 29. Which ONE (1) of the following completes the statements below?
When Seal Injection is unavailable, CCW flow to the    (1)    ensures adequate cooling of the Reactor Coolant Pump seals. This cooling flow path remains in service until isolated by a Phase  (2)    actuation.
A. (1) Thermal Barrier (2) A B. (1) Thermal Barrier (2) B C. (1) Seal WaterHX (2) A D. (1) Seal Water HX (2) B Thursday, June 13, 2013 4:26:19 PM                                                        29
 
NRC Exam
: 30. Given the following plant conditions:
                -  The plant is operating at 100% RTP.
                -  Seal Injection flow to each RCP is 8.5 gpm
                -  C Charging Pump is currently running in Manual at minimum speed.
                -  A Charging Pump is running in MANUAL at 35% demand during the performance of OP-301-1, Section 8.4.7, Charging Pump Break-In After Maintenance.
                -  CVC-283C, Charging Pump A Discharge Relief, has lifted and has not reseated.
Which ONE (1) of the following identifies the impact on Seal Injection flow(s) AND how this malfunction would be addressed by AOP-018, Reactor Coolant Pump Abnormal Conditions?
Which ONE (1) of the following completes the statement below?
Seal Injection flows will lower to      (1)  and AOP-01 8 directs the operators to      (2)
A. (1) ZERO flow (2) Isolate letdown, secure all Charging Pumps, manually isolate A Charging pump.
B. (1) MINIMUMfI0w(--6gpmeach)
(2) Isolate letdown, secure all Charging Pumps, manually isolate A Charging pump.
C. (1) ZERO flow (2) Stop A Charging Pump and adjust the speed of C Charging Pump to restore normal seal injection flows.
D. (1) MINIMUM flow ( 6 gpm each)
(2) Stop A Charging Pump and adjust the speed of C Charging Pump to restore normal seal injection flows.
Thursday, June 13, 2013 4:26:19 PM                                                          30
 
NRC Exam
: 31. Given the following plant conditions:
            -The RCS is on RHR and SOLID
            -RCS pressure is 340 psig
            -PC-145, PRESSURE, in AUTO
            -HIC-142, PURIFICATION FLOW, controller seffing is at 55% demand Subsequently, an RCS leak occurs Which ONE (1) of the following completes the statement below?
PC-145 controller output      LI)    and PCV-145 throttles  (2)
A. (1) lowers (2) closed B. (1) lowers (2) open C. (1) rises (2) closed D. (1) rises (2) open Thursday, June 13, 2013 4:26:19 PM                                          31
 
NRC Exam
: 32. Given the following plant conditions:
                -  The plant is in Mode 5.
                -  The air supply line to HCV-758, RHR HX OUTLET FLOW TO COLD LEGS, breaks, causing a complete loss of Instrument Air to the valve.
Which ONE (1) of the following completes the statements below?
Based off the conditions above, total RHR flow initially    (1)    . lAW AOP-020, Loss of Residual Heat Removal (Shutdown Cooling), the crew will MANUALLY throttle A. (1) rises (2) FCV-605, RHR HX BYPASS closed B. (1) rises (2) RHR-764, HCV-758 BYPASS closed C. (1) lowers (2) FCV-605, RHR HX BYPASS open D. (1) lowers (2) RHR-764, HCV-758 BYPASS open Thursday, June 13, 2013 4:26:19 PM                                                          32
 
NRC Exam
: 33. Given the following plant conditions:
            -The reactor is at 100% RTP
            -A Safety Injection signal is received SI-870 A/B, BIT INJECTION TANK OUTLETS RHR-744 A/B, LOOP DISCHARGE TO RCS ISOLATION VALVES SI-865 A/B/C, SI ACCUMULATOR DISCHARGE VALVES S1-867 NB, BIT INJECTION TANK INLETS Which of the following valves will reposition because of the Safety Injection signal?
A. 5 1-870 NB & RHR-744 A/B B. 5 1-865 NB/C & S 1-867 A/B C. S1-870 NB & Sl-865 A/B/C D. RHR-744 A/B & Sl-867 NB Thursday, June 13, 2013 4:26:19 PM                                                            33
 
NRC Exam
: 34. Given the following plant conditions:
            -The reactor was at 100% RTP when a LOCA occurs
            -A Safety Injection has been initiated and is injecting into the core Immediately upon the Safety Injection Flow going to the core, the INNER WALL of the SI piping that connects to the RCS undergoes        (1)    stress. If one of the SI pipes that connects to the RCS breaks from this stress,        (2)    pipe(s) would still be available to supply SI flow to the core.
A. (1) tensile (2) one B. (I) tensile (2) two C. (1) compressive (2) one D. (1) compressive (2) two Thursday, June 13, 2013 4:26:19 PM                                                                34
 
NRC Exam
: 35. Given the following plant conditions:
                - A bubble is being drawn in the Pressurizer lAW, OP-I 04, Pressurizer Operations
                -  RCS pressure is 335 psig
                -  Tl-454, PRZR VAPOR TEMP is 432&deg;F
                -  LI-462, COLD PRESSURIZER, Level is 80% and slowly lowering
                -  Tl-463, PZR PWR RELIEF LINE TEMP, reads 320&deg;F A PZR PORV              (I)  leaking. Confirmatory indications would be pressure, level, or temperature.
A. (1) is (2) PRT B. (I) is (2) RCDT C. (1) is NOT (2) PRT D. (I) is NOT (2) RCDT Thursday, June 13, 2013 4:26:19 PM                                                      35
 
NRC Exam
: 36. Given the following plant conditions:
                - The reactor is at 100% RTP
                - CCW Heat Exchanger outlet temperature is 106&deg;F and rising
                - All Service Water Pumps are running
                - The highest RCP Motor bearing temperature is 190&deg;F and rising
                - Service Water pressure is 46 psig and stable on both headers AOP-018, REACTOR COOLANT PUMP ABNORMAL CONDITIONS AOP-014, COMPONENT COOLING WATER SYSTEM MALFUNCTION Which ONE (1) of the following completes the statements below?
Based off the conditions above, the      (1)    . The crew is required to (2)
A. (1) RCP operating limits have been exceeded (2) monitor all RCP parameters lAW AOP-01 8.
B. (1) RCP operating limits have been exceeded (2) Lower heat load on CCW system lAW AOP-014.
C. (1) CCW system cooling capacity is degraded (2) lower heat load on CCW system lAW AOP-014 D. (1) CCW system cooling capacity is degraded (2) monitor all RCP parameters lAW AOP-018.
Thursday, June 13, 2013 4:26:19 PM                                                    36
 
NRC Exam
: 37. Given the following plant conditions:
            -RCS Tavg is 560&deg;F
            -LT-459, PRZR LEVEL, has failed high Which ONE (1) of the following completes the statements below?
Prior to the failure, pressurizer level was  (1) . Pressurizer heaters will all turn on when LT-459 reaches          (2)
A. (1) 36.1%
(2) 46.1%
B. (1) 53.3%
(2) 63.3%
C. (1) 53.3%
(2) 58.3%
D. (1) 36.1%
(2) 41.1%
Thursday, June 13, 2013 4:26:19 PM                                                            37
 
NRC Exam
: 38. Given the following plant conditions:
            -The reactor is at 37% RTP
            -RCP breaker A trips Which ONE (1) of the following completes the statement?
Reactor Trip Breakers RTA and RTB          (1) lights will be illuminated. The conditions for P-8        (2) satisfied.
A. (1) red (2) are B. (1) green (2) are C. (1) red (2) are NOT D. (1) green (2) are NOT Thursday, June 13, 2013 4:26:19 PM                                                    38
 
NRC Exam
: 39. Given the following conditions:
                -  Plant is at 100% RTP
                -  All equipment is in normal alignment
                -  An electrical fault results in a loss of power to Instrument Bus 3 Which ONE (1) of the following describes SI Pump response if an AUTO SI actuation occurs before Instrument Bus 3 is recovered?
A. SI Pumps A and B start.
B. SI Pumps B and C start.
C. Only SI Pump A starts.
D. Only SI Pump C starts.
Thursday, June 13, 2013 4:26:19 PM                                                      39
 
NRC Exam
: 40. Given the following plant conditions:
            -Tavg is 547&deg; F
            -RCS Pressure is 2235 psig
            -A loss of offsite power occurs
            -One minute later a large break LOCA occurs Which ONE (1) of the following completes the statement below?
The FINAL CV Recirculation fans start    (1)    seconds after both trains of the f        sequencers start.
A. (1) 30 (2) Blackout B. (1) 35 (2) Blackout C. (1) 30 (2) Safety Injection D. (1) 35 (2) Safety Injection Thursday, June 13, 2013 4:26:19 PM                                                        40
 
NRC Exam
: 41. Which ONE (1) of the following combinations of Containment Heat removal equipment will require immediate entry into LCO 3.0.3?
A. Both HVH trains inoperable.
B. Three Containment HVH units inoperable.
C. Two Containment Spray Pumps inoperable.
D. One Containment Spray Pump and one HVH train inoperable.
Thursday, June 13, 2013 4:26:19 PM                                                    41
 
NRC Exam
: 42. Given the following plant conditions:
            -A loss of offsite power and a reactor trip has occurred
            -Two minutes later APP-007-F5, SD AFW PMP LO DISCH PRESS TRIP alarms and remains locked in
            -The pump has been verified to be coasting down locally due to an overspeed trip Which ONE (1) of the following correctly completes the statements below?
SDAFW Pump Steam Shutoff Valves, V1-8A, V1-8B, and V1-8C should be            (1)    at this time. The BOP operator is required to      (2)    closure of SDAFW Pump Discharge Valves, V2-14A, V2-14B, and V2-14C.
A. (1) open (2) verify automatic B. (1) open (2) perform manual C. (1) closed (2) verify automatic D. (1) closed (2) perform manual Thursday, June 13, 2013 4:26:19 PM                                                          42
 
NRC Exam
: 43. Given the following plant conditions:
            -The Plant is at 50% RTP perform post outage power ascension.
            -FCV-478, FRV A, develops an air leak at the valve operator and the valve starts to slowly drift in the close direction
            -The air leak increases slowly for 5 minutes and then the air line completely separates EOP-E-0, REACTOR TRIP OR SAFETY INJECTION AOP-010, MAIN FEEDWATER/CONDENSATE MALFUNCTION Which ONE (1) of the following completes the statements below?
Prior to the line separation, FCV-478 controller output will  (1)    . After the line separates the crew will          (2)  lAW AOP-01 0.
A. (1) rise (2) stabilize A S/G Level using the FRV Bypass Valve B. (1) lower (2) stabilize A S/G Level using the FRV Bypass Valve C. (1) rise (2) trip the Reactor and Go To EOP-E-0 D. (1) lower (2) trip the Reactor and Go To EOP-E-0 Thursday, June 13, 2013 4:26:19 PM                                                            43
 
NRC Exam
: 44. Given the following plant conditions:
            -The plant is in Mode 3
            -The SDAFW Pump is under clearance
            -MDAFW Pump B is running Subsequently,
            -A line break occurs between FCV-1425, MDAFW PUMP B FCV and V2-20B, AFW HDR SECTION valve
            -MDAFW Pump B trips on overcurrent due to runout through line break
            -The break has been isolated using single valve isolation Which ONE (1) of the following identifies the S/Gs available to be fed by the remaining AFW Pump?
A. S/GAONLY B. S/GBONLY C. S/GsA, B, andC D. S/GsAandBONLY Thursday, June 13, 2013 4:26:19 PM                                                          44
 
NRC Exam
: 45. Given the following plant conditions:
            -The Plant is at 100% RTP
            -A fault has isolated the Startup Transformer Which ONE (1) of the following completes the statements below?
This results in a loss of    (1)    . Emergency Diesel Generator (2) starts and loads.
A. (1) Spent Fuel Pit Cooling Pump A and Rod Drive MG Set B (2)A B. (1) Spent Fuel Pit Cooling Pump A and Rod Drive MG Set B (2) B C. (1) Spent Fuel Pit Cooling Pump B and PZR Heater Back-up Group A (2)A D. (1) Spent Fuel Pit Cooling Pump B and PZR Heater Back-up Group A (2) B Thursday, June 13, 2013 4:26:19 PM                                                      45
 
NRC Exam
: 46. Given the following plant conditions:
            -A LOCA and a Loss of Offsite Power have occurred
            -Both battery chargers that were in service are tripped Which ONE (1) of the following completes the statements below?
Given the accident above, A and B Batteries are designed to last for a MAXIMUM of (1)    . Assuming battery load remains constant, battery current will (2)      as terminal voltage lowers.
A. (1) 1 hour (2) lower B. (1) 1 hour (2) rise C. (1) 30 minutes (2) lower D. (1) 30 minutes (2) rise Thursday, June 13, 2013 4:26:19 PM                                                        46
 
NRC Exam
: 47. Which ONE (1) of the following completes the statements below?
The purpose of the Emergency Diesels is to provide emergency power in the event of a loss of (1)      . The design time to energize the associated bus is within (2) seconds.
A. (1) offsite power (2) 10 B. (1) offsite power (2) 15 C. (1) allA/C power (2) 10 D. (1)allA/Cpower (2) 15 Thursday, June 13, 2013 4:26:19 PM                                                        47
 
NRC Exam
: 48. De-energizing which ONE (1) of the following Motor Control Centers will cause a loss of Diesel Air Compressor A?
A. MCC-5 B. MCC-6 C. MCC-9 D. MCC-1O Thursday, June 13, 2013 4:26:19 PM                                                        48
 
NRC Exam
: 49. Given the following plant conditions:
            -The reactor is at 100% RTP
            -The crew is performing a containment vacuum relief
            -R-12, CV AIR OR PLANT STACK, NOBLE GAS, alarms V12-12, CVVAC RELIEF V12-13, CVVAC RELIEF APP-036-D7, AREA MONITOR HI RAD APP-036-D8, PROCESS MONITOR HI RAD Which ONE(1) of the following completes the statements below?
The crew would expect to see      (1)  annunciator flashing. They would also see (2)      go shut.
A. (1) APP-036-D7 (2) VI 2-12 & VI 2-13 only B. (1) APP-036-D8 (2)V12-12 & V12-13 only C. (1) APP-036-D7 (2) V12-12, V12-13 & the CV Intake Damper D. (1) APP-036-D8 (2) V12-12, V12-13 & the CV Intake Damper Thursday, June 13, 2013 4:26:19 PM                                                        49
 
NRC Exam
: 50. Given the following plant conditions:
            -The reactor is at 100% RTP
            -The following radiation monitor alarms are received:
                  -R-15, CONDENSER AIR EJECTOR GAS MONITOR
                  -R-19A, S/G A RADIATION MONITOR
                  -R-24A, S/G A LEAKAGE MONITOR
            -All other radiation monitors are normal Which ONE (1) of the following describes the valves that CLOSE in response to these indications?
A. FCV-1930A, S/G A Blowdown Isolation Valve V1-31, Blowdown Isolation Valve to Catch Basin B. V1-31, Blowdown Isolation Valve to Catch Basin RCV-1 0549, Condensate Polisher Discharge to Catch Basin C. FCV-1930A, S/G A Blowdown Isolation Valve FCV-1933B, SIG A Blowdown Sample Isolation Valve D. FCV-1933B, S/G A Blowdown Sample Isolation Valve RCV-1 0549, Condensate Polisher Discharge to Catch Basin Thursday, June 13, 2013 4:26:19 PM                                                        50
 
NRC Exam
: 51. Given the following plant conditions:
            -The reactor is at 100% RTP
            -Service Water pumps A & C are running
            -Service Water Header pressure is 42 psig and stable as indicated on P1-1616 and P1-1684
            -Both CCW Heat Exchangers are in service
            -Main Generator Exciter Cooler air discharge temperature is 145&deg; F and rising slowly TCV-1673, TURBINE LUBE OIL TEMP CONTROL VALVE TCV-1 650, HYDROGEN COOLER TEMP CONTRL VALVE Which ONE (1) of the following completes the statements below?
lAW OP-903, Service Water System, the maximum allowable Main Generator Exciter Cooler air discharge temperature is      LU &deg;F. To restore Main Generator Exciter Cooler air discharge temperature the crew will first A. (1) 140 (2) start D Service Water pump B. (1) 188 (2) start D Service Water pump C. (1) 140 (2) raise the setpoint for TCV-1673 and TCV-1650 D. (1) 188 (2) raise the setpoint for TCV-1 673 and TCV-1 650 Thursday, June 13, 2013 4:26:19 PM                                                          51
 
NRC Exam
: 52. Given the following plant conditions:
            -MCC-5 de-energizes due to the supply breaker tripping open
            -During the transient, a turbine trip occurs and the South Service Water header pressure decreases to 28 psig V6-16B, SW SOUTH HEADER SUPPLY TO TURBINE BUILDING V6-16C, SW ISOLATION TO TURBINE BUILDING Which ONE (1) of the following completes the statement below?
TWO (2) minutes after the turbine trip, V6-16B is      (1)  and V6-16C is    (2)
A. (1) closed (2) closed B. (1) closed (2) open C. (1) open (2) open D. (1) open (2) closed Thursday, June 13, 2013 4:26:19 PM                                                          52
 
NRC Exam
: 53. Given the following plant conditions:
            -APP-002-F7, INSTR AIR HDR LO PRESS alarms
            -P1-I 702, INST AIR HEADER PRESS, dropped from 100 psig to 0 psig in less than 10 seconds
            -Pressurizer Level is 54% and STABLE
            -Steam Generator Narrow Range Levels are 52% and STABLE
            -The reactor is at 100% RTP and STABLE AOP-017, LOSS OF INSTRUMENT AIR EOP-E-0, REACTOR TRIP OR SAFETY INJECTION Which ONE (1) of the following completes the statements below?
APP-002-F7 alarm setpoint is          (1)    psig. The crew is required to    (2)
A. (1) 60 (2) initiate action to repair the transmitter and monitor Instrument Air pressure locally B. (1) 85 (2) initiate action to repair the transmitter and monitor Instrument Air pressure locally C. (1) 60 (2) trip the reactor and implement AOP-017 and EOP-E-0 concurrently D. (1) 85 (2) trip the reactor and implement AOP-01 7 and EOP-E-0 concurrently Thursday, June 13, 2013 4:26:19 PM                                                            53
 
NRC Exam
: 54. Which ONE (1) of the following completes the statements below?
Instrument Air Compressor A and B cylinder water jackets are cooled by (1)
Water. Flow is            to the cylinder water jackets when the air compressors are shutdown.
A. (1) Service (2) maintained B. (1) Component Cooling (2) maintained C. (1) Service (2) isolated D. (1) Component Cooling (2) isolated Thursday, June 13, 2013 4:26:19 PM                                                          54
 
NRC Exam
: 55. Which ONE (1) of the following completes the statements below?
To ensure the LCO is met for the Personnel Airlock as required by Technical Specification 3.6.2 in MODES        (1)  the personnel hatch doors are  (2) to ensure only one door is open at any time.
A. (1) 1-4 only (2) administratively controlled B. (1) 1-4,and6 (2) administratively controlled C. (1) 1-4 only (2) physically interlocked D. (1) 1-4,and6 (2) physically interlocked Thursday, June 13, 2013 4:26:19 PM                                                      55
 
NRC Exam
: 56. Given the following plant conditions:
            -The reactor was at 100% RTP.
            -Subsequently, the reactor was tripped due to a Steam Line leak on the 72 inch Main Steam Header
            -All MSIV5 are stuck full open.
            -All AFW Pumps failed to start
            -FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, has been entered
            -S/G Wide Range levels are all at 3%
            -CETC Temperature indicates 505&deg;F with a subcooling of 115&deg;F
            -Safety Injection has been manually initiated Which ONE (1) of the following completes the statement below?
Safety injection        (1) injecting into the core. In order to initiate Bleed and Feed, the crew will FIRST try to open        (2)
A. (1)is (2) all head vents B. (1)isNOT (2) all head vents C. (1)is (2) both PZR PORVs D. (1) is NOT (2) both PZR PORVs Thursday, June 13, 2013 4:26:19 PM                                                                56
 
NRC Exam
: 57. Given the following plant conditions:
            -The crew is lowering power from 100% to 90% RTP lAW OP-105, MANEUVERING THE PLANT WHEN GREATER THAN 25% POWER
            -All PZR heaters are energized
            -B Charging pump is in manual
            -C Charging pump is in AUTO
            -LT-460, CH II PRZR LEVEL, fails low Which ONE (1) of the following completes the statements below?
The PZR Backup heaters are        (1)  . Because of this failure, C charging pump speed will        (2)
A. (1)off (2) lower B. (1)on (2) lower C. (1)off (2) rise D. (1)on (2) rise Thursday, June 13, 2013 4:26:19 PM                                                        57
 
NRC Exam
: 58. Given the following plant conditions:
            -The reactor is at 100% RTP
            -The crew has entered AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM, for a dropped rod in Control Bank D
            -They are at the step to place the Lift Coil Disconnect Switch for the dropped rod to the OFF position Which ONE (1) of the following completes the statements below?
The operator performing this step will go to the      (1)  . This is done to allow operators to        (2)
A. (1) Rod Control Room (2) withdraw the dropped rod B. (1) back of the RTGB (2) withdraw the dropped rod C. (1) Rod Control Room (2) control flux during the downpower D. (1) back of the RTGB (2) control flux during the downpower Thursday, June 13, 2013 4:26:19 PM                                                            58
 
NRC Exam
: 59. Given the following plant conditions:
            -The crew is in FRP-C.1, RESPONSE TO INADEQUATE CORE COOLING Which ONE (1) of the following completes the statements below?
From the ICCM Panel, the crew will monitor  (1)  lAW FRP-C.1. The minimum temperature at which core damage has occurred with RCPs running is  (2)
A. (1)RTDs (2) 1200&deg;F B. (1)RTDs (2) 2300&deg;F C. (1)CETCs (2) 1200&deg;F D. (1)CETCs (2) 2300&deg;F Thursday, June 13, 2013 4:26:19 PM                                                  59
 
NRC Exam
: 60. Which ONE (1) of the following is the power supply for HVE-4, CV AIR IODINE REMOVAL EXHAUST FAN?
A. MCC-5 B. MCC-6 C. MCC.-9 D. MCC-10 Thursday, June 13, 2013 4:26:19 PM                                                60
 
NRC Exam
: 61. Given the following plant conditions:
            -One AO is in containment verifying a valves position
            -R-1 1, CV AIR & Plant Vent Particulate, alarms
            -The crew has entered AOP-005, RADIATION MONITORING SYSTEM Which ONE (1) of the following completes the statement below?
The OAC will place the VLC switch to the      (1)  position and will then Hold the CV EVACUATION HORN for          (2)    seconds lAW AOP-005.
A. (1) OVERRIDE (2) 5 B. (1) OVERRIDE (2) 15 C. (1)EMERG (2) 5 D. (1)EMERG (2) 15 Thursday, June 13, 2013 4:26:19 PM                                                            61
 
NRC Exam
: 62. Given the following plant conditions:
            -The reactor is at 100% RTP
            -APP-036-B6, SPENT FUEL PIT LO LEVEL, alarm comes in
            -AO reports that APP-036-B6 is a valid alarm Which ONE (1) of the following completes the statements below?
APP-036-B6 alarm setpoint is      (1)  . The crew will fill the Spent Fuel Pit level using waterfrom the          (2)
A. (1)35ft (2) RWST B. (1) 36ft, 2.5 inches (2) RWST C. (1) 35ft (2) Demineralized Water System D. (1) 36ft, 2.5 inches (2) Demineralized Water System Thursday, June 13, 2013 4:26:19 PM                                                              62
 
NRC Exam
: 63. Given the following plant conditions:
              -The reactor is at 100% RTP
              -The CAD reports a steam leak near the Main Steam Isolation Valves
              -The following indications are noted in the Control Room:
Tavg is lowering
                  -Steam flow and feed flow have risen
                  -Power Limit Warning alarm on ERFIS has been received
                  -Reactor power is 100.3% and slowly rising Which ONE (1) of the following completes the statements below?
The time in core life that will result in the smallest reactivity excursion is  (1)    . The Reactor is required to be operated at less than or equal to        (2)    MW thermal lAW OMM-001-2, SHIFT ROUTINES AND OPERATING PRACTICES.
A. (1)BOL (2) 2300 B. (1)BOL (2) 2339 C. (1) EOL (2) 2300 D. (1)EOL (2) 2339 Thursday, June 13, 2013 4:26:19 PM                                                              63
 
NRC Exam
: 64. Given the following plant conditions:
            -The plant is performing a power ascension and is at 8% RTP Which ONE (1) of the following completes the statements below?
The REACTOR TRIP BLOCK P-7 status light will4Wiiate when          (1)  Power Range Nis read above 10%. One of the Reacto(Trips that this enables is  (2)
A. (1) 2/4                                                      /2.3 (2) PZR High Level B. (1)3/4 (2) PZR High Level C. (1)2/4 (2) PZR High Pressure D. (1)3/4 (2) PZR High Pressure Thursday, June 13, 2013 4:26:19 PM                                                    64
 
NRC Exam
: 65. Which of the following discharge to the Reactor Coolant Drain Tank?
A. Charging pump seals B. RCV-609, CC SURGE TANK VENT C. CVC-203 A/B, LETDOWN RELIEF VALVES D. CVC389, EXCESS LETDOWN DIVERSION Thursday, June 13, 2013 4:26:19 PM                                        65
 
NRC Exam
: 66. Which ONE (1) of the following completes the statements below?
lAW OPS-NGGC-1 000, FLEET CONDUCT OF OPERATIONS, a plant announcement will be made for the starting of    (1)  motors. The announcement will include (2)
A. (1)all (2) only the applicable motor B. (1) only large (2) only the applicable motor C. (1)all (2) the applicable motor and its switchgear D. (1) only large (2) the applicable motor and its switchgear Thursday, June 13, 2013 4:26:19 PM                                                      66
 
NRC Exam
: 67. Given the following plant conditions:
            -The plant is in MODE 6 for refueling operations
            -Core alterations are in progress Which ONE (1) of the following completes the statements below?
lAW LCO 3.9.2, NUCLEAR INSTRUMENTATION,              (1)  source range neutron flux monitor(s) shall be OPERABLE. NI-51 and NI-52,      (2)  capable of providing audible indication inside CV.
A. (1)one (2) are B. (1)two (2) are C. (1)one (2) are NOT D. (1)two (2) are NOT Thursday, June 13, 2013 4:26:19 PM                                                        67
 
NRC Exam
: 68. Which ONE (1) of the following completes the statements below?
SI Accumulator Pressure is checked during          (1)  . A deviation of greater than (2)      of full scale during a channel check is used as the OOS limit.
A. (1) OST-020, SHIFTLY SURVEILLANCES (2) 7.5%
B. (1) OST-020, SHIFTLY SURVEILLANCES (2)5%
C. (1) OST-021, DAILY SURVEILLANCES (2)5%
D. (1) OST-021, DAILY SURVEILLANCES (2) 7.5%
Thursday, June 13, 2013 4:26:19 PM                                                              68
 
NRC Exam
: 69. Which ONE (1) of the following people can be selected to be an Infrequently Performed Test or Evolution (IPTE) Manager lAW OPS-NGGC-1315, CONDUCT OF INFREQUENTLY PERFORMED TESTS OR EVOLUTIONS?
A. Lead Test Performer B. A Control Room Supervisor C. The on-duty Shift Manager D. The Manager, Shift Operations Thursday, June 13, 2013 4:26:19 PM                                                69
 
NRC Exam
: 70. Inside  Work    Control, the following conditions were found:
            -Removable surface contamination is 1500 dpm/cm 2
            -Radiation levels are 3 mrem/hr at 30cm Which ONE (1) of the following identifies the minimum postings for the Work Control area?
A. Radiation area only B. Contamination area only C. no postings necessary D. A contamination and radiation area Thursday, June 13, 2013 4:26:19 PM                                                          70
 
NRC Exam
: 71. Which ONE (1) of the following radiation monitors is located in the Auxiliary Building hallway above the Station Air receiver?
A. R-18 (Waste Disposal System liquid effluent)
B. R17 (Component Cooling Water)
C. R-16 (Containment Fan Coolers)
D. R-9 ( Letdown line area)
Thursday, June 13, 2013 4:26:19 PM                                                            71
 
NRC Exam
: 72. Given the following conditions:
            -An RNP Mechanic, previously employed by VC Summer, has been assigned to repack a valve
            -The mechanics current yearly dose from VC Summer was 1 Rem TEDE
            -The mechanic has received no dose from RNP
            -Projected dose rate in the area is 500 mR/hr What is the MAXIMUM time that the mechanic can work on the valve before reaching the Annual Administrative Dose Limit lAW DOS-NGGC-0004, ADMINISTRATIVE DOSE LIMITS?
A. 1 hour B. 2 hours C. 4 hours D. 8 hours Thursday, June 13, 2013 4:26:20 PM                                                    72
 
NRC Exam
: 73. The RD has determined that for the safety of the reactor and the plant, a reactor trip and initiation of Safety lnjection(SI) is necessary. He has announced it to the CRS, however, it has been several seconds and the CRS has not responded.
Which ONE (1) of the following completes the statement below?
The RD should            (1) then      (2)  lAW OPS-NGGC-1 000, FLEET CONDUCT OF OPERATIONS.
A. (1) wait for confirmation from the CRS (2) trip the reactor and initiate SI B. (1) wait for confirmation from the CRS (2) initiate SI C. (1) trip the reactor, verify it is tripped (2) initiate SI D. (1) trip the reactor and initiate SI (2) perform immediate action steps Thursday, June 13, 2013 4:26:20 PM                                                            73
 
NRC Exam
: 74. Given the following plant conditions:
            -A SMALL fire is reported near the A and B Auxiliary boilers Which ONE (1) of the following completes the statement below?
lAW OMM-003, FIRE PROTECTION PRE-PLANS/UNIT NO. 2, the fire brigade must attack this fire with      (1) and the fire brigade is required to protect the (2)
A. (1) a portable fire extinguisher or hose stream (2) Primary Air Compressor B. (1) a portable fire extinguisher or hose stream (2) Steam Driven AFW pump C. (1) hose stream only (2) Primary Air Compressor D. (1) hose stream only (2) Steam Driven AFW pump Thursday, June 13, 2013 4:26:20 PM                                                        74
 
NRC Exam
: 75. The Plant is at 100% RTP when the following events occur:
2115    - Power is lost to all Control Room annunciators 2120 An Unusual Event is declared
                        -
2125 The Emergency Notification form is complete and the SM directs you to
                        -
make the state and county notifications 2130 -A reactor trip occurs and the SM declares an Alert 2135 The SM completes a new Emergency Notification form and directs you to
                        -
make the state and county notifications Which ONE (1) of the following indicates the latest time the state and counties must FIRST be notified?
A. 2130 B. 2135 C. 2140 D. 2145 Thursday, June 13, 2013 4:26:20 PM                                                          75
 
NRC Exam
: 76. Given the following plant conditions:
            -Plant is at 100% RTP
            -PCV-455C, PZR PORV, indicates open
            -PT-444, CH I PRZR PRESS, is 2100 psig and lowering
            -PT-445, CH II PRZR PRESS, is 2100 psig and lowering
            -The OAC manually shuts PCV-455C
            -I&C determines that the PCV-455C cant be controlled automatically AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL AOP-025, RTGB INSTRUMENT FAILURE Which ONE (1) of the following completes the statements below?
The crew has entered      (1)  . lAW ITS, PCV-455C      (2)  OPERABLE.
A. (1)AOP-019 (2) is NOT B. (1) AOP-025 (2) is NOT C. (1)AOP-019 (2) is D. (1)AOP-025 (2) is Thursday, June 13, 2013 3:33:37 PM                                              77
 
NRC Exam
: 77. Given the following plant conditions:
            -The plant is at 98% RTP
            - AOP-O1 0 is entered due a leak in FW Heater 4B
            -OPS Manager has chosen to repair the leak on line AOP-O1O, MAIN FEEDWATER/CONDENSATE MALFUNCTION OP-407, HEATER DRAINS AND VENTS Which ONE (1) of the following completes the statements below?
The CRS will direct the OAO to use      (1) for the specific steps to remove the required FW Heaters from service. The crew      (2)    have to reduce power for this evolution.
A. (1) OP-407 (2) will NOT B. (1)AOP-010 (2) will NOT C. (1)OP-407 (2) will D. (1)AOP-010 (2) will Thursday, June 13, 2013 3:33:37 PM                                                          78
 
NRC Exam
: 78. Given the following plant conditions:
            -A Station Blackout has occurred from 100% RTP
            -The crew is performing actions of EPP-1, LOSS OF ALL AC POWER
            -Immediate actions are complete
            -A Charging pump is running
            -Offsite power is available to re-energize the SUT
            -APP-009-B5, MAIN TRANSF PHASE TRIP, alarm is in OP-603, ELECTRICAL DISTRIBUTION OP-603-3, RESETTING HIGH IMPEDANCE FAULT TRIPS 86P, GENERATOR LOCKOUT RELAY, PRIMARY 86BU, GENERATOR LOCKOUT RELAY, BACKUP Which ONE (1) of the following completes the statement below?
lAW EPP-1, the CRS will direct the use of OP- (1)        to restore power. APP-009-B5 is an indication that the    (2)    lockout needs to be reset.
A. (1)603 (2) 86P B. (1) 603-3 (2) 86P C. (1)603 (2) 86 BU D. (1) 603-3 (2) 86 BU Thursday, June 13, 2013 3:33:37 PM                                                          79
 
NRC Exam
: 79. Given the following plant conditions:
            -The reactor is at 100% RTP
            -B Charging pump is running in Manual
            -C Charging pump is running in AUTO
            -A reactor trip occurs
            -The following indications are seen:
                -See next page for references Which ONE (1) of the following completes the statements below?
Based off the indications above, C Charging pump is  (1)  . The crew will transition from EOP-E-0 to (2) to EPP-27.
A. (1) running (2) EOP-ES-0.1 B. (1)tripped (2) EOP-ES-0.1 C. (1) running (2) EPP-7 D. (1) tripped (2) EPP-7 Thursday, June 13, 2013 3:33:37 PM                                                  80
 
NRC Exam CHARGING PUMP C i:
SELECT    I JIlL  fri    hR TURII-Oll CODE      OP                                      hAY 09.2013        ON-LINE
 
hI: 55: 19 TEMP Ti          HOuRS  J  21 DAYS TREJiD DTSPLHY DC            (fiN/flAX)
 
NH F          I                    I t:a4      gI        i:e,        t:27                    I iio                      i:
POIIIT to DESCRIPTIOII                                      TREIIO      CLIRREIIT              LOU      HI6H LIFIE        VALUE    QIJAL    ALARI1    ALARI1 APU3O22H OC 11CC 1 VOLT 132.10        132.10    OK      123.00  1O.00 1
flPU3O 1    fl  2 BC    occ-n    CURREFIT                              -8.8          -6.      OK          0.0  1000.0 0P03(F)3fl BC 11CC- B VOLT nan          nan  ROER        123. 00  1)iJ. 00 DER          0.0        .0 F1.FAST LEFT          F2LEFT          F3-MEIILJ        FA1TE1IPLATE C.. CAHO                                                                cREoHT              F6..FHST RIOHT COIISOLE.IIORI1AL    P At flOUEt C
Thursday, June 13, 2013 5:15:24 PM                                                                                  81
 
NRC Exam
: 80. Given the following plant conditions:
            -Plant is at 40% RTP
            -The Load Dispatcher reports that grid voltage is degrading
            -12:00:00 on 1/1/13, 480V Bus E2 voltage was reduced to 400V
            -12:00:20 on 1/1/13, there were no changes to the electrical lineup
            -1 2:30:00 on 1/1/1 3, grid voltage was restored Which ONE (1) of the following completes the statements below?
The B EDG is designed to start under this condition when      (1)    degraded voltage relays sense their setpoint. If B EDG cannot be restored to service, the latest time the plant can be in MODE 3 is        (2)  lAW applicable LCO.
(REFERENCE PROVIDED)
A. (1) 1/2 (2) 18:00:20 on 1/7/13 B. (1) 1/2 (2) 18:00:20 on 1/8/13 C. (1)2/3 (2) 18:00:20 on 1/7/13 D. (1)2/3 (2) 18:00:20 on 1/8/13 Thursday, June 13, 2013 3:33:37 PM                                                              82
 
NRC Exam
: 81. Given the following plant conditions:
            -The crew is implementing FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK
            -CST is intact, level is 15% and lowering OP-402, AUXILIARY FEEDWATER SYSTEM FRP-H.1, ATTACHMENT 2, SERVICE WATER BACKUP TO MDAFW PUMPS Which ONE (1) of the following completes the statements below?
The correct order in which the crew will attempt to restore Feed Flow to S/Gs is AFW, (1)    . If the CST level reaches 10%, the CRS will direct the use of  (2)    to align Service Water as a backup to the AFW pumps.
A. (1) Main Feedwater, Condensate (2) OP-402 B. (1) Main Feedwater, Condensate (2) ATTACHMENT 2 C. (1) Condensate, Main Feedwater (2) OP-402 D. (1) Condensate, Main Feedwater (2) ATTACHMENT 2 Thursday, June 13, 2013 3:33:37 PM                                                            83
 
NRC Exam
: 82. Given the following plant conditions:
            -Unit 2 is raising power from 50% to 100% RTP
            -Reactor power is currently at 55% RTP at EOL
            -Control Bank D rods are at 171 steps
            -30 minutes ago, a 200 gallon dilution to the RCS was performed
            -The OAC pulls rods and releases the switch, Tavg and Reactor power steadily rise
            -APP-005-E4, DELTA FLUX ALARM, is in
            -VCT level has remained stable at 25% for the last 15 minutes Which ONE (1) of the following completes the statements below?
Based on the above conditions, the accident the crew is dealing with is a  (1) accident. The basis for the LCO actions to address the Delta Flux Alarm is to (2)
A. (1) uncontrolled rod withdraw (2) limit the amount of axial power distribution B. (1) dilution (2) limit the amount of axial power distribution C. (1) uncontrolled rod withdraw (2) limit the gross radial power distribution D. (1) dilution (2) limit the gross radial power distribution Thursday, June 13, 2013 3:33:37 PM                                                        84
 
NRC Exam
: 83. Given the following plant conditions:
            -The plant is in MODE 1
            -A CV Purge is in progress
            -R-14C, PLANT STACK, NOBLE GAS, is OOS
            -R-12, CV AIR OR PLANT STACK, NOBLE GAS, fails high Which ONE (1) of the following completes the statements below?
The running CV PURGE EXHAUST UNIT, HVE-IA or HVE-IB will      (1)  . lAW the ODCM, OFF-SITE DOSE CALCULATION MANUAL, effluent releases      (2) continue.
(REFERENCES PROVIDED)
A. (1)trip (2) can B. (1)trip (2) can NOT C. (1)NOTtrip (2) can D. (1) NOT trip (2) can NOT Thursday, June 13, 2013 3:33:37 PM                                              85
 
NRC Exam
: 84. Given the following plant conditions:
            -The reactor is at 100% RTP
            -The BOP reports R-9 is trending up and currently reads 0.6 R/hr OP-920, RADIATION MONITORING SYSTEM OMM-014, RADIATION MONITOR SETPOINTS Which ONE(1) of the following completes the statements below?
The BOP will verify R-9 setpoint lAW    (1)  . There    (2)  an EAL declaration that needs to be entered.
(REFERENCE PROVIDED)
A. (1) OMM-014 (2) is NOT B. (1)OMM-014 (2) is C. (1) OP-920 (2) is NOT D. (1)OP-920 (2) is Thursday, June 13, 2013 3:33:37 PM                                                        86
 
NRC Exam
: 85. Given the following plant conditions:
            -A Large Break LOCA has occurred
            -Neither CV Spray pump started
            -CV Pressure has reached 40.5 psig FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK FRP-J.1, RESPONSE TO HIGH CONTAINMENT PRESSURE Which ONE (1) of the following completes the statements below?
The crew will use        (1) to mitigate this event. Containment design pressure (2) been exceeded.
A. (1)FRP-P.1 (2) has NOT B. (1)FRP-J.1 (2) has NOT C. (1) FRP-P.1 (2) has D. (1) FRP-J.1 (2) has Thursday, June 13, 2013 3:33:37 PM                                                          87
 
NRC Exam
: 86. Given the following plant conditions:
Initial Conditions:
              -APP-006-D4, SIG A STM LINE HI FLOW, alarm is in
              -APP-006-E4, SIG B STM LINE HI FLOW, alarm is in
              -APP-006-F4, S/G C STM LINE HI FLOW, alarm is in
              -Steam line pressure is 600 psig Subsequently:
              -The crew has transitioned to EPP-16
              -AFW flow has been throttled to each S/G
              -SIG conditions are now as follows:
A-40% WR level, Pressure is 355 PSIG and rising B-35% WR level, Pressure is 300 PSIG and lowering C-35% WR level, Pressure is 290 PSIG and lowering EOP-E-2, FAULTED STEAM GENERATOR ISOLATION EPP-16, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS Which ONE (1) of the following completes the statements below?
Based off the initial conditions above, the plant (1)    received an automatic SI signal. The crew will      (2)
A. (1) has NOT (2) remain in EPP-16 B. (1)has (2) remain on in EPP-16 C. (1)has (2) transition to EOP-E-2 D. (1) has NOT (2) transition to EOP-E-2 Thursday, June 13, 2013 3:33:37 PM                                                        88
 
NRC Exam
: 87. Given the following plant conditions:
            -The plant is in MODE 3
            -The crew is currently in EPP-28, LOSS OF ULTIMATE HEAT SINK, for a loss of the intake structure
            -CST Level is 8%
            -Deepwell Pump D is the only available water supply to MDAFW Pump A OP-402, AUXILIARY FEEDWATER SYSTEM ATTACHMENT 6, DEEPWELL COOLING Which ONE(1) of the following completes the statements below?
lAW EPP-28, total AFW flow to the S/Gs is limited to    (1)  gpm. The crew will use (2)    to align Deepwell Pump D.
A. (1)195 (2) ATTACHMENT 6 of EPP-28 B. (1) 140 (2) ATTACHMENT 6 of EPP-28 C. (1) 195 (2) OP-402 D. (1) 140 (2) OP-402 Thursday, June 13, 2013 3:33:37 PM                                                      89
 
NRC Exam
: 88. Given the following plant conditions:
            -The plant is in MODE 4
            -Battery Charger A is in service
            -APP-036-F1O, BATT RM A/B HI/LO TEMP, alarms
            -It is determined that Battery As representative cells have an average electrolyte temperature of 65&deg;F 3.8.4, DC SOURCES-OPERATING 3.8.5, DC SOURCES-SHUTDOWN 3.8.6, BATTERY CELL PARAMETERS Which ONE (1) of the following completes the statements below?
Per APP-036-F1 0, the SRO will direct the OAO to verify the        (1)  is operating.
The SRO is required to enter LCO(s)        (2)
A. (1) alternate heater (2) 3.8.5 only B. (1) air conditioning (2)3.8.5 only C. (1) alternate heater (2)3.8.4 and 3.8.6 D. (1) air conditioning (2)3.8.4 and 3.8.6 Thursday, June 13, 2013 3:33:37 PM                                                              90
 
NRC Exam
: 89. Given the following plant conditions:
            -A plane crashed into the Intake Structure
            -The plant was manually tripped
            -The SUT tripped
            -The CRS has entered EPP-28, EPP-28, LOSS OF ULTIMATE HEAT SINK ATTACHMENT 6, DEEPWELL COOLING ATTACHMENT 7, ESTABLISHING CCW COOLING Which ONE (1) of the following completes the statements below?
The maximum time the crew has to restore cooling to an EDG to preclude adverse effects is        (1)      minutes. In order to provide cooling to at least one EDG, the CRS will direct ATTACHMENT            (2)  to be performed.
A. (1)60 (2) 6 B. (1)60 (2) 7 C. (1)40 (2) 6 D. (1)40 (2) 7 Thursday, June 13, 2013 3:33:37 PM                                                                91
 
NRC Exam
: 90. Given the following plant conditions:
              -A main steam line break inside CV results in a Safety Injection and CV Spray actuation
              -EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, has been implemented
              -CV pressure is currently 14 psig
              -CC-735, THERM BAR OUT ISO, is open SUPPLEMENT A, SAFETY INJECTION COMPONENT ALIGNMENT SUPPLEMENT B, PHASE B AND CV SPRAY COMPONENT ALIGNMENT Which ONE (1) of the following completes the statement below?
Based on current plant conditions, CC-735          (1)    in the correct position and the CRS may direct the use of        (2)  to verify its position.
A. (1)is (2) SUPPLEMENT A B. (1) is NOT (2) SUPPLEMENT A C. (1)is (2) SUPPLEMENT B D. (1) is NOT (2) SUPPLEMENT B Thursday, June 13, 2013 3:33:37 PM                                                                92
 
NRC Exam
: 91. Given the following plant conditions:
            -APP-004-E4, CV HI PRESS SFGRDITRIP, flashes and is confirmed valid
            -The reactor is at 100% RTP
            -CETs are 1225&deg;F and rising FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS FRP-C.1, RESPONSE TO INADEQUATE CORE COOLING SACRM-1, SEVERE ACCIDENT CONTROL ROOM MANAGEMENT INITIAL
 
===RESPONSE===
Which ONE (1) of the following completes the statements below?
lAW FRP-S. 1, the crew unsuccessfully tried tripping the reactor by opening the (1)      . The CRS is required to transition to (2)
A. (1) Generator A & B Circuit Breakers (2) SACRM-1 B. (1) Generator A & B Circuit Breakers (2) FRP-C.1 C. (1) feeder breaker to 480V busses 2B and 3 (2) SACRM-1 D. (1) feeder breaker to 480V busses 2B and 3 (2) FRP-C.1 Thursday, June 13, 2013 3:33:37 PM                                                      93
 
NRC Exam
: 92. Given the following plant conditions:
            -An approved radioactive liquid waste release is in progress
            -Subsequently, R-18, LIQUID EFFLUENT WASTE DISPOSAL, is reading above its alarm setpoint
            -The release is still in progress Which ONE(1) of the following completes the statements below?
R-18 reading above the alarm setpoint        (1)    have terminated the release. Per the ODCM, the release may continue provided          (2)
(REFERENCES PROVIDED)
A. (1) should (2) two independent samples are analyzed and two facility staff independently verify the release rate calculations and discharge line valving B. (1) should NOT (2) two independent samples are analyzed and two facility staff independently verify the release rate calculations and discharge line valving C. (1) should (2) the flow rate is estimated at lease once per 4 hours during actual releases D. (1) should NOT (2) the flow rate is estimated at lease once per 4 hours during actual releases Thursday, June 13, 2013 3:33:37 PM                                                              94
 
NRC Exam
: 93. Given the following plant conditions:
            -The crew has started a gaseous waste release from WGDT C
            -ATTACHMENT 10.3, GASEOUS WASTE RELEASE PERMIT-WASTE GAS DECAY TANK, is complete (SEE REFERENCE ON NEXT PAGE)
            -During the release, R-14C, PLANT STACK, NOBLE GAS, read 12K cpm Which ONE(1) of the following completes the statements below?
The      (1)    had to approve the release before it could begin. Based off of ATTACHMENT 10.3, R-14C              (2)    alarm during the release.
A. (1) E&C Supervisor (2) did NOT B. (1) E&C Supervisor (2) did C. (1)SM (2) did NOT D. (1)SM (2) did Thursday, June 13, 2013 4:26:45 PM                                                      93
 
___________
_________
ATTACHMENT 10.3 Page 1 of 2 GASEOUS WASTE RELEASE PERMIT WASTE GAS DECAY TANK RELEASE NUMBER;          l3o6                            SSN:      I?                  DATE:    lej This revision is the latest revision availbIe s yen      by:
Name (Print)                      Initial                    Signature                        Date PART I: PRE-RELEASE INFORMATION (E&C)
A I B i) D                            Estimated Relesse Start icy                  - 1o Waste Gas Decay Tank                                                      Date            Time (Circle AppropriaLe Letter)                Estimated Release Stop Te2&
Date            Time Monitor                  Setpaint                      Basis (Circle One)          CV Purge (Circle One) (NCR 410785)
R-14C                                      CPM            EC          i)              In Senfice      Not In ServiCe Maximum WGDT Flow Rate:        CX              CFM PART II: RADIATION MONITOR INFORMATION (OPS and E&C)
READING                                                                  R-14C 2
PRIOR (Channel Check)                                                                CPM SOURCECHECK 2                                                              E&CINI, 3
SETPOINTV      ERF.AT                                                                  CPM UPDATESTATUSBOARD 4                                                              OPSNI, DURING REL.EASE                          --
CPM AFTER RELEASE                                                                          CPM SETPOINTRETURNEDTQ 3                                            --
CPM STATUS 4
___________
BOARDUPIJATED
__________
__________
__________
__________
_______
OPSINI.              --
(N
 
NRC Exam
: 94. Which ONE (1) of the following completes the statement below?
The CRS is responsible for conducting a(n)      every 45  60 minutes during long lasting events.
A. Crew Update B. Alignment Brief C. Crew Shift Brief D. Plant Status Brief Thursday, June 13, 2013 3:33:37 PM                                                    96
 
NRC Exam
: 95. Given the following plant conditions:
                - The letdown line has been removed from service and cleared for maintenance to install several new vent valves.
                - An approved test procedure has been provided with the work order package to perform the line hydrostatic test following installation.
                - A clearance boundary change must be implemented to initiate the system hydrostatic test.
Which ONE (1) of the following completes the statements below?
lAW OPS-NGGC-1 301, Equipment Clearance, each boundary change shall be authorized by (1)        . The (2) will provide concurrence for Maintenance personnel to introduce fluids into the clearance boundary for the system hydrostatic test.
A. (1) an SRO (2) WCCSRO B. (1) the CRS only (2) CRS C. (1) anSRO (2) CRS D. (1) the CRS only (2) WCCSRO Thursday, June 13, 2013 3:33:38 PM                                                        97
 
NRC Exam
: 96. Given the following plant conditions:
                -  Two trains of RHR are OPERABLE
                -  RCS is at 135&deg;F and has been drained to -30 inches standpipe level for RCP seal replacement
                -  Maintenance has requested that both CV Personnel Hatch doors be opened to allow cables and hoses to be routed through the doors to support maintenance activities Which ONE (1) of the following completes the statements below?
lAW OMM-033, IMPLEMENTATION OF CV CLOSURE, CV Personnel Hatch doors can be opened provided CV closure can be implemented within          (1)    hours. The hoses and cables can be routed through the hatch provided      (2)    for removal.
A. (1)0.5 (2) the hoses and cables have quick disconnects B. (1)4 (2) the hoses and cables have quick disconnects C. (1)0.5 (2) dedicated personnel are stationed inside the CV with tools needed D. (1)4 (2) dedicated personnel are stationed inside the CV with tools needed Thursday, June 13, 2013 3:33:38 PM                                                              98
 
NRC Exam
: 97. Given the following plant conditions:
            -  A Site Area Emergency has been declared due to a LOCA outside containment
            -  All Emergency Response Organization facilities are staffed and functional
            -  The TSC has determined that the leak can be isolated
            -  Expected exposure to isolate the leak is> 5 Rem TEDE
            -  An operator has been briefed and is awaiting approval for entry into the Auxiliary Build ing to isolate the leak Which ONE (1) of the following completes the statement below?
Authorization of the exposure        (1)  be delegated to the Radiological Control Director. If authorized, the operator is allowed to receive up to    (2)    REM for this entry.
A. (1) can (2) 10 B. (1) can (2) 25 C. (1) can NOT (2) 10 D. (1) can NOT (2) 25 Thursday, June 13, 2013 3:33:38 PM                                                              99
 
NRC Exam
: 98. Given the following plant conditions:
              -A Large Break LOCA has occurred
              -Containment pressure is 32 psig and rising
              -HVH-1 and HVH-2 have tripped
              -Containment Sump level is rising
              -R-32A, CV High P      , has the current indication:
Which ONE (1) of the following completes the statement below?
Based on the information provided a    (1)  must be declared due to    (2)
(References Provided)
A. (1) Site Area Emergency (2) Loss of the Reactor Coolant AND Fuel Cladding Barriers B. (1) General Emergency (2) Loss of the Reactor Coolant, Fuel Cladding AND Containment Barriers C. (1) Site Area Emergency (2) Loss of the Reactor Coolant Barrier AND a Potential Loss of the Containment Barrier D. (1) General Emergency (2) Loss of the Reactor Coolant AND Fuel Cladding Barrier AND Potential Loss of the Containment Barrier Thursday, June 13, 2013 5:13:02 PM                                                          98
 
NRC Exam
: 99. Given the following plant conditions:
            -The crew is in EPP-28, LOSS OF ULTIMATE HEAT SINK, for a total loss of the intake structure
            -Subsequently a loss of all AC power occurs Which ONE (1) of the following completes the statement below?
The CRS          (1)    transition to EPP-1, LOSS OF ALL AC POWER, because (2)
A. (1)will NOT (2) EPP-28 contains actions to deal with a loss of all AC power B. (1) will (2) EPP-1 contains actions to deal with a loss of all AC power C. (1) will (2) EPP-1 has priority over all other EPP procedures D. (1)will NOT (2) EPP-28 has priority over all other EPP procedures Thursday, June 13, 2013 3:33:38 PM                                                    101
 
NRC Exam 100. Given the following plant conditions:
                -  Today at 0100 LCO 3.4.13, RCS OPERATIONAL LEAKAGE, was entered due to an 8 gpm leak from a crack on the spray line penetration weld at the PZR
                -  The crew commenced a shutdown at 0200
                -  The plant reached MODE 3 at 0800 Which ONE (1) of the following completes the statement below?
Notifications must be made to the NRC by        (1)    and    (2)
(REFERENCES PROVIDED)
A. (1) 0300 (2) 0800 B. (1) 0600 (2) 0800 C. (1) 0300 (2) 1200 D. (1) 0600 (2) 1200 You have completed the test!
Thursday, June 13, 2013 3:33:38 PM                                                            102
 
Table of Contents for Provided References
-LCO 3.8.1, AC Sources-Operating
-LCO 3.4.13, RCS Operational LEAKAGE
-ODCM Table 2.6-1, Radioactive Liquid Effluent Monitoring Instrumentation
-ODCM Section 3.10, Radioactive Gaseous Effluent Monitoring Instrumentation
-AP-30, NRC Reporting Requirements, Attachments 11.1, IMMEDIATE(One Hour) Notifications to the NRC, 11.2, FOUR Hour Notifications to the NRC, 11.3, EIGHT Hour Notifications to the NRC
-EAL Hot Conditions Board
 
ANSWER KEY REPORT for NRC Exam Test Form: 0 Answers ID                                      Points Type 0 008 AK2.03 1                              1.00 MCS  D 2      009 EK1.02 1                              1.00 MCS  D 3      011 EG2.4.21 1                            1.00 MCS  D 4      022 AK3.07 1                              1.00 MCS  A 5      025 AK2.02 1                              1.00 MCS  D 6      027 AA1.02 1                              1.00 MCS  C 7      029 EA1.02 1                              1.00 MCS  C 8      038 EK3.08 1                              1.00 MCS  B 9      040 AA2.02 1                              1.00 MCS  D 10    054 AK1.01 1                              1.00 MCS  A 11    055EG2.4.21 1                            1.00 MCS  B 12    056AA1.151                                1.00 MCS  D 13    057 AA2.19 1                              1.00 MCS  A 14    058 AK1.01 1                              1.00 MCS  A 15    077 AK3.02 1                              1.00 MCS  C 16    WE/04EK2.1 1                              1.00 MCS  D 17    WE/OS G2.4.6 1                            1.00 MCS  D 18    WE/li EA2.2 1                            1.00 MCS  B 19    028 AA2.03 1                              1.00 MCS  B 20    032 AA1.0i 1                              1.00 MCS  B 21    033 AG2.2.22 1                            1.00 MCS  B 2      060 AK3.02 1                              1.00 MCS  B 3    067 AK1.02 1                              1.00 MCS  B 24    068 AG2.2.37 1                            1.00 MCS  B 25    076 AA1.04 1                              1.00 MCS  A 26    W/E08 EK1.2 1                            1.00 MCS  A 27    WIEIO EK2.2 1                            1.00 MCS  A 28    003 A1.O9 1                              1.00 MCS  C 29    003 K4.04 1                              1.00 MCS  B 30    004 K3.08 1                              1.00 MCS  A 31    004 K6.26 1                              1.00 MCS  C 32    005 A2.O4 1                              1.00 MCS  D 33    006A4.O22                                1.00 MCS  A 34    006 K5.1O 1                              1.00 MCS  B 35    007 K5.02 1                              1.00 MCS  A 36    008 A2.03 1                              1.00 MCS  C 37    OIOK1.082                                1.00 MCS  D 38    012A3.O41                                1.00 MCS  C 39    013 K2.O1 1                              1.00 MCS  C 40    022 A3.O1 1                              1.00 MCS  D 41    026 G2.2.42 1                            1.00 MCS  C 42    039 A4.04 1                              1.00 MCS  D 43    059 A2.12 1                              1.00 MCS  C 44    061 K6.02 1                              1.00 MCS  D 5  062 K3.O1 1                              1.00 MCS  B 46    063 A1.O1 2                              1.00 MCS  B Thursday, June 13, 2013 5:20:47 PM
 
ANSWER KEY REPORT for NRC Exam Test Form: 0 Answers ID                                      Points Type 0 47    06402.1.27 1                              1.00 MCS  A 48    064 K2.01 1                              1.00 MCS  A 49    073 A4.01 1                              1.00 MCS  D 50    073 K4.01 I                              1.00 MCS  C 51    076A1.021                                1.00 MCS  B 52    0761(2.011                                1.00 MCS  D 53    078 G2.4.50 1                            1.00 MCS  B 54    078K1.041                                1.00 MCS  C 55    103 K4.04 1                              1.00 MCS  C 56    002 A2.04 1                              1.00 MCS  D 57    011 K6.03 I                              1.00 MCS  A 58    01402.1.302                              1.00 MCS  D 59    017 A1.01 1                              1.00 MCS  C 60    027 K2.01 1                              1.00 MCS  B 61    029A4.041                                1.00 MCS  D 62    033 K4.01 1                              1.00 MCS  D 63    035 K5.01 I                              1.00 MCS  B 64    015 A3.02 1                              1.00 MCS  A 65    068 1(1.072                              1.00 MCS  D 66    02.1.14 1                                1.00 MCS  D 67    02.1.40 1                                1.00 MCS  D 8      02.2.12 1                                1.00 MCS  B
)    02.2.71                                  1.00 MCS  D 70    G2.3.14 1                                1.00 MCS  B 71    02.3.15 1                                1.00 MCS  C 72    02.3.41                                  1.00 MCS  C 73    02.4.12 1                                1.00 MCS  C 74    0 2.4.26 2                                1.00 MCS  B 75    02.4.39 1                                1.00 MCS  B 76    008 AG2.1.7 SRO 1                        1.00 MCS  C 77    054 AG2.4.35 SRO 1                        1.00 MCS  C 78    055 EA2.06 SRO 1                          1.00 MCS  A 79    058 AG2.1.19 SRO I                        1.00 MCS  A 80    077 AA2.07 SRO 1                          1.00 MCS  D 81    W/E 05 EA2.2 SRO 1                        1,00 MCS  A 82    001 AA2.05 SRO 2                          1.00 MCS  A 83    060 AG2.2.40 SRO 1                        1.00 MCS  B 84    061 AA2.02 SRO 1                          1.00 MCS  B 85    W/E14 EG2.2.38 SRO I                      1.00 MCS  B 86    012G2.1.2OSRO1                            1.00 MCS  C 87    061 02.4.20 SRO 1                        1.00 MCS  C 88    063 A2.02 SRO 1                          1.00 MCS  C 89    076 A2.01 SRO 1                          1.00 MCS  C 90      103 A2.03 SRO 2                          1.00 MCS  D I    001A2.13SRO1                              1.00 MCS  A 92    068 A2.04 SRO 1                          1.00 MCS  A Thursday, June 13, 2013 5:20:47 PM                                  2
 
ANSWER KEY REPORT for NRC Exam Test Form: 0 Answers ID                                      Points Type 0 93    071 G2.4.46 SRO 1                          1.00 MCS  D 94    G2.1.38 SRO 1                              1.00 MCS  D 95    G2.2.13 SRO 1                              1.00 MCS  C 96    G2.2.18 SRO 1                              1.00 MCS  A 97    G2.3.13 SRO 1                              1.00 MCS  C 98    G2.3.5 SRO 1                              1.00 MCS  A 99    G2.4.23 SRO 1                              1.00 MCS  A 100  G2.4.30 SRO 1                              1.00 MCS  B SECTION 1 ( 100 items)                        100.00 Thursday, June 13, 2013 5:20:47 PM                                  3}}

Revision as of 15:05, 4 November 2019

Initial Exam 2013-301 Final SRO Written Exam
ML13219A180
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Issue date: 08/06/2013
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DUKE

H .B. Robinson ILC-13 NRC Licensing Exam SRO Written Exam Final Submittal

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:

Region: I El ii El III El iv El Reactor Type: W El CE El BW El GE El 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 / / Points Applicants Scores / / Points Applicants Grade I / Percent

Name: NRC Exam Form: 0 Version: 0

1. Given the following plant conditions:

-Plant is at 100% RTP

-RCS pressure is 2280 psig

-PC-444J, PZR PRESSURE, is in Automatic at 65% ouput

-PCV-455A, PZR SPRAY 444G, controller is in Automatic at 25% ouput

-PCV-455C, PZR PORV, partially opens

-The OAC takes action and manually closes PCV-455C

-NO further operator actions have been taken

-Current RCS pressure is 2150 psig Which ONE (1) of the following completes the statements below?

PCV-455A, PZR SPRAY 444G, controller output indication currently reads (1)

PC-444J output indication currently reads (2)

A. (1)25%

(2) 65%

B. (1)25%

(2) 0 C. (1)0 (2) 65%

D. (1)0 (2) 0 Thursday, June 13, 2013 4:26:18 PM

NRC Exam

2. Given the following plant conditions:

-A EDG is OOS

-Reactor power is at 100% RTP Subsequently:

-A fault on 4Kv bus 2 leads to a reactor trip

-Upon the reactor trip, a small break LOCA occurs

-The crew is in EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT

-CETCs read 547°F

-Max. CV pressure reached was 3.4 psig

-RCS Wide Range Pressure reads 1292 psig Which ONE (1) of the following completes the statements below?

The RCS subcooling is (1) . Based off the indications above, RCP trip criteria for EOP-E-1 Foldout is (2)

A. (1) 29.6°F (2) NOT met B. (1) 31°F (2) met C. (1) 29.6°F (2) met D. (1) 31°F (2) NOT met Thursday, June 13, 2013 4:26:18 PM 2

NRC Exam

3. Given the following plant conditions:

-A Seismic Event coincident with a Large Break LOCA has occurred

-CV pressure is currently 11 psig

-B CV Spray Pump has tripped

-All other ESF components operated properly

-CV Sump level is 380 inches and rising

-CV Radiation levels are <5 r/hr FRP-J.1, RESPONSE TO HIGH CONTAINMENT PRESSURE FRP-J.2, RESPONSE TO CONTAINMENT FLOODING Which ONE (1) of the following completes the statements below?

Based off the indications above, the crew meets entry conditions for (1) . One of the Major Action Categories of this procedure is (2)

A. (1) FRP-J.1 (2) Verify Containment Isolation and Heat Removal B. (1) FRP-J.1 (2) Check for and Isolate Faulted Steam Generator C. (1) FRP-J.2 (2) Determine the radioactivity level of the sump fluid D. (1) FRP-J.2 (2) Try to Identify Unexpected Source of Sump Water and Isolate It if Possible Thursday, June 13, 2013 4:26:18 PM 3

NRC Exam

4. Given the following plant conditions:

-The following conditions are at time 12:30:00:

-The Reactor is at 100% RTP

-All control systems are in normal alignments

-Charging flow has been rising and is currently at 50 gpm

-Tl-140, REGEN HX LTDN OUTLET TEMP, is lowering

-VCT level is lowering

-The following conditions are at time 12:45:00:

-RCS Pressure is 2235 psig

-Charging pump discharge pressure is 2100 psig Which ONE (1) of the following completes the statements below?

The leak is located (1) of the Regenerative Heat Exchanger.

The crew takes action to close HIC-121, Charging Flow, lAW AOP-018, REACTOR COOLANT PUMP ABNORMAL CONDITIONS, Section C, LOSS OF SEAL INJECTION. The purpose of doing this is to (2)

A. (1) downstream (2) isolate the charging line leak B. (1) downstream (2) maintain minimum RCP Seal Injection Flow C. (1) upstream (2) isolate the charging line leak D. (1) upstream (2) maintain minimum RCP Seal Injection Flow Thursday, June 13, 2013 4:26:18 PM 4

NRC Exam

5. Given the following plant conditions:

-The plant is in mid loop operation to repair a SIG primary manway leak

-RCS level is -68 inches and rising very slowly

-RHR pump A is in service at 3500 gpm

-The operator notices that RHR flow and pressure are oscillating Which ONE (1) of the following completes the statement below?

lAW AOP-020, LOSS OF RESIDUAL HEAT REMOVAL (SHUTDOWN COOLING), the crew will reduce RHR flow to in an attempt to stabilize the RHR oscillations.

A. 3250 gpm B. 3000 gpm C. 2800 gpm D. 1500 gpm Thursday, June 13, 2013 4:26:18 PM 5

NRC Exam

6. Given the following plant conditions:

-The reactor is at 100% RTP

-P1-444, CH I PRZR PRESS, reads 2310 psig and rising

-P1-455, 456 and 457, PROT CH 1(11 and Ill) PRZR PRESS, all read approximately 2210 psig and lowering Which ONE (1) of the following completes the statements below?

To combat this, the OAC will take PC-444J to MANUAL and (1) its output to energize all PZR heaters.

After PC-444J is adjusted, P1-458, Calibration PZR Pressure, will indicate (2) psig for maximum proportional heater output.

A. (1) raise (2)-15 B. (1) raise (2) +15 C. (1) lower (2)-15 D. (1) lower (2) +15 Thursday, June 13, 2013 4:26:18 PM 6

NRC Exam

7. Given the following plant conditions:

-The crew attempted to trip the reactor and it failed to trip

-They are initiating emergency boration of the RCS

-The Boric Acid Pump aligned for blend failed to start Which ONE (1) of the following completes the statement below?

To initiate emergency boration, the crew will open (1) . The emergency boration can be secured when PR Channels are <5% (2) a Negative IR Startup Rate.

A. (1) MOV-350 (2) or B. (1) MOV-350 (2) and C. (1) LCV-115B and close LCV-115C (2) and D. (1) LCV-115B and close LCV-115C (2) or Thursday, June 13, 2013 4:26:18 PM 7

NRC Exam

8. Which ONE (1) of the following identifies the reason for securing the RCPs in EOP-E-3, STEAM GENERATOR TUBE RUPTURE?

A. Minimizes the impact upon core heat removal.

B. It insures against possible operator misdiagnosis.

C. Prevents excessive depletion of RCS water inventory.

D. Prevents the possiblity of RCP motor overspeed and catastrophic failure.

Thursday, June 13, 2013 4:26:18 PM 8

NRC Exam

9. Given the following plant conditions:

-The reactor is at 50% RTP

-A small steam line leak has been reported

-The CRS implements Attachment 10.4, CONTROL BAND AND TRIP LIMIT GUIDANCE, from OMM-022, EMERGENCY OPERATING PROCEDURES USERS GUIDE

-APP-006-A2, S/G A STM>FW FLOW is in alarm lAW Attachment 10.4, at what NR S/G level is the crew required to manually trip the reactor?

A. 16%

B. 21%

C. 30%

D. 35%

Thursday, June 13, 2013 4:26:18 PM 9

NRC Exam

10. Given the following plant conditions:

-The reactor is at 100% RTP

-A large Feedwater Line Break occurs at the piping connection to SIC A inside the Cv Which ONE (1) of the following completes the statements below?

Prior to the Reactor trip, RCS Tavg will (1) . The reactor will automatically trip on (2)

A. (1) rise (2) Low-Low S/G level B. (1) lower (2) Low-Low S/C level C. (1) rise (2) Low S/C Level with Steam Flow> Feed Flow D. (1) lower (2) Low S/G Level with Steam Flow> Feed Flow Thursday, June 13, 2013 4:26:18 PM 10

NRC Exam

11. Given the following plant conditions:

-The crew has just finished their immediate actions of EPP-1, LOSS OF ALL AC POWER

-Narrow Range SIG levels are all 6%

-Total FW Flow to the SIGs is 500 GPM Which ONE (1) of the following completes the statements below?

CSFSTs (1) being monitored for information only. A red path (2) exist on CSF-3, HEAT SINK.

A. (1) are NOT (2) does NOT B. (1)are (2) does NOT C. (1) are NOT (2) does D. (1)are (2) does Thursday, June 13, 2013 4:26:18 PM 11

NRC Exam

12. Given the following plant conditions:

-A Loss of off-site power occurs

-Fifteen seconds later a Large Break LOCA occurs Which ONE (1) of the following completes the statements below?

The BOP will expect to see the SWBPs started on the (1) . SWBP suction pressure (2) have to be at least 30 psig for the SWBPs to start.

A. (1) Blackout sequencer (2) does B. (1) Blackout sequencer (2) does NOT C. (1) SI sequencer (2) does D. (1) SI sequencer (2) does NOT Thursday, June 13, 2013 4:26:18 PM 12

NRC Exam

13. Given the following plant conditions:

-The reactor is currently at 6% power with the turbine rolling at 1800 rpm lAW GP-005, POWER OPERATION

-Power is lost to Instrument Bus (SB) #1 Which ONE (1) of the following completes the statements below?

The loss of lB #1 (1) cause a reactor trip. The turbine is (2)

A. (1) will (2) tripped B. (1)will NOT (2) tripped C. (1) will (2) NOT tripped D. (1) will NOT (2) NOT tripped Thursday, June 13, 2013 4:26:18 PM 13

NRC Exam

14. Given the following plant conditions:

-Battery chargers A and B are in service

-Battery chargers A-i and B-I are in standby

-12:00 MCC-5 is de-energized

-13:01 APP-036-D3, BATT A/B LO VOLT, alarm is illuminated

-There are multiple indications of loss of control power to components Subsequently:

-13:05:00 MCC-5 is re-energized Which ONE (1) of the following completes the statements below?

Battery charger(s) (1) will need to be manually restarted. As of 13:05:00 the following day, the batteries (2) be fully charged.

A. (I)A-1 only (2) will B. (1)A&A-1 (2) will C. (I)A&A-1 (2) will NOT D. (1)A-1 only (2) will NOT Thursday, June 13, 2013 4:26:18 PM 14

NRC Exam

15. Given the following plant conditions:

-The reactor is at 25% RTP

-APP-009-F8, 4KV BUSES LO FREQ, is in alarm

-The crew enters AOP-026, GRID INSTABILITY

-Frequency is now at 58.3Hz Which ONE (1) of the following completes the statements below?

The crew will (1) trip the reactor. lAW AOP-026 basis document, the purpose of tripping the RCPs is to (2)

A. (1) immediately (2) prevent the automatic reactor trip from low flow B. (1) wait 5 minutes, and then (2) prevent the automatic reactor trip from low flow C. (1) immediately (2) prevent the automatic RCP trip at 58.2 Hz D. (1) wait 5 minutes, and then (2) prevent the automatic RCP trip at 58.2 Hz Thursday, June 13, 2013 4:26:18 PM 15

NRC Exam

16. Given the following plant conditions:

-The plant is in Mode 3

-The crew has entered EPP-20, LOCA OUTSIDE CONTAINMENT SI-870 A & B, BIT INJ Valves RHR-744 A & B, RHR COLD LEG INJ Valves Which ONE (1) of the following completes the statement below?

In order to isolate a leak in the Cold Leg Injection piping, EPP-20 will have the crew shut (1) and monitior (2) to see if the leak is isolated.

A. (1)SI-870A&B (2) RCS pressure B. (1)Sl-870A&B (2) PZR level C. (1)RHR-744A&B (2) PZR level D. (1)RHR-744A&B (2) RCS pressure Thursday, June 13, 2013 4:26:18 PM 16

NRC Exam

17. Which of the following is the FIRST mitigation strategy that FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, directs you to attempt?

A. Maximize charging flow to cool the RCS B. Depressurize the SIGs to raise subcooling C. Initiation of RCS Bleed and Feed Heat Removal D. Attempt Restoration of Feed Flow To Steam Generators Thursday, June 13, 2013 4:26:18 PM 17

NRC Exam

18. Given the following plant conditions:

-The crew has implemented EPP-15, Loss of Emergency Coolant Recirculation

-The crew is initiating an RCS cooldown to cold shutdown

-The following table is a plot of the RCS cooldown:

TIME RCS TCOLD TIME RCS TCOLD 0800 547°F 0945 425°F 0815 530°F 1000 395°F 0830 520°F 1015 382°F 0845 505°F 1030 364°F 0900 498°F 1045 340°F 0915 478°F 1100 320°F 0930 447°F 1115 300°F Which ONE (1) of the following completes the statements below?

The cooldown rate limit (1) been exceeded. At (2) RWST level, the crew is required to secure all running ECCS pumps taking a suction from the RWST.

A. (1) has (2) 27%

B. (1)has (2)9%

C. (1) has NOT (2) 27%

D. (1) has NOT (2) 9%

Thursday, June 13, 2013 4:26:18 PM 18

NRC Exam

19. Given the following plant conditions:

-Reactor is at 100% RTP

-A & B Charging pumps are OOS

-HIC-121, CHARGING FLOW VALVE, controller indicates 100% output

-CVC-297 A/B/C are full open

-Seal Injection flow are all about 6.6 GPM CVC-297A, RCP A SEAL WATER FLOW CONTROL VALVE CVC-297 B, RCP B SEAL WATER FLOW CONTROL VALVE CVC-297 C, RCP C SEAL WATER FLOW CONTROL VALVE LT-459, CH I PRZR LEVEL LT-461, CH Ill PRZR LEVEL Which ONE (1) of the following completes the statements below?

Based off the conditions above, LT- (1) has failed low. ITS LCO 3.4.17, Chemical and Volume Control System, requirements (2) met.

A. (1)461 (2) are NOT B. (1)459 (2) are NOT C. (1)461 (2) are D. (1)459 (2) are Thursday, June 13, 2013 4:26:18 PM 19

NRC Exam

20. Given the following plant conditions:

-The plant is in Mode 3 preparing for startup.

-Several alarms are received and multiple controllers & indicators lose power.

-Nl-32, Source Range Nuclear Instrument, is deenergized

-The crew has entered AOP-024, LOSS OF INSTRUMENT BUS

-An AO reports that an ILC student doing JPM walkdowns bumped into the supply breaker and the AO heard the breaker trip Which ONE (1) of the following completes the statement below?

In order to restore power to N 1-32, the crew will need to reset and close the supply breaker to Instrument Bus (1) at (2)

A. (1)1 (2) InverterA B. (1)2 (2) InverterA C. (1)1 (2) MCC-5 D. (1)2 (2) MCC-5 Thursday, June 13, 2013 4:26:18 PM 20

NRC Exam

21. Given the following plant conditions:

-Power is above P-6

-Power is below P-i 0

-Power ascension is in progress

-Nl-35, INTERMEDIATE RANGE NUCLEAR INSTRUMENT, fails as is

-Nl-36, INTERMEDIATE RANGE NUCLEAR INSTRUMENT, fails as is Which ONE (1) of the following correctly completes the statement below?

The maximum time the crew has to (1) is (2) lAW LCO 3.3.1, REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION.

A. (1) suspend operations involving positive reactivity additions (2) 15 minutes B. (1) suspend operations involving positive reactivity additions (2) immediately C. (1) increase thermal power to >P-10 (2) 15 minutes D. (1) increase thermal power to >P-10 (2) immediately Thursday, June 13, 2013 4:26:18 PM 21

NRC Exam

22. Given the following plant conditions:

-High radiation alarms have just been received from R-20, FUEL HANDLING BUILDING LOWER LEVEL, and R-30, FUEL HANDLING BUILDING LOWER LEVEL HIGH RANGE

-The Inside Auxiliary Operator reports the following:

-WGDT A is at 40 psig and is in service

-WGDT B is at 20 psig and is in standby

-WGDT C is at 80 psig and is on cover gas

-WGDT D is at 60 psig with pressure slowly lowering

-AOP-009, ACCIDENTAL GAS RELEASE FROM A WGDT, has been entered

-The crew has started HVE-5A, AUX BLDG CHARCOAL EXH FAN Which ONE (1) of the following completes the statements below?

The basis for starting HVE-5A lAW AOP-009 is to (1) . WGDT D will be placed on cover gas and equalized with WGDT (2)

A. (1) minimize any radiological release (2) A B. (1) minimize any radiological release (2) B C. (1) limit the concentration of explosive gases (2) B D. (1) limit the concentration of explosive gases (2) A Thursday, June 13, 2013 4:26:18 PM 22

NRC Exam

23. Given the following plant conditions:

-A fire breaks out on the RTGB

-The crew has entered AOP-041, RESPONSE TO FIRE EVENT, and subsequently, DSP-OO1, ALTERNATE SHUTDOWN DIAGNOSTIC

-The crew has tripped the reactor CVC-200 A/B/C, LTDN ORIFICE PCV-455C, PZR PORV PCV-456, PZR PORV Which ONE (1) of the following completes the statements below?

Prior to leaving the control room, the QAC will (1) . This is performed to (2)

A. (1) Verify CVC-200 A/B/C closed (2) prevent spurious operation B. (1) Isolate PCV-456 & PCV-455C (2) prevent spurious operation C. (1) Verify CVC-200 A/B/C closed (2) allow for remote operation of these valves D. (1) Isolate PCV-456 & PCV-455C (2) allow for remote operation of these valves Thursday, June 13, 2013 4:26:19 PM 23

NRC Exam

24. Given the following plant conditions:

-A fire has broke out in the Hagan Room

-It has spread to the Control Room

-The crew is currently in DSP-002, HOT SHUTDOWN USING THE DEDICATED/ALTERNATE SHUTDOWN SYSTEM

-Attachment 1, TURBINE BUILDING OPERATOR ACTIONS, are complete

-The DS Bus is energized Which ONE (1) of the following completes the statements below?

One of the operators will start A CCW pump from (1) . MDAFW pumps (2) available.

A. (1) the Charging Pump room (2) are B. (1) the Charging Pump room (2) are NOT C. (1) the Rod Control room (2) are D. (1) the Rod Control room (2) are NOT Thursday, June 13, 2013 4:26:19 PM 24

NRC Exam

25. The reactor is at 100% RTP. Which of the following would indicate failed fuel?

A.

k mRftr rL R-9 0

6 LETDOWN LINE AREA B.

I I1 k mRlhr ccl.

1*1.

R-2 0

CV AREA C.

499 K CPM wI. rAl.

R-11

  • 6 CV AIR && PLANT VENT PAR11CLJ LATE D.

ll CPM I IJ R-12 U

  • V AIR && PLANT VENT RADIOACTIVE GAS 6

Thursday, June 13, 2013 5:12:17 PM 25

NRC Exam

26. Given the following plant conditions:

-A reactor trip has occurred

-The turbine failed to trip

-The MSIVs have failed to close

-The crew is in FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK Which ONE (1) of the following completes the statements below?

lAW FRP-P.1, the crew will maintain (1) . The crew will be required to perform a soak for (2) hour(s).

A. (1) between 80-90 gpm feed flow to each S/G (2) 1 B. (1) between 80-90 gpm feed flow to each S/G (2)29 C. (1) total feed flow> 300 gpm (2) 1 D. (1) total feed flow> 300 gpm (2) 29 Thursday, June 13, 2013 4:26:19 PM 26

NRC Exam

27. Given the following plant conditions:

-The crew has experienced a Loss of All A/C Power

-They have transitioned to EPP-6, NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN VESSEL Which ONE (1) of the following completes the statements below?

JAW EPP-6, the maximum RCS temperature at which RHR can be placed in service is LESS THAN (1) . Per EPP-6, the maximum cooldown rate is LESS THAN (2) in the last 60 minutes.

A. (1) 350°F (2) 100°F B. (1) 250°F (2) 100°F C. (1) 350°F (2) 25°F D. (1) 250°F (2) 25°F Thursday, June 13, 2013 4:26:19 PM 27

NRC Exam

28. Given the following plant conditions:

- The Plant is at 100% RTP

- APP-001-D2, RCP #1 SEAL LEAKOFF HI FLOW is in alarm

- RCP #1 Seal Leakoff Flows and Thermal Barrier D/Ps are as indicated (SEE REFERENCE ON NEXT PAGE)

Which ONE (1) of the following completes the statements below?

RCP A seal is failed. To prevent damage to the RCP A Seal Stack, the RCP A SEAL LEAKOFF Valve, CVC-303A should be closed after tripping RCPA.

A. (1)#1 (2) immediately B. (1)#2 (2) immediately C. (1)#1 (2) between 3 and 5 minutes D. (1)#2 (2) between 3 and 5 minutes Thursday, June 13, 2013 4:26:19 PM 28

P1. 1 56A I PI-155A PI-154A Thursday, June 13, 2013 5:15:08 PM 29

NRC Exam

29. Which ONE (1) of the following completes the statements below?

When Seal Injection is unavailable, CCW flow to the (1) ensures adequate cooling of the Reactor Coolant Pump seals. This cooling flow path remains in service until isolated by a Phase (2) actuation.

A. (1) Thermal Barrier (2) A B. (1) Thermal Barrier (2) B C. (1) Seal WaterHX (2) A D. (1) Seal Water HX (2) B Thursday, June 13, 2013 4:26:19 PM 29

NRC Exam

30. Given the following plant conditions:

- The plant is operating at 100% RTP.

- Seal Injection flow to each RCP is 8.5 gpm

- C Charging Pump is currently running in Manual at minimum speed.

- A Charging Pump is running in MANUAL at 35% demand during the performance of OP-301-1, Section 8.4.7, Charging Pump Break-In After Maintenance.

- CVC-283C, Charging Pump A Discharge Relief, has lifted and has not reseated.

Which ONE (1) of the following identifies the impact on Seal Injection flow(s) AND how this malfunction would be addressed by AOP-018, Reactor Coolant Pump Abnormal Conditions?

Which ONE (1) of the following completes the statement below?

Seal Injection flows will lower to (1) and AOP-01 8 directs the operators to (2)

A. (1) ZERO flow (2) Isolate letdown, secure all Charging Pumps, manually isolate A Charging pump.

B. (1) MINIMUMfI0w(--6gpmeach)

(2) Isolate letdown, secure all Charging Pumps, manually isolate A Charging pump.

C. (1) ZERO flow (2) Stop A Charging Pump and adjust the speed of C Charging Pump to restore normal seal injection flows.

D. (1) MINIMUM flow ( 6 gpm each)

(2) Stop A Charging Pump and adjust the speed of C Charging Pump to restore normal seal injection flows.

Thursday, June 13, 2013 4:26:19 PM 30

NRC Exam

31. Given the following plant conditions:

-The RCS is on RHR and SOLID

-RCS pressure is 340 psig

-PC-145, PRESSURE, in AUTO

-HIC-142, PURIFICATION FLOW, controller seffing is at 55% demand Subsequently, an RCS leak occurs Which ONE (1) of the following completes the statement below?

PC-145 controller output LI) and PCV-145 throttles (2)

A. (1) lowers (2) closed B. (1) lowers (2) open C. (1) rises (2) closed D. (1) rises (2) open Thursday, June 13, 2013 4:26:19 PM 31

NRC Exam

32. Given the following plant conditions:

- The plant is in Mode 5.

- The air supply line to HCV-758, RHR HX OUTLET FLOW TO COLD LEGS, breaks, causing a complete loss of Instrument Air to the valve.

Which ONE (1) of the following completes the statements below?

Based off the conditions above, total RHR flow initially (1) . lAW AOP-020, Loss of Residual Heat Removal (Shutdown Cooling), the crew will MANUALLY throttle A. (1) rises (2) FCV-605, RHR HX BYPASS closed B. (1) rises (2) RHR-764, HCV-758 BYPASS closed C. (1) lowers (2) FCV-605, RHR HX BYPASS open D. (1) lowers (2) RHR-764, HCV-758 BYPASS open Thursday, June 13, 2013 4:26:19 PM 32

NRC Exam

33. Given the following plant conditions:

-The reactor is at 100% RTP

-A Safety Injection signal is received SI-870 A/B, BIT INJECTION TANK OUTLETS RHR-744 A/B, LOOP DISCHARGE TO RCS ISOLATION VALVES SI-865 A/B/C, SI ACCUMULATOR DISCHARGE VALVES S1-867 NB, BIT INJECTION TANK INLETS Which of the following valves will reposition because of the Safety Injection signal?

A. 5 1-870 NB & RHR-744 A/B B. 5 1-865 NB/C & S 1-867 A/B C. S1-870 NB & Sl-865 A/B/C D. RHR-744 A/B & Sl-867 NB Thursday, June 13, 2013 4:26:19 PM 33

NRC Exam

34. Given the following plant conditions:

-The reactor was at 100% RTP when a LOCA occurs

-A Safety Injection has been initiated and is injecting into the core Immediately upon the Safety Injection Flow going to the core, the INNER WALL of the SI piping that connects to the RCS undergoes (1) stress. If one of the SI pipes that connects to the RCS breaks from this stress, (2) pipe(s) would still be available to supply SI flow to the core.

A. (1) tensile (2) one B. (I) tensile (2) two C. (1) compressive (2) one D. (1) compressive (2) two Thursday, June 13, 2013 4:26:19 PM 34

NRC Exam

35. Given the following plant conditions:

- A bubble is being drawn in the Pressurizer lAW, OP-I 04, Pressurizer Operations

- RCS pressure is 335 psig

- Tl-454, PRZR VAPOR TEMP is 432°F

- LI-462, COLD PRESSURIZER, Level is 80% and slowly lowering

- Tl-463, PZR PWR RELIEF LINE TEMP, reads 320°F A PZR PORV (I) leaking. Confirmatory indications would be pressure, level, or temperature.

A. (1) is (2) PRT B. (I) is (2) RCDT C. (1) is NOT (2) PRT D. (I) is NOT (2) RCDT Thursday, June 13, 2013 4:26:19 PM 35

NRC Exam

36. Given the following plant conditions:

- The reactor is at 100% RTP

- CCW Heat Exchanger outlet temperature is 106°F and rising

- All Service Water Pumps are running

- The highest RCP Motor bearing temperature is 190°F and rising

- Service Water pressure is 46 psig and stable on both headers AOP-018, REACTOR COOLANT PUMP ABNORMAL CONDITIONS AOP-014, COMPONENT COOLING WATER SYSTEM MALFUNCTION Which ONE (1) of the following completes the statements below?

Based off the conditions above, the (1) . The crew is required to (2)

A. (1) RCP operating limits have been exceeded (2) monitor all RCP parameters lAW AOP-01 8.

B. (1) RCP operating limits have been exceeded (2) Lower heat load on CCW system lAW AOP-014.

C. (1) CCW system cooling capacity is degraded (2) lower heat load on CCW system lAW AOP-014 D. (1) CCW system cooling capacity is degraded (2) monitor all RCP parameters lAW AOP-018.

Thursday, June 13, 2013 4:26:19 PM 36

NRC Exam

37. Given the following plant conditions:

-RCS Tavg is 560°F

-LT-459, PRZR LEVEL, has failed high Which ONE (1) of the following completes the statements below?

Prior to the failure, pressurizer level was (1) . Pressurizer heaters will all turn on when LT-459 reaches (2)

A. (1) 36.1%

(2) 46.1%

B. (1) 53.3%

(2) 63.3%

C. (1) 53.3%

(2) 58.3%

D. (1) 36.1%

(2) 41.1%

Thursday, June 13, 2013 4:26:19 PM 37

NRC Exam

38. Given the following plant conditions:

-The reactor is at 37% RTP

-RCP breaker A trips Which ONE (1) of the following completes the statement?

Reactor Trip Breakers RTA and RTB (1) lights will be illuminated. The conditions for P-8 (2) satisfied.

A. (1) red (2) are B. (1) green (2) are C. (1) red (2) are NOT D. (1) green (2) are NOT Thursday, June 13, 2013 4:26:19 PM 38

NRC Exam

39. Given the following conditions:

- Plant is at 100% RTP

- All equipment is in normal alignment

- An electrical fault results in a loss of power to Instrument Bus 3 Which ONE (1) of the following describes SI Pump response if an AUTO SI actuation occurs before Instrument Bus 3 is recovered?

A. SI Pumps A and B start.

B. SI Pumps B and C start.

C. Only SI Pump A starts.

D. Only SI Pump C starts.

Thursday, June 13, 2013 4:26:19 PM 39

NRC Exam

40. Given the following plant conditions:

-Tavg is 547° F

-RCS Pressure is 2235 psig

-A loss of offsite power occurs

-One minute later a large break LOCA occurs Which ONE (1) of the following completes the statement below?

The FINAL CV Recirculation fans start (1) seconds after both trains of the f sequencers start.

A. (1) 30 (2) Blackout B. (1) 35 (2) Blackout C. (1) 30 (2) Safety Injection D. (1) 35 (2) Safety Injection Thursday, June 13, 2013 4:26:19 PM 40

NRC Exam

41. Which ONE (1) of the following combinations of Containment Heat removal equipment will require immediate entry into LCO 3.0.3?

A. Both HVH trains inoperable.

B. Three Containment HVH units inoperable.

C. Two Containment Spray Pumps inoperable.

D. One Containment Spray Pump and one HVH train inoperable.

Thursday, June 13, 2013 4:26:19 PM 41

NRC Exam

42. Given the following plant conditions:

-A loss of offsite power and a reactor trip has occurred

-Two minutes later APP-007-F5, SD AFW PMP LO DISCH PRESS TRIP alarms and remains locked in

-The pump has been verified to be coasting down locally due to an overspeed trip Which ONE (1) of the following correctly completes the statements below?

SDAFW Pump Steam Shutoff Valves, V1-8A, V1-8B, and V1-8C should be (1) at this time. The BOP operator is required to (2) closure of SDAFW Pump Discharge Valves, V2-14A, V2-14B, and V2-14C.

A. (1) open (2) verify automatic B. (1) open (2) perform manual C. (1) closed (2) verify automatic D. (1) closed (2) perform manual Thursday, June 13, 2013 4:26:19 PM 42

NRC Exam

43. Given the following plant conditions:

-The Plant is at 50% RTP perform post outage power ascension.

-FCV-478, FRV A, develops an air leak at the valve operator and the valve starts to slowly drift in the close direction

-The air leak increases slowly for 5 minutes and then the air line completely separates EOP-E-0, REACTOR TRIP OR SAFETY INJECTION AOP-010, MAIN FEEDWATER/CONDENSATE MALFUNCTION Which ONE (1) of the following completes the statements below?

Prior to the line separation, FCV-478 controller output will (1) . After the line separates the crew will (2) lAW AOP-01 0.

A. (1) rise (2) stabilize A S/G Level using the FRV Bypass Valve B. (1) lower (2) stabilize A S/G Level using the FRV Bypass Valve C. (1) rise (2) trip the Reactor and Go To EOP-E-0 D. (1) lower (2) trip the Reactor and Go To EOP-E-0 Thursday, June 13, 2013 4:26:19 PM 43

NRC Exam

44. Given the following plant conditions:

-The plant is in Mode 3

-The SDAFW Pump is under clearance

-MDAFW Pump B is running Subsequently,

-A line break occurs between FCV-1425, MDAFW PUMP B FCV and V2-20B, AFW HDR SECTION valve

-MDAFW Pump B trips on overcurrent due to runout through line break

-The break has been isolated using single valve isolation Which ONE (1) of the following identifies the S/Gs available to be fed by the remaining AFW Pump?

A. S/GAONLY B. S/GBONLY C. S/GsA, B, andC D. S/GsAandBONLY Thursday, June 13, 2013 4:26:19 PM 44

NRC Exam

45. Given the following plant conditions:

-The Plant is at 100% RTP

-A fault has isolated the Startup Transformer Which ONE (1) of the following completes the statements below?

This results in a loss of (1) . Emergency Diesel Generator (2) starts and loads.

A. (1) Spent Fuel Pit Cooling Pump A and Rod Drive MG Set B (2)A B. (1) Spent Fuel Pit Cooling Pump A and Rod Drive MG Set B (2) B C. (1) Spent Fuel Pit Cooling Pump B and PZR Heater Back-up Group A (2)A D. (1) Spent Fuel Pit Cooling Pump B and PZR Heater Back-up Group A (2) B Thursday, June 13, 2013 4:26:19 PM 45

NRC Exam

46. Given the following plant conditions:

-A LOCA and a Loss of Offsite Power have occurred

-Both battery chargers that were in service are tripped Which ONE (1) of the following completes the statements below?

Given the accident above, A and B Batteries are designed to last for a MAXIMUM of (1) . Assuming battery load remains constant, battery current will (2) as terminal voltage lowers.

A. (1) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (2) lower B. (1) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (2) rise C. (1) 30 minutes (2) lower D. (1) 30 minutes (2) rise Thursday, June 13, 2013 4:26:19 PM 46

NRC Exam

47. Which ONE (1) of the following completes the statements below?

The purpose of the Emergency Diesels is to provide emergency power in the event of a loss of (1) . The design time to energize the associated bus is within (2) seconds.

A. (1) offsite power (2) 10 B. (1) offsite power (2) 15 C. (1) allA/C power (2) 10 D. (1)allA/Cpower (2) 15 Thursday, June 13, 2013 4:26:19 PM 47

NRC Exam

48. De-energizing which ONE (1) of the following Motor Control Centers will cause a loss of Diesel Air Compressor A?

A. MCC-5 B. MCC-6 C. MCC-9 D. MCC-1O Thursday, June 13, 2013 4:26:19 PM 48

NRC Exam

49. Given the following plant conditions:

-The reactor is at 100% RTP

-The crew is performing a containment vacuum relief

-R-12, CV AIR OR PLANT STACK, NOBLE GAS, alarms V12-12, CVVAC RELIEF V12-13, CVVAC RELIEF APP-036-D7, AREA MONITOR HI RAD APP-036-D8, PROCESS MONITOR HI RAD Which ONE(1) of the following completes the statements below?

The crew would expect to see (1) annunciator flashing. They would also see (2) go shut.

A. (1) APP-036-D7 (2) VI 2-12 & VI 2-13 only B. (1) APP-036-D8 (2)V12-12 & V12-13 only C. (1) APP-036-D7 (2) V12-12, V12-13 & the CV Intake Damper D. (1) APP-036-D8 (2) V12-12, V12-13 & the CV Intake Damper Thursday, June 13, 2013 4:26:19 PM 49

NRC Exam

50. Given the following plant conditions:

-The reactor is at 100% RTP

-The following radiation monitor alarms are received:

-R-15, CONDENSER AIR EJECTOR GAS MONITOR

-R-19A, S/G A RADIATION MONITOR

-R-24A, S/G A LEAKAGE MONITOR

-All other radiation monitors are normal Which ONE (1) of the following describes the valves that CLOSE in response to these indications?

A. FCV-1930A, S/G A Blowdown Isolation Valve V1-31, Blowdown Isolation Valve to Catch Basin B. V1-31, Blowdown Isolation Valve to Catch Basin RCV-1 0549, Condensate Polisher Discharge to Catch Basin C. FCV-1930A, S/G A Blowdown Isolation Valve FCV-1933B, SIG A Blowdown Sample Isolation Valve D. FCV-1933B, S/G A Blowdown Sample Isolation Valve RCV-1 0549, Condensate Polisher Discharge to Catch Basin Thursday, June 13, 2013 4:26:19 PM 50

NRC Exam

51. Given the following plant conditions:

-The reactor is at 100% RTP

-Service Water pumps A & C are running

-Service Water Header pressure is 42 psig and stable as indicated on P1-1616 and P1-1684

-Both CCW Heat Exchangers are in service

-Main Generator Exciter Cooler air discharge temperature is 145° F and rising slowly TCV-1673, TURBINE LUBE OIL TEMP CONTROL VALVE TCV-1 650, HYDROGEN COOLER TEMP CONTRL VALVE Which ONE (1) of the following completes the statements below?

lAW OP-903, Service Water System, the maximum allowable Main Generator Exciter Cooler air discharge temperature is LU °F. To restore Main Generator Exciter Cooler air discharge temperature the crew will first A. (1) 140 (2) start D Service Water pump B. (1) 188 (2) start D Service Water pump C. (1) 140 (2) raise the setpoint for TCV-1673 and TCV-1650 D. (1) 188 (2) raise the setpoint for TCV-1 673 and TCV-1 650 Thursday, June 13, 2013 4:26:19 PM 51

NRC Exam

52. Given the following plant conditions:

-MCC-5 de-energizes due to the supply breaker tripping open

-During the transient, a turbine trip occurs and the South Service Water header pressure decreases to 28 psig V6-16B, SW SOUTH HEADER SUPPLY TO TURBINE BUILDING V6-16C, SW ISOLATION TO TURBINE BUILDING Which ONE (1) of the following completes the statement below?

TWO (2) minutes after the turbine trip, V6-16B is (1) and V6-16C is (2)

A. (1) closed (2) closed B. (1) closed (2) open C. (1) open (2) open D. (1) open (2) closed Thursday, June 13, 2013 4:26:19 PM 52

NRC Exam

53. Given the following plant conditions:

-APP-002-F7, INSTR AIR HDR LO PRESS alarms

-P1-I 702, INST AIR HEADER PRESS, dropped from 100 psig to 0 psig in less than 10 seconds

-Pressurizer Level is 54% and STABLE

-Steam Generator Narrow Range Levels are 52% and STABLE

-The reactor is at 100% RTP and STABLE AOP-017, LOSS OF INSTRUMENT AIR EOP-E-0, REACTOR TRIP OR SAFETY INJECTION Which ONE (1) of the following completes the statements below?

APP-002-F7 alarm setpoint is (1) psig. The crew is required to (2)

A. (1) 60 (2) initiate action to repair the transmitter and monitor Instrument Air pressure locally B. (1) 85 (2) initiate action to repair the transmitter and monitor Instrument Air pressure locally C. (1) 60 (2) trip the reactor and implement AOP-017 and EOP-E-0 concurrently D. (1) 85 (2) trip the reactor and implement AOP-01 7 and EOP-E-0 concurrently Thursday, June 13, 2013 4:26:19 PM 53

NRC Exam

54. Which ONE (1) of the following completes the statements below?

Instrument Air Compressor A and B cylinder water jackets are cooled by (1)

Water. Flow is to the cylinder water jackets when the air compressors are shutdown.

A. (1) Service (2) maintained B. (1) Component Cooling (2) maintained C. (1) Service (2) isolated D. (1) Component Cooling (2) isolated Thursday, June 13, 2013 4:26:19 PM 54

NRC Exam

55. Which ONE (1) of the following completes the statements below?

To ensure the LCO is met for the Personnel Airlock as required by Technical Specification 3.6.2 in MODES (1) the personnel hatch doors are (2) to ensure only one door is open at any time.

A. (1) 1-4 only (2) administratively controlled B. (1) 1-4,and6 (2) administratively controlled C. (1) 1-4 only (2) physically interlocked D. (1) 1-4,and6 (2) physically interlocked Thursday, June 13, 2013 4:26:19 PM 55

NRC Exam

56. Given the following plant conditions:

-The reactor was at 100% RTP.

-Subsequently, the reactor was tripped due to a Steam Line leak on the 72 inch Main Steam Header

-All MSIV5 are stuck full open.

-All AFW Pumps failed to start

-FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, has been entered

-S/G Wide Range levels are all at 3%

-CETC Temperature indicates 505°F with a subcooling of 115°F

-Safety Injection has been manually initiated Which ONE (1) of the following completes the statement below?

Safety injection (1) injecting into the core. In order to initiate Bleed and Feed, the crew will FIRST try to open (2)

A. (1)is (2) all head vents B. (1)isNOT (2) all head vents C. (1)is (2) both PZR PORVs D. (1) is NOT (2) both PZR PORVs Thursday, June 13, 2013 4:26:19 PM 56

NRC Exam

57. Given the following plant conditions:

-The crew is lowering power from 100% to 90% RTP lAW OP-105, MANEUVERING THE PLANT WHEN GREATER THAN 25% POWER

-All PZR heaters are energized

-B Charging pump is in manual

-C Charging pump is in AUTO

-LT-460, CH II PRZR LEVEL, fails low Which ONE (1) of the following completes the statements below?

The PZR Backup heaters are (1) . Because of this failure, C charging pump speed will (2)

A. (1)off (2) lower B. (1)on (2) lower C. (1)off (2) rise D. (1)on (2) rise Thursday, June 13, 2013 4:26:19 PM 57

NRC Exam

58. Given the following plant conditions:

-The reactor is at 100% RTP

-The crew has entered AOP-001, MALFUNCTION OF REACTOR CONTROL SYSTEM, for a dropped rod in Control Bank D

-They are at the step to place the Lift Coil Disconnect Switch for the dropped rod to the OFF position Which ONE (1) of the following completes the statements below?

The operator performing this step will go to the (1) . This is done to allow operators to (2)

A. (1) Rod Control Room (2) withdraw the dropped rod B. (1) back of the RTGB (2) withdraw the dropped rod C. (1) Rod Control Room (2) control flux during the downpower D. (1) back of the RTGB (2) control flux during the downpower Thursday, June 13, 2013 4:26:19 PM 58

NRC Exam

59. Given the following plant conditions:

-The crew is in FRP-C.1, RESPONSE TO INADEQUATE CORE COOLING Which ONE (1) of the following completes the statements below?

From the ICCM Panel, the crew will monitor (1) lAW FRP-C.1. The minimum temperature at which core damage has occurred with RCPs running is (2)

A. (1)RTDs (2) 1200°F B. (1)RTDs (2) 2300°F C. (1)CETCs (2) 1200°F D. (1)CETCs (2) 2300°F Thursday, June 13, 2013 4:26:19 PM 59

NRC Exam

60. Which ONE (1) of the following is the power supply for HVE-4, CV AIR IODINE REMOVAL EXHAUST FAN?

A. MCC-5 B. MCC-6 C. MCC.-9 D. MCC-10 Thursday, June 13, 2013 4:26:19 PM 60

NRC Exam

61. Given the following plant conditions:

-One AO is in containment verifying a valves position

-R-1 1, CV AIR & Plant Vent Particulate, alarms

-The crew has entered AOP-005, RADIATION MONITORING SYSTEM Which ONE (1) of the following completes the statement below?

The OAC will place the VLC switch to the (1) position and will then Hold the CV EVACUATION HORN for (2) seconds lAW AOP-005.

A. (1) OVERRIDE (2) 5 B. (1) OVERRIDE (2) 15 C. (1)EMERG (2) 5 D. (1)EMERG (2) 15 Thursday, June 13, 2013 4:26:19 PM 61

NRC Exam

62. Given the following plant conditions:

-The reactor is at 100% RTP

-APP-036-B6, SPENT FUEL PIT LO LEVEL, alarm comes in

-AO reports that APP-036-B6 is a valid alarm Which ONE (1) of the following completes the statements below?

APP-036-B6 alarm setpoint is (1) . The crew will fill the Spent Fuel Pit level using waterfrom the (2)

A. (1)35ft (2) RWST B. (1) 36ft, 2.5 inches (2) RWST C. (1) 35ft (2) Demineralized Water System D. (1) 36ft, 2.5 inches (2) Demineralized Water System Thursday, June 13, 2013 4:26:19 PM 62

NRC Exam

63. Given the following plant conditions:

-The reactor is at 100% RTP

-The CAD reports a steam leak near the Main Steam Isolation Valves

-The following indications are noted in the Control Room:

Tavg is lowering

-Steam flow and feed flow have risen

-Power Limit Warning alarm on ERFIS has been received

-Reactor power is 100.3% and slowly rising Which ONE (1) of the following completes the statements below?

The time in core life that will result in the smallest reactivity excursion is (1) . The Reactor is required to be operated at less than or equal to (2) MW thermal lAW OMM-001-2, SHIFT ROUTINES AND OPERATING PRACTICES.

A. (1)BOL (2) 2300 B. (1)BOL (2) 2339 C. (1) EOL (2) 2300 D. (1)EOL (2) 2339 Thursday, June 13, 2013 4:26:19 PM 63

NRC Exam

64. Given the following plant conditions:

-The plant is performing a power ascension and is at 8% RTP Which ONE (1) of the following completes the statements below?

The REACTOR TRIP BLOCK P-7 status light will4Wiiate when (1) Power Range Nis read above 10%. One of the Reacto(Trips that this enables is (2)

A. (1) 2/4 /2.3 (2) PZR High Level B. (1)3/4 (2) PZR High Level C. (1)2/4 (2) PZR High Pressure D. (1)3/4 (2) PZR High Pressure Thursday, June 13, 2013 4:26:19 PM 64

NRC Exam

65. Which of the following discharge to the Reactor Coolant Drain Tank?

A. Charging pump seals B. RCV-609, CC SURGE TANK VENT C. CVC-203 A/B, LETDOWN RELIEF VALVES D. CVC389, EXCESS LETDOWN DIVERSION Thursday, June 13, 2013 4:26:19 PM 65

NRC Exam

66. Which ONE (1) of the following completes the statements below?

lAW OPS-NGGC-1 000, FLEET CONDUCT OF OPERATIONS, a plant announcement will be made for the starting of (1) motors. The announcement will include (2)

A. (1)all (2) only the applicable motor B. (1) only large (2) only the applicable motor C. (1)all (2) the applicable motor and its switchgear D. (1) only large (2) the applicable motor and its switchgear Thursday, June 13, 2013 4:26:19 PM 66

NRC Exam

67. Given the following plant conditions:

-The plant is in MODE 6 for refueling operations

-Core alterations are in progress Which ONE (1) of the following completes the statements below?

lAW LCO 3.9.2, NUCLEAR INSTRUMENTATION, (1) source range neutron flux monitor(s) shall be OPERABLE. NI-51 and NI-52, (2) capable of providing audible indication inside CV.

A. (1)one (2) are B. (1)two (2) are C. (1)one (2) are NOT D. (1)two (2) are NOT Thursday, June 13, 2013 4:26:19 PM 67

NRC Exam

68. Which ONE (1) of the following completes the statements below?

SI Accumulator Pressure is checked during (1) . A deviation of greater than (2) of full scale during a channel check is used as the OOS limit.

A. (1) OST-020, SHIFTLY SURVEILLANCES (2) 7.5%

B. (1) OST-020, SHIFTLY SURVEILLANCES (2)5%

C. (1) OST-021, DAILY SURVEILLANCES (2)5%

D. (1) OST-021, DAILY SURVEILLANCES (2) 7.5%

Thursday, June 13, 2013 4:26:19 PM 68

NRC Exam

69. Which ONE (1) of the following people can be selected to be an Infrequently Performed Test or Evolution (IPTE) Manager lAW OPS-NGGC-1315, CONDUCT OF INFREQUENTLY PERFORMED TESTS OR EVOLUTIONS?

A. Lead Test Performer B. A Control Room Supervisor C. The on-duty Shift Manager D. The Manager, Shift Operations Thursday, June 13, 2013 4:26:19 PM 69

NRC Exam

70. Inside Work Control, the following conditions were found:

-Removable surface contamination is 1500 dpm/cm 2

-Radiation levels are 3 mrem/hr at 30cm Which ONE (1) of the following identifies the minimum postings for the Work Control area?

A. Radiation area only B. Contamination area only C. no postings necessary D. A contamination and radiation area Thursday, June 13, 2013 4:26:19 PM 70

NRC Exam

71. Which ONE (1) of the following radiation monitors is located in the Auxiliary Building hallway above the Station Air receiver?

A. R-18 (Waste Disposal System liquid effluent)

B. R17 (Component Cooling Water)

C. R-16 (Containment Fan Coolers)

D. R-9 ( Letdown line area)

Thursday, June 13, 2013 4:26:19 PM 71

NRC Exam

72. Given the following conditions:

-An RNP Mechanic, previously employed by VC Summer, has been assigned to repack a valve

-The mechanics current yearly dose from VC Summer was 1 Rem TEDE

-The mechanic has received no dose from RNP

-Projected dose rate in the area is 500 mR/hr What is the MAXIMUM time that the mechanic can work on the valve before reaching the Annual Administrative Dose Limit lAW DOS-NGGC-0004, ADMINISTRATIVE DOSE LIMITS?

A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> C. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> D. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Thursday, June 13, 2013 4:26:20 PM 72

NRC Exam

73. The RD has determined that for the safety of the reactor and the plant, a reactor trip and initiation of Safety lnjection(SI) is necessary. He has announced it to the CRS, however, it has been several seconds and the CRS has not responded.

Which ONE (1) of the following completes the statement below?

The RD should (1) then (2) lAW OPS-NGGC-1 000, FLEET CONDUCT OF OPERATIONS.

A. (1) wait for confirmation from the CRS (2) trip the reactor and initiate SI B. (1) wait for confirmation from the CRS (2) initiate SI C. (1) trip the reactor, verify it is tripped (2) initiate SI D. (1) trip the reactor and initiate SI (2) perform immediate action steps Thursday, June 13, 2013 4:26:20 PM 73

NRC Exam

74. Given the following plant conditions:

-A SMALL fire is reported near the A and B Auxiliary boilers Which ONE (1) of the following completes the statement below?

lAW OMM-003, FIRE PROTECTION PRE-PLANS/UNIT NO. 2, the fire brigade must attack this fire with (1) and the fire brigade is required to protect the (2)

A. (1) a portable fire extinguisher or hose stream (2) Primary Air Compressor B. (1) a portable fire extinguisher or hose stream (2) Steam Driven AFW pump C. (1) hose stream only (2) Primary Air Compressor D. (1) hose stream only (2) Steam Driven AFW pump Thursday, June 13, 2013 4:26:20 PM 74

NRC Exam

75. The Plant is at 100% RTP when the following events occur:

2115 - Power is lost to all Control Room annunciators 2120 An Unusual Event is declared

-

2125 The Emergency Notification form is complete and the SM directs you to

-

make the state and county notifications 2130 -A reactor trip occurs and the SM declares an Alert 2135 The SM completes a new Emergency Notification form and directs you to

-

make the state and county notifications Which ONE (1) of the following indicates the latest time the state and counties must FIRST be notified?

A. 2130 B. 2135 C. 2140 D. 2145 Thursday, June 13, 2013 4:26:20 PM 75

NRC Exam

76. Given the following plant conditions:

-Plant is at 100% RTP

-PCV-455C, PZR PORV, indicates open

-PT-444, CH I PRZR PRESS, is 2100 psig and lowering

-PT-445, CH II PRZR PRESS, is 2100 psig and lowering

-The OAC manually shuts PCV-455C

-I&C determines that the PCV-455C cant be controlled automatically AOP-019, MALFUNCTION OF RCS PRESSURE CONTROL AOP-025, RTGB INSTRUMENT FAILURE Which ONE (1) of the following completes the statements below?

The crew has entered (1) . lAW ITS, PCV-455C (2) OPERABLE.

A. (1)AOP-019 (2) is NOT B. (1) AOP-025 (2) is NOT C. (1)AOP-019 (2) is D. (1)AOP-025 (2) is Thursday, June 13, 2013 3:33:37 PM 77

NRC Exam

77. Given the following plant conditions:

-The plant is at 98% RTP

- AOP-O1 0 is entered due a leak in FW Heater 4B

-OPS Manager has chosen to repair the leak on line AOP-O1O, MAIN FEEDWATER/CONDENSATE MALFUNCTION OP-407, HEATER DRAINS AND VENTS Which ONE (1) of the following completes the statements below?

The CRS will direct the OAO to use (1) for the specific steps to remove the required FW Heaters from service. The crew (2) have to reduce power for this evolution.

A. (1) OP-407 (2) will NOT B. (1)AOP-010 (2) will NOT C. (1)OP-407 (2) will D. (1)AOP-010 (2) will Thursday, June 13, 2013 3:33:37 PM 78

NRC Exam

78. Given the following plant conditions:

-A Station Blackout has occurred from 100% RTP

-The crew is performing actions of EPP-1, LOSS OF ALL AC POWER

-Immediate actions are complete

-A Charging pump is running

-Offsite power is available to re-energize the SUT

-APP-009-B5, MAIN TRANSF PHASE TRIP, alarm is in OP-603, ELECTRICAL DISTRIBUTION OP-603-3, RESETTING HIGH IMPEDANCE FAULT TRIPS 86P, GENERATOR LOCKOUT RELAY, PRIMARY 86BU, GENERATOR LOCKOUT RELAY, BACKUP Which ONE (1) of the following completes the statement below?

lAW EPP-1, the CRS will direct the use of OP- (1) to restore power. APP-009-B5 is an indication that the (2) lockout needs to be reset.

A. (1)603 (2) 86P B. (1) 603-3 (2) 86P C. (1)603 (2) 86 BU D. (1) 603-3 (2) 86 BU Thursday, June 13, 2013 3:33:37 PM 79

NRC Exam

79. Given the following plant conditions:

-The reactor is at 100% RTP

-B Charging pump is running in Manual

-C Charging pump is running in AUTO

-A reactor trip occurs

-The following indications are seen:

-See next page for references Which ONE (1) of the following completes the statements below?

Based off the indications above, C Charging pump is (1) . The crew will transition from EOP-E-0 to (2) to EPP-27.

A. (1) running (2) EOP-ES-0.1 B. (1)tripped (2) EOP-ES-0.1 C. (1) running (2) EPP-7 D. (1) tripped (2) EPP-7 Thursday, June 13, 2013 3:33:37 PM 80

NRC Exam CHARGING PUMP C i:

SELECT I JIlL fri hR TURII-Oll CODE OP hAY 09.2013 ON-LINE

hI: 55: 19 TEMP Ti HOuRS J 21 DAYS TREJiD DTSPLHY DC (fiN/flAX)

NH F I I t:a4 gI i:e, t:27 I iio i:

POIIIT to DESCRIPTIOII TREIIO CLIRREIIT LOU HI6H LIFIE VALUE QIJAL ALARI1 ALARI1 APU3O22H OC 11CC 1 VOLT 132.10 132.10 OK 123.00 1O.00 1

flPU3O 1 fl 2 BC occ-n CURREFIT -8.8 -6. OK 0.0 1000.0 0P03(F)3fl BC 11CC- B VOLT nan nan ROER 123. 00 1)iJ. 00 DER 0.0 .0 F1.FAST LEFT F2LEFT F3-MEIILJ FA1TE1IPLATE C.. CAHO cREoHT F6..FHST RIOHT COIISOLE.IIORI1AL P At flOUEt C

Thursday, June 13, 2013 5:15:24 PM 81

NRC Exam

80. Given the following plant conditions:

-Plant is at 40% RTP

-The Load Dispatcher reports that grid voltage is degrading

-12:00:00 on 1/1/13, 480V Bus E2 voltage was reduced to 400V

-12:00:20 on 1/1/13, there were no changes to the electrical lineup

-1 2:30:00 on 1/1/1 3, grid voltage was restored Which ONE (1) of the following completes the statements below?

The B EDG is designed to start under this condition when (1) degraded voltage relays sense their setpoint. If B EDG cannot be restored to service, the latest time the plant can be in MODE 3 is (2) lAW applicable LCO.

(REFERENCE PROVIDED)

A. (1) 1/2 (2) 18:00:20 on 1/7/13 B. (1) 1/2 (2) 18:00:20 on 1/8/13 C. (1)2/3 (2) 18:00:20 on 1/7/13 D. (1)2/3 (2) 18:00:20 on 1/8/13 Thursday, June 13, 2013 3:33:37 PM 82

NRC Exam

81. Given the following plant conditions:

-The crew is implementing FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK

-CST is intact, level is 15% and lowering OP-402, AUXILIARY FEEDWATER SYSTEM FRP-H.1, ATTACHMENT 2, SERVICE WATER BACKUP TO MDAFW PUMPS Which ONE (1) of the following completes the statements below?

The correct order in which the crew will attempt to restore Feed Flow to S/Gs is AFW, (1) . If the CST level reaches 10%, the CRS will direct the use of (2) to align Service Water as a backup to the AFW pumps.

A. (1) Main Feedwater, Condensate (2) OP-402 B. (1) Main Feedwater, Condensate (2) ATTACHMENT 2 C. (1) Condensate, Main Feedwater (2) OP-402 D. (1) Condensate, Main Feedwater (2) ATTACHMENT 2 Thursday, June 13, 2013 3:33:37 PM 83

NRC Exam

82. Given the following plant conditions:

-Unit 2 is raising power from 50% to 100% RTP

-Reactor power is currently at 55% RTP at EOL

-Control Bank D rods are at 171 steps

-30 minutes ago, a 200 gallon dilution to the RCS was performed

-The OAC pulls rods and releases the switch, Tavg and Reactor power steadily rise

-APP-005-E4, DELTA FLUX ALARM, is in

-VCT level has remained stable at 25% for the last 15 minutes Which ONE (1) of the following completes the statements below?

Based on the above conditions, the accident the crew is dealing with is a (1) accident. The basis for the LCO actions to address the Delta Flux Alarm is to (2)

A. (1) uncontrolled rod withdraw (2) limit the amount of axial power distribution B. (1) dilution (2) limit the amount of axial power distribution C. (1) uncontrolled rod withdraw (2) limit the gross radial power distribution D. (1) dilution (2) limit the gross radial power distribution Thursday, June 13, 2013 3:33:37 PM 84

NRC Exam

83. Given the following plant conditions:

-The plant is in MODE 1

-A CV Purge is in progress

-R-14C, PLANT STACK, NOBLE GAS, is OOS

-R-12, CV AIR OR PLANT STACK, NOBLE GAS, fails high Which ONE (1) of the following completes the statements below?

The running CV PURGE EXHAUST UNIT, HVE-IA or HVE-IB will (1) . lAW the ODCM, OFF-SITE DOSE CALCULATION MANUAL, effluent releases (2) continue.

(REFERENCES PROVIDED)

A. (1)trip (2) can B. (1)trip (2) can NOT C. (1)NOTtrip (2) can D. (1) NOT trip (2) can NOT Thursday, June 13, 2013 3:33:37 PM 85

NRC Exam

84. Given the following plant conditions:

-The reactor is at 100% RTP

-The BOP reports R-9 is trending up and currently reads 0.6 R/hr OP-920, RADIATION MONITORING SYSTEM OMM-014, RADIATION MONITOR SETPOINTS Which ONE(1) of the following completes the statements below?

The BOP will verify R-9 setpoint lAW (1) . There (2) an EAL declaration that needs to be entered.

(REFERENCE PROVIDED)

A. (1) OMM-014 (2) is NOT B. (1)OMM-014 (2) is C. (1) OP-920 (2) is NOT D. (1)OP-920 (2) is Thursday, June 13, 2013 3:33:37 PM 86

NRC Exam

85. Given the following plant conditions:

-A Large Break LOCA has occurred

-Neither CV Spray pump started

-CV Pressure has reached 40.5 psig FRP-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK FRP-J.1, RESPONSE TO HIGH CONTAINMENT PRESSURE Which ONE (1) of the following completes the statements below?

The crew will use (1) to mitigate this event. Containment design pressure (2) been exceeded.

A. (1)FRP-P.1 (2) has NOT B. (1)FRP-J.1 (2) has NOT C. (1) FRP-P.1 (2) has D. (1) FRP-J.1 (2) has Thursday, June 13, 2013 3:33:37 PM 87

NRC Exam

86. Given the following plant conditions:

Initial Conditions:

-APP-006-D4, SIG A STM LINE HI FLOW, alarm is in

-APP-006-E4, SIG B STM LINE HI FLOW, alarm is in

-APP-006-F4, S/G C STM LINE HI FLOW, alarm is in

-Steam line pressure is 600 psig Subsequently:

-The crew has transitioned to EPP-16

-AFW flow has been throttled to each S/G

-SIG conditions are now as follows:

A-40% WR level, Pressure is 355 PSIG and rising B-35% WR level, Pressure is 300 PSIG and lowering C-35% WR level, Pressure is 290 PSIG and lowering EOP-E-2, FAULTED STEAM GENERATOR ISOLATION EPP-16, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS Which ONE (1) of the following completes the statements below?

Based off the initial conditions above, the plant (1) received an automatic SI signal. The crew will (2)

A. (1) has NOT (2) remain in EPP-16 B. (1)has (2) remain on in EPP-16 C. (1)has (2) transition to EOP-E-2 D. (1) has NOT (2) transition to EOP-E-2 Thursday, June 13, 2013 3:33:37 PM 88

NRC Exam

87. Given the following plant conditions:

-The plant is in MODE 3

-The crew is currently in EPP-28, LOSS OF ULTIMATE HEAT SINK, for a loss of the intake structure

-CST Level is 8%

-Deepwell Pump D is the only available water supply to MDAFW Pump A OP-402, AUXILIARY FEEDWATER SYSTEM ATTACHMENT 6, DEEPWELL COOLING Which ONE(1) of the following completes the statements below?

lAW EPP-28, total AFW flow to the S/Gs is limited to (1) gpm. The crew will use (2) to align Deepwell Pump D.

A. (1)195 (2) ATTACHMENT 6 of EPP-28 B. (1) 140 (2) ATTACHMENT 6 of EPP-28 C. (1) 195 (2) OP-402 D. (1) 140 (2) OP-402 Thursday, June 13, 2013 3:33:37 PM 89

NRC Exam

88. Given the following plant conditions:

-The plant is in MODE 4

-Battery Charger A is in service

-APP-036-F1O, BATT RM A/B HI/LO TEMP, alarms

-It is determined that Battery As representative cells have an average electrolyte temperature of 65°F 3.8.4, DC SOURCES-OPERATING 3.8.5, DC SOURCES-SHUTDOWN 3.8.6, BATTERY CELL PARAMETERS Which ONE (1) of the following completes the statements below?

Per APP-036-F1 0, the SRO will direct the OAO to verify the (1) is operating.

The SRO is required to enter LCO(s) (2)

A. (1) alternate heater (2) 3.8.5 only B. (1) air conditioning (2)3.8.5 only C. (1) alternate heater (2)3.8.4 and 3.8.6 D. (1) air conditioning (2)3.8.4 and 3.8.6 Thursday, June 13, 2013 3:33:37 PM 90

NRC Exam

89. Given the following plant conditions:

-A plane crashed into the Intake Structure

-The plant was manually tripped

-The SUT tripped

-The CRS has entered EPP-28, EPP-28, LOSS OF ULTIMATE HEAT SINK ATTACHMENT 6, DEEPWELL COOLING ATTACHMENT 7, ESTABLISHING CCW COOLING Which ONE (1) of the following completes the statements below?

The maximum time the crew has to restore cooling to an EDG to preclude adverse effects is (1) minutes. In order to provide cooling to at least one EDG, the CRS will direct ATTACHMENT (2) to be performed.

A. (1)60 (2) 6 B. (1)60 (2) 7 C. (1)40 (2) 6 D. (1)40 (2) 7 Thursday, June 13, 2013 3:33:37 PM 91

NRC Exam

90. Given the following plant conditions:

-A main steam line break inside CV results in a Safety Injection and CV Spray actuation

-EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, has been implemented

-CV pressure is currently 14 psig

-CC-735, THERM BAR OUT ISO, is open SUPPLEMENT A, SAFETY INJECTION COMPONENT ALIGNMENT SUPPLEMENT B, PHASE B AND CV SPRAY COMPONENT ALIGNMENT Which ONE (1) of the following completes the statement below?

Based on current plant conditions, CC-735 (1) in the correct position and the CRS may direct the use of (2) to verify its position.

A. (1)is (2) SUPPLEMENT A B. (1) is NOT (2) SUPPLEMENT A C. (1)is (2) SUPPLEMENT B D. (1) is NOT (2) SUPPLEMENT B Thursday, June 13, 2013 3:33:37 PM 92

NRC Exam

91. Given the following plant conditions:

-APP-004-E4, CV HI PRESS SFGRDITRIP, flashes and is confirmed valid

-The reactor is at 100% RTP

-CETs are 1225°F and rising FRP-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS FRP-C.1, RESPONSE TO INADEQUATE CORE COOLING SACRM-1, SEVERE ACCIDENT CONTROL ROOM MANAGEMENT INITIAL

RESPONSE

Which ONE (1) of the following completes the statements below?

lAW FRP-S. 1, the crew unsuccessfully tried tripping the reactor by opening the (1) . The CRS is required to transition to (2)

A. (1) Generator A & B Circuit Breakers (2) SACRM-1 B. (1) Generator A & B Circuit Breakers (2) FRP-C.1 C. (1) feeder breaker to 480V busses 2B and 3 (2) SACRM-1 D. (1) feeder breaker to 480V busses 2B and 3 (2) FRP-C.1 Thursday, June 13, 2013 3:33:37 PM 93

NRC Exam

92. Given the following plant conditions:

-An approved radioactive liquid waste release is in progress

-Subsequently, R-18, LIQUID EFFLUENT WASTE DISPOSAL, is reading above its alarm setpoint

-The release is still in progress Which ONE(1) of the following completes the statements below?

R-18 reading above the alarm setpoint (1) have terminated the release. Per the ODCM, the release may continue provided (2)

(REFERENCES PROVIDED)

A. (1) should (2) two independent samples are analyzed and two facility staff independently verify the release rate calculations and discharge line valving B. (1) should NOT (2) two independent samples are analyzed and two facility staff independently verify the release rate calculations and discharge line valving C. (1) should (2) the flow rate is estimated at lease once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases D. (1) should NOT (2) the flow rate is estimated at lease once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases Thursday, June 13, 2013 3:33:37 PM 94

NRC Exam

93. Given the following plant conditions:

-The crew has started a gaseous waste release from WGDT C

-ATTACHMENT 10.3, GASEOUS WASTE RELEASE PERMIT-WASTE GAS DECAY TANK, is complete (SEE REFERENCE ON NEXT PAGE)

-During the release, R-14C, PLANT STACK, NOBLE GAS, read 12K cpm Which ONE(1) of the following completes the statements below?

The (1) had to approve the release before it could begin. Based off of ATTACHMENT 10.3, R-14C (2) alarm during the release.

A. (1) E&C Supervisor (2) did NOT B. (1) E&C Supervisor (2) did C. (1)SM (2) did NOT D. (1)SM (2) did Thursday, June 13, 2013 4:26:45 PM 93

___________

_________

ATTACHMENT 10.3 Page 1 of 2 GASEOUS WASTE RELEASE PERMIT WASTE GAS DECAY TANK RELEASE NUMBER; l3o6 SSN: I? DATE: lej This revision is the latest revision availbIe s yen by:

Name (Print) Initial Signature Date PART I: PRE-RELEASE INFORMATION (E&C)

A I B i) D Estimated Relesse Start icy - 1o Waste Gas Decay Tank Date Time (Circle AppropriaLe Letter) Estimated Release Stop Te2&

Date Time Monitor Setpaint Basis (Circle One) CV Purge (Circle One) (NCR 410785)

R-14C CPM EC i) In Senfice Not In ServiCe Maximum WGDT Flow Rate: CX CFM PART II: RADIATION MONITOR INFORMATION (OPS and E&C)

READING R-14C 2

PRIOR (Channel Check) CPM SOURCECHECK 2 E&CINI, 3

SETPOINTV ERF.AT CPM UPDATESTATUSBOARD 4 OPSNI, DURING REL.EASE --

CPM AFTER RELEASE CPM SETPOINTRETURNEDTQ 3 --

CPM STATUS 4

___________

BOARDUPIJATED

__________

__________

__________

__________

_______

OPSINI. --

(N

NRC Exam

94. Which ONE (1) of the following completes the statement below?

The CRS is responsible for conducting a(n) every 45 60 minutes during long lasting events.

A. Crew Update B. Alignment Brief C. Crew Shift Brief D. Plant Status Brief Thursday, June 13, 2013 3:33:37 PM 96

NRC Exam

95. Given the following plant conditions:

- The letdown line has been removed from service and cleared for maintenance to install several new vent valves.

- An approved test procedure has been provided with the work order package to perform the line hydrostatic test following installation.

- A clearance boundary change must be implemented to initiate the system hydrostatic test.

Which ONE (1) of the following completes the statements below?

lAW OPS-NGGC-1 301, Equipment Clearance, each boundary change shall be authorized by (1) . The (2) will provide concurrence for Maintenance personnel to introduce fluids into the clearance boundary for the system hydrostatic test.

A. (1) an SRO (2) WCCSRO B. (1) the CRS only (2) CRS C. (1) anSRO (2) CRS D. (1) the CRS only (2) WCCSRO Thursday, June 13, 2013 3:33:38 PM 97

NRC Exam

96. Given the following plant conditions:

- Two trains of RHR are OPERABLE

- RCS is at 135°F and has been drained to -30 inches standpipe level for RCP seal replacement

- Maintenance has requested that both CV Personnel Hatch doors be opened to allow cables and hoses to be routed through the doors to support maintenance activities Which ONE (1) of the following completes the statements below?

lAW OMM-033, IMPLEMENTATION OF CV CLOSURE, CV Personnel Hatch doors can be opened provided CV closure can be implemented within (1) hours. The hoses and cables can be routed through the hatch provided (2) for removal.

A. (1)0.5 (2) the hoses and cables have quick disconnects B. (1)4 (2) the hoses and cables have quick disconnects C. (1)0.5 (2) dedicated personnel are stationed inside the CV with tools needed D. (1)4 (2) dedicated personnel are stationed inside the CV with tools needed Thursday, June 13, 2013 3:33:38 PM 98

NRC Exam

97. Given the following plant conditions:

- A Site Area Emergency has been declared due to a LOCA outside containment

- All Emergency Response Organization facilities are staffed and functional

- The TSC has determined that the leak can be isolated

- Expected exposure to isolate the leak is> 5 Rem TEDE

- An operator has been briefed and is awaiting approval for entry into the Auxiliary Build ing to isolate the leak Which ONE (1) of the following completes the statement below?

Authorization of the exposure (1) be delegated to the Radiological Control Director. If authorized, the operator is allowed to receive up to (2) REM for this entry.

A. (1) can (2) 10 B. (1) can (2) 25 C. (1) can NOT (2) 10 D. (1) can NOT (2) 25 Thursday, June 13, 2013 3:33:38 PM 99

NRC Exam

98. Given the following plant conditions:

-A Large Break LOCA has occurred

-Containment pressure is 32 psig and rising

-HVH-1 and HVH-2 have tripped

-Containment Sump level is rising

-R-32A, CV High P , has the current indication:

Which ONE (1) of the following completes the statement below?

Based on the information provided a (1) must be declared due to (2)

(References Provided)

A. (1) Site Area Emergency (2) Loss of the Reactor Coolant AND Fuel Cladding Barriers B. (1) General Emergency (2) Loss of the Reactor Coolant, Fuel Cladding AND Containment Barriers C. (1) Site Area Emergency (2) Loss of the Reactor Coolant Barrier AND a Potential Loss of the Containment Barrier D. (1) General Emergency (2) Loss of the Reactor Coolant AND Fuel Cladding Barrier AND Potential Loss of the Containment Barrier Thursday, June 13, 2013 5:13:02 PM 98

NRC Exam

99. Given the following plant conditions:

-The crew is in EPP-28, LOSS OF ULTIMATE HEAT SINK, for a total loss of the intake structure

-Subsequently a loss of all AC power occurs Which ONE (1) of the following completes the statement below?

The CRS (1) transition to EPP-1, LOSS OF ALL AC POWER, because (2)

A. (1)will NOT (2) EPP-28 contains actions to deal with a loss of all AC power B. (1) will (2) EPP-1 contains actions to deal with a loss of all AC power C. (1) will (2) EPP-1 has priority over all other EPP procedures D. (1)will NOT (2) EPP-28 has priority over all other EPP procedures Thursday, June 13, 2013 3:33:38 PM 101

NRC Exam 100. Given the following plant conditions:

- Today at 0100 LCO 3.4.13, RCS OPERATIONAL LEAKAGE, was entered due to an 8 gpm leak from a crack on the spray line penetration weld at the PZR

- The crew commenced a shutdown at 0200

- The plant reached MODE 3 at 0800 Which ONE (1) of the following completes the statement below?

Notifications must be made to the NRC by (1) and (2)

(REFERENCES PROVIDED)

A. (1) 0300 (2) 0800 B. (1) 0600 (2) 0800 C. (1) 0300 (2) 1200 D. (1) 0600 (2) 1200 You have completed the test!

Thursday, June 13, 2013 3:33:38 PM 102

Table of Contents for Provided References

-LCO 3.8.1, AC Sources-Operating

-LCO 3.4.13, RCS Operational LEAKAGE

-ODCM Table 2.6-1, Radioactive Liquid Effluent Monitoring Instrumentation

-ODCM Section 3.10, Radioactive Gaseous Effluent Monitoring Instrumentation

-AP-30, NRC Reporting Requirements, Attachments 11.1, IMMEDIATE(One Hour) Notifications to the NRC, 11.2, FOUR Hour Notifications to the NRC, 11.3, EIGHT Hour Notifications to the NRC

-EAL Hot Conditions Board

ANSWER KEY REPORT for NRC Exam Test Form: 0 Answers ID Points Type 0 008 AK2.03 1 1.00 MCS D 2 009 EK1.02 1 1.00 MCS D 3 011 EG2.4.21 1 1.00 MCS D 4 022 AK3.07 1 1.00 MCS A 5 025 AK2.02 1 1.00 MCS D 6 027 AA1.02 1 1.00 MCS C 7 029 EA1.02 1 1.00 MCS C 8 038 EK3.08 1 1.00 MCS B 9 040 AA2.02 1 1.00 MCS D 10 054 AK1.01 1 1.00 MCS A 11 055EG2.4.21 1 1.00 MCS B 12 056AA1.151 1.00 MCS D 13 057 AA2.19 1 1.00 MCS A 14 058 AK1.01 1 1.00 MCS A 15 077 AK3.02 1 1.00 MCS C 16 WE/04EK2.1 1 1.00 MCS D 17 WE/OS G2.4.6 1 1.00 MCS D 18 WE/li EA2.2 1 1.00 MCS B 19 028 AA2.03 1 1.00 MCS B 20 032 AA1.0i 1 1.00 MCS B 21 033 AG2.2.22 1 1.00 MCS B 2 060 AK3.02 1 1.00 MCS B 3 067 AK1.02 1 1.00 MCS B 24 068 AG2.2.37 1 1.00 MCS B 25 076 AA1.04 1 1.00 MCS A 26 W/E08 EK1.2 1 1.00 MCS A 27 WIEIO EK2.2 1 1.00 MCS A 28 003 A1.O9 1 1.00 MCS C 29 003 K4.04 1 1.00 MCS B 30 004 K3.08 1 1.00 MCS A 31 004 K6.26 1 1.00 MCS C 32 005 A2.O4 1 1.00 MCS D 33 006A4.O22 1.00 MCS A 34 006 K5.1O 1 1.00 MCS B 35 007 K5.02 1 1.00 MCS A 36 008 A2.03 1 1.00 MCS C 37 OIOK1.082 1.00 MCS D 38 012A3.O41 1.00 MCS C 39 013 K2.O1 1 1.00 MCS C 40 022 A3.O1 1 1.00 MCS D 41 026 G2.2.42 1 1.00 MCS C 42 039 A4.04 1 1.00 MCS D 43 059 A2.12 1 1.00 MCS C 44 061 K6.02 1 1.00 MCS D 5 062 K3.O1 1 1.00 MCS B 46 063 A1.O1 2 1.00 MCS B Thursday, June 13, 2013 5:20:47 PM

ANSWER KEY REPORT for NRC Exam Test Form: 0 Answers ID Points Type 0 47 06402.1.27 1 1.00 MCS A 48 064 K2.01 1 1.00 MCS A 49 073 A4.01 1 1.00 MCS D 50 073 K4.01 I 1.00 MCS C 51 076A1.021 1.00 MCS B 52 0761(2.011 1.00 MCS D 53 078 G2.4.50 1 1.00 MCS B 54 078K1.041 1.00 MCS C 55 103 K4.04 1 1.00 MCS C 56 002 A2.04 1 1.00 MCS D 57 011 K6.03 I 1.00 MCS A 58 01402.1.302 1.00 MCS D 59 017 A1.01 1 1.00 MCS C 60 027 K2.01 1 1.00 MCS B 61 029A4.041 1.00 MCS D 62 033 K4.01 1 1.00 MCS D 63 035 K5.01 I 1.00 MCS B 64 015 A3.02 1 1.00 MCS A 65 068 1(1.072 1.00 MCS D 66 02.1.14 1 1.00 MCS D 67 02.1.40 1 1.00 MCS D 8 02.2.12 1 1.00 MCS B

) 02.2.71 1.00 MCS D 70 G2.3.14 1 1.00 MCS B 71 02.3.15 1 1.00 MCS C 72 02.3.41 1.00 MCS C 73 02.4.12 1 1.00 MCS C 74 0 2.4.26 2 1.00 MCS B 75 02.4.39 1 1.00 MCS B 76 008 AG2.1.7 SRO 1 1.00 MCS C 77 054 AG2.4.35 SRO 1 1.00 MCS C 78 055 EA2.06 SRO 1 1.00 MCS A 79 058 AG2.1.19 SRO I 1.00 MCS A 80 077 AA2.07 SRO 1 1.00 MCS D 81 W/E 05 EA2.2 SRO 1 1,00 MCS A 82 001 AA2.05 SRO 2 1.00 MCS A 83 060 AG2.2.40 SRO 1 1.00 MCS B 84 061 AA2.02 SRO 1 1.00 MCS B 85 W/E14 EG2.2.38 SRO I 1.00 MCS B 86 012G2.1.2OSRO1 1.00 MCS C 87 061 02.4.20 SRO 1 1.00 MCS C 88 063 A2.02 SRO 1 1.00 MCS C 89 076 A2.01 SRO 1 1.00 MCS C 90 103 A2.03 SRO 2 1.00 MCS D I 001A2.13SRO1 1.00 MCS A 92 068 A2.04 SRO 1 1.00 MCS A Thursday, June 13, 2013 5:20:47 PM 2

ANSWER KEY REPORT for NRC Exam Test Form: 0 Answers ID Points Type 0 93 071 G2.4.46 SRO 1 1.00 MCS D 94 G2.1.38 SRO 1 1.00 MCS D 95 G2.2.13 SRO 1 1.00 MCS C 96 G2.2.18 SRO 1 1.00 MCS A 97 G2.3.13 SRO 1 1.00 MCS C 98 G2.3.5 SRO 1 1.00 MCS A 99 G2.4.23 SRO 1 1.00 MCS A 100 G2.4.30 SRO 1 1.00 MCS B SECTION 1 ( 100 items) 100.00 Thursday, June 13, 2013 5:20:47 PM 3

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