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{{#Wiki_filter:Question:        1 Initial Conditions:
* Reactor at 50% and stable.
* Tave at 558 °F, Tref at 558 °F.
Current Conditions:
* Median Tave fails such that Tave is 4.0 °F lower than Tref.
* Rod Control is placed in manual 30 seconds after the failure occurs.
Which ONE of the following states:
: 1) The direction of rod motion immediately before the rods were placed in manual.
: 2) The number of steps the control rods must be moved to restore the control rods to their previous rod height (prior to the Tave failure).
A. 1) Out.
: 2) 16.
B. 1) Out.
: 2) 20.
C. 1) In.
: 2) 16.
D. 1) In.
: 2) 20.
 
________
Question:          2 Initial plant conditions:
* Unit 1 is at 100% power.
* Currently performing a test of Reactor Trip breaker A per 1 -PT-8. 1, Rx. Protection Logic testing.
* An automatic reactor trip signal occurs.
* Reactor Trip and Reactor Trip Bypass breaker position following the Trip are shown below.
* No operator actions have been taken.
REACTOR TRiP BKR RTA
[  REACTOR TRIP J    EKR RTB CONTROL ROD SOUD STATE POWER SUPPLY ROD CONTROL RTSYPASS                        RTBYPASS SKR BYA                          BKR BYB Which ONE of the following correctly completes the following statements:
: 1) The Reactor trip and Bypass breakers                            correctly.
: 2) With respect to the breaker under test, the operator is required to A.      1) did not
: 2) initiate a manual reactor trip per 1-E-0, Reactor Trip or SI B.      1) did not
: 2) locally trip the breaker per 1-FR-S.1, Response to Nuclear Generation/ATWS C.      1) did
: 2) initiate a manual reactor trip per 1-E-0, Reactor Trip or SI D.      1) did
: 2) locally trip the breaker per 1-FR-Si, Response to Nuclear Generation/ATWS
 
Question:        3 Initial Conditions:
* The Unit is in Cold Shutdown with the Team preparing to start the first RCP in accordance with 1 -OP-RC-001, Starting and Running Any Reactor Coolant Pump.
* Vacuum assist was unavailable during RCS Loop fill.
The following sequence of events occur:
* 0900, C RCP started for RCS Vent.
* 0902, C RCP secured due to low seal Differential Pressure.
* 0933, C RCP started for RCS Vent.
* 0938, C RCP secured due to low seal Differential Pressure.
* 1012, C RCP started for RCS Vent.
* 1027, C RCP secured due to the loss of both seal injection and thermal barrier flow.
Which ONE of the following states:
: 1)    What is the earliest time the fourth start of the C RCP may be attempted, in accordance with 1-OP-RC-001?
: 2)    When restoring seal injection and thermal barrier cooling to an RCP seal, which is restored first?
A. 1) 1128.
: 2) Thermal Barrier.
B. 1) 1128.
: 2) Seal Injection.
C. 1) 1058.
: 2) Thermal Barrier.
D. 1) 1058.
: 2) Seal Injection.
 
Question:      4 Unit I was operating at 100% operation when a failure occurred causing Letdow temper n        ature to rise.
Which of the following describes:
: 1) At what temperature will the Letdown divert valve, 1-CH-TCV-1 143 divert to the VCT?
: 2) What is the reason for this action?
A.      1) 145°F.
: 2) Protect Ion Exchanger resin from damage due to high Letdown line temp.
B.      1) 145°F.
: 2) Mitigate negative reactivity caused by boron release from Demins.
C.      1) 130°F.
: 2) Protect Ion Exchanger resin from damage due to high Letdown line temp.
D. 1) 130°F.
: 2) Mitigate negative reactivity caused by boron release from Demins.
 
Question:        5 Initial Conditions:
* Unit 1 is being cooled down to Cold Shutdown, with RHR in service.
Which ONE of the following states:
: 1) The power supply to 1-RH-MOV-1 700, RHR Inlet MOV.
: 2) The pressure transmitter that supplies the signal for the open (maximum pressure) interlock for 1-RH-MO V-i 700.
A. 1) iHi-2S-8C.
: 2) i-RC-PT-i402-1, RCS Pressure Wide Range.
B. 1) iHl-2S-SC.
: 2) i-RC-PT-i403, RCS Pressure Narrow Range.
C. 1) 1A1-1E-4B.
: 2) i-RC-PT-1402-i, RCS Pressure Wide Range.
D. 1) iAi-1E-4B.
: 2) i-RC-PT-i403, RCS Pressure Narrow Range.
 
Question:      6 Given the following conditions:
* RCS temperature is 175°F.
* RCS pressure is 305 psig.
* The PRZR is solid.
* Charging flow control is in manual.
* RHR is in service, with the A RHR heat exchanger and 1-RH-P-lA in service.
* 1-RH-FCV-1 605, RHR H/X bypass, is in AUTO.
The A RHR heat exchanger suddenly develops a 150 gpm tube leak.
With NO Operator actions, which ONE of the following identifies the effect of this malfunction on:
: 1) Flow through the RHR pump.
: 2) RCS pressure.
A. 1) Flow remains the same.
: 2) Pressure lowers.
B. 1) Flow remains the same.
: 2) Pressure rises.
C. 1) Flow rises.
: 2) Pressure rises.
D. 1)Flowrises.
: 2) Pressure lowers.
 
_________
Question:        7 Initial Conditions:
* A Large Break LOCA is in progress.
* The Team is performing 1-E-0, Loss of Reactor or Secondary Coolant.
* The BOP operator is performing 1-E-0, Attachment 1, System Alignment Verification and is on Step 12 CHECK SI FLOW.
Current Conditions:
* RCS pressure is 30 psig.
* HHSI and LHSI pump amps are listed below:
PUMP        AMPS 1-CH-P-1A  70 1-.CH-P-1B  69 1-CH-P-1C  30 1-SI-P-lA  265 1-SI-P-lB    275 Which ONE of the following describes the status of the HHSI and LHSI pumps upon compl etion of , step 12.
: 1) The HHSI pump that will be secured is
: 2) The number of LHSI pumps that will be running is A. 1) l-CH-P-1C
: 2) two B. 1) 1-CH-P-1A
: 2) two C. 1) 1-CH-P-1C
: 2) one D. 1) 1-CH-P-1A
: 2) one
 
Question:        8 Given the following:
* Unit 1 operating at 100%.
* The crew experienced a spurious SI signal.
* Following the SI the Charging pump suction valves have the following positions:
o  1 -CH-MOV-1 11 5B,  CHG  pump suction from RWST; CLOSED.
o  1.-CH-MOV-1115C,    CHG  pump suction from VCT; OPEN.
o  1 -CH-MOV-1 11 5D,  CHG  pump suction from RWST; OPEN.
o  1-CH-MOV-1115E,    CHG  pump suction from VCT; CLOSED.
* All other auto SI actions occur as designed.
In the given alignment, the VCT _(1)          a source of HHSI flow, and the RWST _(2)            a source of HHSI flow.
A. 1)is              2)isnot B. 1)isnot          2)is C. 1)is              2)is D. 1) is not        2) is not
 
Question:        9 Initial Conditions:
* 1-RC-PT-1445, PRZR PRESS CNTRL, failed high.
* The Team has completed the Immediate Actions of 1-AP-31 .00, Increasing or Decrea sing RCS Pressure.
Current Conditions: (2 minutes later):
* PRT Pressure is 12 psig and stable.
* Annunciator 1C-F7, PRZR RELIEF TK HI PRESS is Lit.
Which ONE of the following identifies:
: 1) The PRZR PORV that was closed is_____
: 2) The procedure that will direct returning the PRT to normal pressure is________
A. 1) 1-RC-PCV-1455C
: 2) 1-AP-31.00, Increasing or Decreasing RCS Pressure B. 1) 1-RC-PCV-1456
: 2) ARP 1C-F7, PRZR RELIEF TK HI PRESS C. 1) 1-RC-PCV-1455C
: 2) ARP 1C-F7, PRZR RELIEF TK HI PRESS D. 1) 1-RC-PCV-1456
: 2) 1 -AP-31 .00, Increasing or Decreasing RCS Pressure
 
_____
__
Question:          10 Initial Conditions:
* Unit 1 is at 100%.
* Tave is at 573 °F.
* Pressurizer Safety Valve 1-RC-SV-1551A inadvertently fails partially open.
* S/G B NR level channel 1, 1-FW-Ll-1484, fails high immediately following the Reactor trip.
* 30 seconds later SI automatically actuates.
Current Conditions (10 minutes later)
* Plant is stabilized with Tave at 552 °F and RCS pressure at 1910 psig.
* Pressurizer vapor space temperature is steady at 630 °F.
* Main Feedwater pumps have tripped, all Feed Reg valves are closed, and all Feed Reg Bypass valves are closed.
Which of the following describes:
: 1) The Main Feed pumps trip after the_______
: 2) The Feed Regulating Bypass valves initially closed due to the A. 1) reactor trip, but before the safety injection
: 2) reactor trip coincident with low Tave B. 1) reactor trip, but before the safety injection
: 2) safety injection C. 1) safety injection
: 2) reactor trip coincident with low Tave D. 1) safety injection
: 2) safety injection
 
Question:        11 Initial Conditions:
* Unit 1 reactor operating at 100% power.
* A tube leak develops in 1-CC-E-1A, A CCHX.
Which ONE of the following states:
: 1) The effect on CC Surge Tank level.
: 2) The CW lines that supply SW to the CCHXs.
A. 1) Rise.
: 2) lA/C.
B. 1) Lower.
: 2) IBID.
C. 1) Rise.
: 2) iB/D.
D. 1) Lower.
: 2) lA/C.
 
_____
Question:        12 Initial Conditions:
* Unit 1 and Unit 2 operating at 100%.
* LOCA on Unit 1 causing Reactor trip and SI.
* Charging pump, 1-CH-P-1B started then tripped on lockout, 1-CH-P-IA and C are running.
* Containment pressure is 16.2 psia and slowly rising.
Current conditions:
* RO reports loss of 1 H 4160 V bus. EDG 1 did not start.
* RCS pressure is 1082 psig and slowly lowering.
* CETC is 528 °F and stable.
Which of the following states:
: 1) RCP Trip criteria is
: 2) In accordance with 1-E-1 Basis; the reason RCP5 are tripped is to A. 1) Met
: 2) Prevent excessive depletion of RCS inventory B. 1) Not met
: 2) Minimize heat input C. 1) Not met
: 2) Prevent excessive depletion of RCS inventory D. 1) Met
: 2) Minimize heat input
 
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Question:      13 A ground has developed on DC Panel 1-2, causing 1-.RC-SOy-biB-I and 1-RC-SOV-1 O1B-2, PRZR Vent Valves, to fail open.
Which ONE of the following states:
: 1) The Master Pressure controller output will
: 2) The PRZR Vent Valves discharge to the A. 1) rise
: 2) Primary Vent Pot B. 1) rise
: 2) Reactor Cavity C. 1) lower
: 2) Primary Vent Pot D. 1) lower
: 2) Reactor Cavity
 
Question:          14 Initial conditions:
* Unit 1 is at 100% power.
* The breaker for 1 -SI-MOV-1 885C, LHSI Pump A Recirc Valve, was found open, and could not be reclosed.
* A Large Break LOCA occurs.
Current conditions:
* The RWST level is 12.5%.
* The Team is currently at 1-ES-i .3, Transfer to Cold Leg Recirculation; step 5, Align SI System for Recirc.
Which ONE of the following identifies:
: 1) Which LHSI pump(s) will automatically align to the RMT mode?
: 2) Per ES-i .3 CAP, after step 5, the operator will monitor for oscillating LHSI pump amps and flow to check for A.        1) Both LHSI pumps.
: 2) RWST <3%
B.      1) ONLY the B LHSI pump.
: 2) sump blockage C.      1) Both LHSI pumps.
: 2) sump blockage D.      i) ONLY the B LHSI pump.
: 2) RWST <3%
 
Question:        15 A loss of off-site power has resulted in the trip of both Units.
* 120 seconds have elapsed since the reactor trip.
Which ONE of the following identifies the Pressurizer heaters energized on Unit 1?
A. None.
B. E Group.
C. E and A Groups.
D. A Group.
 
Question:        16 Given the following:
* Unit 1 is at 100%.
* Power Range N-41 fails HIGH.
* 0-AP-53.00, Loss of Vital Instrumentation/Controls, immediate actions completed.
* Crew is presently performing 1-AP-4.00, Nuclear Instrumentation Malfunction, Attach ment ito place the failed Power range channel in trip.
Which one of the choices below completes the following statements?
: 1) In accordance with 1-AP-4.00, Attachment 1; OP L\T channel 1          have to be placed in trip.
: 2) OP z\T provides protection against A.        1) will
: 2) DNB B.      1) will
: 2) high power density C.      1) will not
: 2) DNB D.      1) will not
: 2) high power density
 
Question:          17 Initial Conditions:
* Unit 1 is heating up per 1-GOP-i .3, RCS Heatup from 345 &deg;F to HSD following a mid-cy cle outage.
* 40,000 gallons were transferred to the RWST from the blender.
* RWST Refrigeration Unit 1A is tagged out for compressor breaker replacement.
* RWST Refrigeration Unit 1 B is in operation.
* Annunciator 1A-C7, RWST HI TEMP has alarmed.
* RWST temperature is 42&deg;F on channel 1 and channel 2; (1-CS-TI-i OOA and bOB).
Current Conditions (5 mm. later)
* Operator reports RWST Refrigeration Unit 1 B has a low oil pressure trip and he is unable to reset. Operator requests maintenance support.
* Unit 1 RWST parameters are as follows:
Temp.          Boron 44&deg;F            2275 ppm In accordance with Tech Specs 3.3.A. 1, RWST; which of the following completes the statem ent.
With the current conditions the RWST LCO temperature limit is _(1), and the RWST Boron LCO limit is _(2)....
A. 1) met
: 2) not met B. 1) not met
: 2) met C. 1) not met
: 2) not met D. 1) met
: 2) met
 
_____
Question:          18 Initial Conditions:
* Unit 1 is at 100% power when a large break LOCA occurs.
* Containment pressure peaks at 45 psia.
Current Conditions:
* The crew is at 1-El, Loss of Reactor or Secondary Coolant, step 17 and is attempting to open 1-lA-TV-i 00.
* The RO reports that Containment pressure is slowly lowering and is as follow s:
o 1-LM-Pl-100A 15 psia.
o 1-LM-Pl-100B 15 psia.
o 1-LM-Pl-100C 14 psia.
o 1-LM-Pl-100D 15 psia.
* 1-Pl-IA-101, CTMT INST AIR, indicates 25 psig.
* The operator has depressed both CLS Train A (B) RESET buttons.
* SI has been reset.
Which one of the following correctly completes the statements below:
: 1) After depressing both CLS RESET buttons, CLS          reset.
: 2) When the operator attempts to open 1-IA-TV-i 00, the valve will A.      1) is        2) remain closed B.      1) is not    2) open C.      I) is not    2) remain closed D. 1) is        2) open
 
Question:        19 The reactor is operating at 100% power when the following sequence of events occur:
* Initial D Bank rod height 225 Steps.
* The RO is performing 1-OPT-RX-005, Control Rod Assembly partial Movem ent, for D Control Bank.
* Annunciator G-A6, Rod Cont Sys Urgent Failure is received when Contro Bank l      D begins to move inward.
* Rod Control In-Hold-Out switch placed in Hold.
The following indications are noted by the RO:
* Control  Bank D, Group 1 Step counter indicates 224 Steps.
* Control  Bank D, Group 2 Step counter indicates 222 Steps.
* Control  Bank D, CERPI Group 1 indicates 224 Steps.
* Control  Bank D, CERPI Group 2 indicates 222 Steps.
Which ONE of the following identifies the:
: 1) Power Cabinet affected by the Urgent Failure.
: 2) The procedure that would need to be entered to mitigate the malfunction.
A. 1) Power Cabinet 1BD.
: 2) 0-AP-1 .00, Rod Control System malfunction.
B. 1) Power Cabinet 1BD.
: 2) 0-AP-1 .02, Individual Rod Position Indicators.
C. 1) Power Cabinet 2BD.
: 2) 0-AP-1.00, Rod Control System malfunction.
D. 1) PowerCabinet2BD.
: 2) 0-AP-1.02, Individual Rod Position Indicators.
 
Question:        20 With Unit 1 at 100% power, an inadvertent phase Ill containment isolation occurs. Approximately 15 minutes later, the following RCP temperatures exist:
A RCP
* Upper Motor radial bearing                185&deg;F
* RCP lower bearing Seal Water Temp          215&deg;F
* Stator winding                            285&deg; F C RCP
* Upper Motor radial bearing                180&deg;F
* RCP lower bearing Seal Water Temp          210&deg;F
* Stator winding                              305&deg; F In order to mitigate these plant conditions, the crew will monitor RCP temper atures using (1)          ,then initiate 1-E-0, Reactor Trip or Safety Injection, trip the reactor, and stop (2)
A.      1) 1-AP-15.00, Loss of Component Cooling
: 2) C RCP B. 1) 1-AP-15.00, Loss of Component Cooling
: 2) A RCP C.      1) 1-AP-9.00, RCP Abnormal Conditions
: 2) A RCP D.      1) 1-AP-9.00, RCP Abnormal Conditions
: 2) C RCP
 
Question:        21 Unit 2 initially operating at 100% power, when the following occurs:
* A LOCA outside of CTMT.
* The Reactor is tripped and Safety Injection actuated.
* The RCPs have been tripped due to low RCS subcooling.
* RVLIS Full Range Indicates 42% and stable.
* RCS THOT indicates 650 &deg;F and stable.
* CETCs indicate 660 &deg;F and rising.
Which ONE of the following describes:
: 1) The temperature indication used on the Core Cooling Status tree.
: 2) The status of the Core Cooling Status Tree.
A. 1) CETC temperature.
: 2) Orange.
B. 1) CETC temperature.
: 2) Red.
C. 1)THOT.
: 2) Orange.
D. 1) THOT.
: 2) Red.
 
Question:        22 Unit 2 is performing a Reactor Startup following a forced outage. Shutdo wn banks are fully withdrawn.
During the outage, a substantial amount of work had been performed in the Pressurizer Cubicle in Containment.
Given the following data:
Initial        Condition Parameter                                  Condition        1 Day later PRT Level                                      78%              78%
PRT Pressure                                  6 psig          6 psig PRT Temperature                                82&deg;F            84&deg;F Weighted AVG CTMT Temperature                  972&deg;F            101 5&deg;F A PRZR SV Temperature                        129&deg;F            152&deg;F B PRZR SV Temperature                        140&deg;F            160&deg;F C PRZR SV Temperature                        121&deg;F            149&deg;F PRZR PORV Temperature                          121&deg;F            148&deg;F Shutdown bank CERPI Indication                  No change in CERPI Which ONE of the following states the cause for the changes noted betwee n the Initial Conditions and the Conditions found 1 Day later?
A.      Cubicle Ventilation Damper position change.
B.      CRDM Fan Trips.
C.      B PRZR SV Leaking.
D.      PRZR PORV leaking.
 
Question:        23 Initial Conditions:
* Unit 1 at 50% power and ramping up to 100% in accordance with GOP-i .5, Unit Startup, 2% to Max Allowable Power.
* Rod Control in manual due to hunting in automatic.
Current Conditions:
* Median Tave fails to a stable indication of 550 &deg;F.
* No Operator Actions have been taken.
Which ONE of the following states:
: 1) The Pressurizer level control setpoint is
: 2) The automatic charging low flow limit is A. 1) 24.8%
: 2) 30 gpm B. 1) 25.8%
: 2) 30 gpm C. 1) 24.8%
: 2) 25gpm D. 1) 25.8%
: 2) 25 gpm
 
Question:        24 Unit 2 is operating at 100% power with Chilled CC in service to containment.
* An operator is verifying the Plant Computer System displays and indications are functioning properly using the laptop computer at the Auxiliary Shutdown Panel.
* 2-CD-REF-i, Unit 2 Turbine Building Chiller trips.
Which ONE of the following states:
: 1) Containment partial pressure will
: 2) Containment saturation temperature is sensed at the_______
A. 1) lower
: 2) Containment air recirculation fan discharge B. 1) rise
: 2) Containment air recirculation fan discharge C. 1) rise
: 2) Containment dome D. 1) lower
: 2) Containment dome
 
_____
__
Question:        25 Initial Conditions:
* Unit 1 is in Cold Shutdown, at 190 &deg;F, on RHR, preparing to take the pressu rizer solid.
* A RHR pump is running with the A RHR HX in service.
* A CC pump running on Unit 1; D CC pump running on Unit 2. CC is cross-t ied.
Current Conditions:
* C RSST trips and locks out.
Which ONE of the following states:
: 1) The status ofA RHR pump.
: 2) The              CC pump is running on Unit 1, and the        CC pump is running on Unit 2.
A. 1) Running.
: 2) A; D B. 1) Tripped.
L;
: 2)        C C. 1) Running.
: 2) B; C D. 1) Tripped.
: 2)  ?;
 
Question:        26 Given the following:
* A Large Break LOCA has occurred on unit 1.
* An operator has been assigned to perform 1-E-O, Reactor Trip or SI; Attachment 4, CLS Component verification.
* When checking the valve lineup the operator notices that the red and green light bulbs for 1-SW-MOV-104A, RSHX A SW INLET are NOT lit.
Which one of the following indications does 1 -E-O, Attachment 4 direct the operator use to verify that there is adequate flow through the heat exchanger?
A. 1-SW-MOV-103A, RS HX A&D SW SUPPLY; and 1-SW-MOV-105A, RSHX A SW OUTLET red lights LIT.
B. Annunciator 1A-D6, RS HX 1A RAD MON PP NO FLOW is NOT LIT.
C. Flow indication on 1-SW-Fl-i 06A, RS HX A SW Outlet Flow.
D. 1-SW-P-5A, RS SW Radiation Monitor Sample pump red light is LIT.
 
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_____
__    _
Question:        27 Unit 1 is operating at 100% with the following conditions:
* 1-OPT-RC-10. 0, Computer leak Rate Program has trended a rise in Uniden tified leakage of 0.1 gpm.
* A Containment entry has been performed and the leak has been identified on the A SG Primary manway.
* HP has requested the Unit 1 Iodine filter fans, 1-VS-F-3A and 3B, be placed in service.
Which ONE of the following identifies:
: 1) The operator will place the control switch for the Iodine Filter Fans to to start the fans.
: 2) The Unit 1 Iodine Filter Fans are operated at the Ui Main Control Room panel.
A. 1) Auto
: 2) Ventilation B. 1) Auto
: 2) Post Accident Monitoring C.1)On
: 2) Post Accident Monitoring D. 1) On
: 2) Ventilation
 
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_____
Question:          28 Initial Conditions:
* Unit 1 is at HSD with all RCPs running.
* Preparations for Unit startup are in progress per 1-GOP-1.4, Unit Startup.
* The Master Pressure Controller (MPC) and spray valve controllers are all in auto and set to maintain 2235 psig.
* Pressurizer pressure indicates 2250 psig on 1-RC-Pl-1444, and 1-RC-Pl-144 5.
Current Conditions (60 sec):
* Pressurizer pressure is 2130 psig.
* 1C-B8, PRZR LO PRESS is alarming.
* 1-RC-PC-1444G, PRZR Spray from Loop A, 1-RC-PCV-1455A indicates 100%.
* 1-RC-PC-1444H, PRZR Spray from Loop C, 1-RC.-PCV-1455B indicates 0%.
* 1-RC-PC-1444J, PRZR PRESS Master CNTRL, indicates 0%.
Which ONE of the following identifies:
: 1) The POT setting of the Master Pressure Controller for 2235 psig is
: 2) The expected operator action associated with the failure in accordance with 0-AP-53.00, Loss of Vital Instrumentation/Cont is to place              in manual and close the spray valve.
A. 1) 7.45
: 2) 1-RC-PC-1444G, PRZR Spray from Loop A, 1-RC-PCV-1455A B. 1)6.68
: 2) 1-RC-PC-1444G, PRZR Spray from Loop A, 1-RC-PCV-1455A C. 1)7.45
: 2) 1-RC-PC-1444H, PRZR Spray from Loop C, 1-RC-PCV-1455 D. 1)6.68
: 2) 1-RC-PC-1444H, PRZR Spray from Loop C, 1-RC-PCV-1455
 
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Proposed Question:      29 Given the following:
* Pressurizer level channel transmitter 1-RC-LT-459, Pressurizer Level Protec tion  Channel I, is the upper channel.
* The reference leg of 1-RC-LT-459 develops a slow leak.
Which ONE of the following describes:
: 1) As a result of the reference leg leak, the level indication on 1 -RC-LI-1459 will
: 2) In accordance with D-AP-53.DO, Loss of Vital Instrumentation/Controls, the operator required to isolate letdown for this failure.
A. 1) rise
: 2) is not B. 1) rise
: 2) is C. 1) lower
: 2) is not D. 1) lower
: 2) is
 
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Question:        30 Initial Conditions:
* Unit 1 operating at 100% power.
* Reactor Trip First-out annunciator Ctmt Hi Press.
* Crew is performing 1-E-0, Reactor Trip or Safety Injection, immediate actions.
* Both reactor trip breakers remain closed after E-0 step 1 performed.
Current Conditions:
* An operator has just been dispatched to open reactor trip breakers per 1-FR-S.1, step 8.
* Gamma-Metrics is reading 20%.
* Power Range NI channels are all reading 15%.
* Containment pressure is 22 psia and rising.
Which of the following completes the statements:
: 1) In accordance with 1-E-0, Reactor Trip or SI, Background; if any reactor trip breaker and associated bypass breaker is open, and neutron flux has decreased to less than 5
                                                                            %, the reactor considered tripped.
: 2) In accordance with 1-FR-Si, Response to Nuclear Generation/ATWS; the instrumentation the crew should be using to monitor neutron flux is A. 1) is
: 2) Power Range NI channels B. 1) is not
: 2) Gamma-Metrics C. 1) is
: 2) Gamma-Metrics D. 1) is not
: 2) Power Range NI channels
 
_
Question:        31 Initial Condition:
* Unit 2 Containment pressure has just reached atmospheric.
* The Team is preparing to place Unit 2 Containment on purge using 1-VS-F
                                                                                -58A, in accordance with 2-OP-VS-OO1, Containment Ventilation.
* The Personnel and Equipment Hatches are closed.
Which ONE of the following completes the following statement?
: 1) An allowable configuration would consist of
: 2) The            filter is used in the flowpath.
(REFERENCE PROVIDED)
A. 1) Containment Purge and Fuel Building Exhaust
: 2) CAT II B. 1) Containment Purge Only
: 2) CATI C. 1) Containment Purge and Fuel Building Exhaust
: 2) CATI D. 1) Containment Purge Only
: 2) CATII
 
Question:      32 Given the following:
* Unit 2 is currently stable at 75% power.
* The B Feed Reg Valve demand begins to slowly lower due to an instrument failure.
* Annunciator 2H-G6, STM GEN 1 B LVL ERROR, is Lit.
Which ONE of the following identifies:
: 1) The effect this will have on the indicated power by Instantaneous Calorimetric.
: 2) The procedure used to respond to this event.
A. 1) Lowers.
: 2) 2-AP-21 .00, Loss of Main Feedwater Flow.
B. 1) Rises.
: 2) 2-AP-21 .00, Loss of Main Feedwater Flow.
C. 1) Lowers.
: 2) 0-AP-53.00, Loss of Vital Instrumentation/Controls.
D. 1) Rises.
: 2) 0-AP-53.00, Loss of Vital Instrumentation/Controls.
 
Question:      33 The Operating Team is in E-3, Steam Generator Tube Rupture and has compl eted RCS cooldown and depressurization. CHG pump suction has been aligned to the VCT.
The following Unit conditions exist:
* PRZR level is 35% and slowly rising.
* S/G levels are as follows:
o A S/G is 68% and lowering.
o B S/G is 33% and rising.
o C S/G is 32% and rising.
* RCS pressure is 985 psig.
* S/G pressures are as follow:
o A S/G is 1000 psig and lowering.
o B S/G is 670 psig and rising.
o C S/G is 650 psig and rising.
Which ONE of the following is the MINIMUM actions required to be taken by the Operating Team in accordance with step 36 of E-3?
(REFERENCE PROVIDED)
A. Depressurize RCS and raise CHG flow.
B. Lower CHG flow and depressurize the RCS.
C. Turn on PRZR heaters.
D. Raise CHG flow.
 
Question:      34 Given the following:
* Unit 1 is at 100 % power.
* A complete separation of the Main steamline piping upstream of the MSR Steam Supply to the A & C MSRs (30 pipe) occurs.
Which ONE of the following describes the effect this will have on the...
: 1) Main Feed pumps.
: 2) Main Steam Trip valves.
A. 1) Remain running.
: 2) Remain open.
B. 1)Trip.
: 2) Remain open.
C. 1) Remain running.
: 2) Close.
D. 1)Trip.
: 2) Close.
 
Question:        35 Initial Conditions:
Unit 1 operating at 100% power.
* A Steam line in Unit 1 alleyway ruptures.
* Station Service buses are lost on swap-over to Reserve Station Service Transf ormers following a manual reactor trip.
* Individual MSTV close switches on Benchboard fail to operate.
* MSTV Emergency close switch on Vertical Board fails to close the MSTV s.
Which one of the following states:
: 1) The redundant MSTV Emergency Close Switch, is located on the Appen dix R panel in
: 2) Operation of this switch              the MSTV close SOVs.
A. 1) Unit 1 ESGR
: 2) Energizes B. 1) Unit 1 ESGR
: 2) Deenergizes C. 1) Unit 2 ESGR
: 2) Energizes D. 1) Unit 2 ESGR
: 2) Deenergizes
 
Question:        36 Unit 1 is placing the Unit on-line in accordance with 1-OP-TM-001, Turbine  - Generator Startup to 20%
- 25% Turbine Power.
* Steam Dumps are in Auto in steam pressure mode.
* Reactor Power has been raised to 8%.
* P-7 NIS POWER RANGE AND TURBINE POWER < 10% is LIT.
* When the second Generator output breaker, OCB-G1T240 is closed, Annun ciator iF-El, GEN BACKUP LOCKOUT REL TRIP, comes in due to a fault.
Which one of the following correctly describes the effect this will have on:
: 1) The reactor.
: 2) Main Generator output breakers.
Reactor                  Main Gen output breakers A. trip                      trip open after 30 seconds B. not trip                  trip open after 30 seconds C. trip                      trip open immediately D. not trip                  trip open immediately
 
____
Proposed Question:      37 Initial Conditions:
* The team was performing 1-E-0 in response to a faulted steam generator outside containment.
* Upon transition from 1-E-0, the STA reported a red path on HEAT SINK.
* The team has entered 1-FR-Hi, Loss of Secondary Heat Sink.
Current Conditions
* SG levels are A- 0% WR, B- 13% WR, C- 14% WR (all lowering).
* RCS Thot 640&deg;F and rising.
* Pressurizer level 80% and rising
* Pressurizer pressure 2345 psig and rising.
* 1-RC-PCV-1455C was cycling open/close and is now open.
Which ONE of the following states:
: 1) In accordance with 1 -FR-H. 1, Continuous Actions Page, RCS Bleed and Feed      required.
: 2) What is the reason for the Pressurizer PORV remaining open?
A. 1)is not
: 2) RCS expansion due to Loss of Heat sink.
B. i)is
: 2) Pressurizer fill due to safety injection.
C. i)is
: 2) RCS expansion due to Loss of Heat sink.
D. i)isnot
: 2) Pressurizer fill due to safety injection.
 
_____ _____
_________
Question:        38 Initial Conditions:
* Unit 1 operating at 100% power.
* A SGTR occurs on the A SG, the reactor is tripped and safety injection actuated.
* The Team has completed the Rapid Cooldown of I -E-3, Steam Generator Tube Rupture.
* The Air Ejector discharge has been re-aligned to Containment.
Current Conditions:
* The A SG faults inside of Containment.
* Hi and Hi-Hi CLS have actuated.
Which ONE of the following states:
: 1) The position of 1-SV-TV-102A, AE DISCH TO CTMT SFGD TV, is
: 2) The position of 1-SV-TV-102, AE DISCH TO CTMTTB TV, is A. 1) open
: 2) open B. 1) closed
: 2) closed C. 1) closed
: 2) open D. 1) open
: 2) closed
 
Question:    39 ECA-O.O, Loss of all AC Power, Step 24, directs the operator to:
Depress urize all Intact SGs to 300 psig Which ONE of the following describes the reason for stopping the pressure reduction at 300 psig?
A. Prevent losing pressurizer level.
B. Minimize inventory loss out of RCP seals.
C. Prevent voiding in the Reactor Vessel upper head.
D. Prevent SI Accumulator Nitrogen into the RCS.
 
_____
Question:        40 Initial Conditions:
* Unit 1 at 100%
* A transient causes the following annunciators to alarm:
o 1 K-B8, UPS SYSTEM 1 B TROUBLE.
o 1C-Bi, RCP lB CC RETURN LO FLOW.
o 1 E-G4, RX TRIP CH-2 PRZR LO PRESS.
Current Conditions:
* The non-licensed operator dispatched reports the red INVERTER SUPPLYING LOAD light is NOT lit for UPS lB-i.
* Indication on 1-FW-FCV-1488 (B FRV Controller) is:
o Auto Light NOT LIT.
 
o Manual Light NOT LIT.
* The control room team is currently performing actions per 1 K-B8, UPS System 1 B Trouble.
Which one of the following describes:
: 1) B S/G feed flow          be controlled by using the pushbuttons on the FRV controller.
: 2) The Abnormal Procedure that should be utilized is A.      1) can not
: 2) 1-AP-1 0.04, Loss of Vital Bus IV B.      1)can
: 2) 1-AP-i 0.02, Loss of Vital Bus II C.      1)cannot
: 2) 1-AP-10.02, Loss of Vital Bus II D.      1)can
: 2) 1-AP-1 0.04, Loss of Vital Bus IV
 
Question:      41 Which ONE of the following breakers, if open, will cause a Vital Bus UPS Static Switch to shift to the alternate source?
A. Battery Charger AC Input.
B. Battery Charger DC Output.
C. Inverter DC Input.
D. Battery Bus DC Input.
 
Question:      42 Unit 1 is currently at 60% power and is performing a startup.
1-FW-P-1B, B Main Feed Pump, is running.
Shortly after starting 1-FW-P-1A, A Main Feed Pump, the operator observes the Main Feed Pump tripping.
Which ONE of the following conditions could have caused 1-FW-P-1A, A Main Feed Pump trip?
to A. Feed pump Lube oil pressure at 8 psig.
B. C Station Service Bus voltage at 68%.
C. Feed flow    < 3000 gpm and Recirc valve, 1 -FW-FCV-i 50A not fully open.
D. Feed pump Suction pressure at 430 psig.
 
Question:      43 Given the following:
Power from the associated rack in the relay room, to the A FRV controller, 1-FW-FCV-1478 is lost.
With the conditions stated, which of the following answers the questions listed below:
: 1) What is the effect on the output of the controller?
: 2) Can this controller be controlled from the Main Control Room?
A. 1) Shift to manual and output will remain the same as prior to loss of power.
: 2) Yes.
B. 1) The output of the controller will raise to 100% demand.
: 2) Yes.
B. 1) The output of the controller will raise to 100% demand.
: 2) No.
D. 1) Shift to manual and output will remain the same as prior to loss of power.
: 2) No.
 
Question:      44 Given the following:
* An accidental gaseous radwaste release has occurred in the Waste Gas Decay Tank Room.
* A Site Area Emergency has been declared due to dose at the site boundary of 200 mRem/hr.
* Radiation protection has determined that radiation dose level in the room is 1,000 mRem/hr.
A Surry Power Station worker assigned to enter the room has a current year-to-date TEDE of 700 mRem.
The MAXIMUM total time the worker is allowed RCA access, to perform the work, with NO extensions is        hour(s)?
A. 0.50 B. 1.00 C. 1.85 D. 2.30
 
Question:      45 The team is performing 1-E-0, Reactor Trip or Safety Injection, with plant conditions as follows:
* Containment pressure is 27 psia and rising slowly.
* A SIG parameters o Pressure- 650 psig and lowering slowly.
o Level- 57% WR and lowering slowly.
* B SIG parameters o Pressure 120 psig and lowering rapidly.
o Level- 15% WR and lowering rapidly.
* C SIC parameters o Pressure 630 psig and lowering slowly.
o Level- 56% WR and lowering slowly.
* Pressurizer level 0%.
* Pressurizer pressure 1200 psig and lowering.
* RCS Tave- 512 &deg;F and lowering at a rate of 120 &deg;FIhr.
Which ONE of the following states the minimum required AFW flow to the S/Cs in accord ance with E-0, Reactor Trip or Safety Injection, Attachment 8?
A. A SIG- 100 gpm; B S/G- 100 gpm; C S/G-100 gpm.
B. A S/G- 175 gpm; B SIC- 0 gpm; C S/G- 175 gpm.
C. A S/G- 60 gpm; B SIG- 60 gpm; C SIG- 60 gpm.
D. A S/G- 225 gpm; B S/C- 0 gpm; C SIG- 225 gpm.
 
Question:        46 In accordance with 1-AP-21.01, Response to AFW Check Valve Backleakage, which ONE of the following identifies:
: 1) The temperature on an AFW pump casing where the pump is considered vapor bound.
: 2) Which of the AFW pumps is aligned and cooled FIRST if all AEW pumps are found to be vapor bound?
A. 1) 200&deg;F.
: 2) Motor Driven.
B. 1) 200&deg;F.
: 2) Turbine Driven.
C. 1) 165&deg;F.
: 2) Motor Driven.
D. 1) 165&deg;F.
: 2) Turbine Driven.
 
Question:        47 Initial Conditions:
Unit 1 A DC Bus is lost due to a fault, causing a reactor trip.
Current Conditions: (11 minutes following the reactor trip)
A Large Break LOCA occurs on Unit 1.
The Team decides to locally start 1-CS-P-lA, A CS Pump.
Which ONE of the following identifies:
: 1) The red breaker position indicating light          be used by the control room team to identify that 1-CS-P-lA has been successfully started.
: 2) 1-CS-P-lA breaker, 1-EP-BKR-14H5,                have overcurrent trip protection.
A. 1) can
: 2) does not B. 1) can
: 2) does C. 1) cannot
: 2) does D. 1) cannot
: 2) does not
 
_____
_ _____
__
Question:        48 Initial Conditions:
* Unit 1 is operating at 100%.
* 1-SW-P-i CA, CHG PUMP SW PUMP, is running in HAND, 1-SW-P-lOB, CHG PUMP SW PUMP is in Auto.
* 1-CH-P-1C, CHARGING PUMP is running.
* 1 D-G5, SW OR CC PPS DISCH TO CHG PPS LO PRESS has just alarmed.
Current Conditions:
* Reactor Operator reports the following:
o 1-SW-P-bA has tripped, and i-SW-P-lOB remains in standby.
o Highest reading Charging pump bearing temperature is 179&deg;F and rising.
Which ONE of the following describes:
: 1) The Reactor Operator can monitor Charging pump SW flow on the
: 2) 0-AP-1 2.00, Service Water Abnormal, states that the affected Charging pump should be secured once bearing temperature exceeds a minimum of A. 1) Vertical board        2)195&deg;F B. 1) PCS                    2)185&deg;F C. 1)PCS                    2)195&deg;F D. 1) Vertical board        2)185&deg;F
 
__________
Question:      49 Given the following conditions:
* Unit 1 tripped from 100% power due to loss of on-site and off-site power.
* The team is performing 1-ECA-0.0, Loss of all AC Power.
* The AAC EDG has not been loaded on an emergency bus.
Which ONE of the following identifies:
: 1) The power source for Unit 1 Annunciator System is
: 2) The Black Battery supplies the A. 1) A Station Battery
: 2) Seal Oil Backup Pump B. 1) B Station Battery
: 2) Emergency Oil Pump C. 1) A Station Battery
: 2) Emergency Oil Pump D. 1) B Station Battery
: 2) Seal Oil Backup Pump
 
Question:      50 Which one of the following supplies the DC control power to #1 EDG output breaker, 1 -EP-BKR-1 5H3?
A. A DC bus.
B. B DC bus.
C. Black battery DC bus.
D. #1 EDG DC system.
 
Question:    51
* O-VSP-C8, Fire Detected, has alarmed with Unit 1 ESGR indicated on the fire display panel.
* The BOP has dispatched an operator to investigate Unit 1 ESGR for a fire.
Which ONE of the following identifies:
: 1) The maximum time limit for the operator to report fire status.
: 2) The reason for this time limit in accordance with O-VSP-C8.
A. 1) 5 minutes.
: 2) Ensure adequate time for EAL classification and transmission, if required.
B. 1) 5 minutes.
: 2) Prompt response is necessary to prevent significant damage.
C. 1) 3 minutes.
: 2) Ensure adequate time for EAL classification and transmission, if required.
D. 1) 3 minutes.
: 2) Prompt response is necessary to prevent significant damage.
 
________
____
Question:          52 Initial Conditions
* Both units at 100% power.
* The Control Room is evacuated due to a Limiting Main Control Room Fire.
* All actions per 0-FCA-001, Limiting MCR Fire were taken prior to evacuation.
Current Conditions (20 minutes later)
* Operator dispatched to perform 0-FCA-1 1.0, Remote Monitoring.
* Operator reports that Unit 1, Neutron flux indicators are reading as shown below:
Operator reports the following additional        NEUT FLUX      NEUT FLUX 1-NM-NFI-190A2 nformation:                                                  1-1iMMFI-190B2 10          CO
* 1-NM-NFI-190A2 has been steady at presentvalueforlast5 minutes.
* 1-NM-NFI-190B2 has lowered from 1 x iO to present value over last 5                            R      102 minutes.                                            io S
P O
10&deg;
                                                                              .7 p      10 10I 5 17e4          375.7 Unit Supervisor directs the operator to switch 1 -NM-NFl-i 90A & B to the alternate power supply using the Appendix R switch.
Which of the following describes:
: 1) The Nuclear Instrument indication at the Remote Monitoring panel                as expected.
: 2) The location of the alternate power App R switch for 1-NM-NFl-i 90A & B is located in the A.      1) is not
: 2) Cable Tray Room Unit 2 B.      i)is
: 2) Cable Tray Room Unit 2 C.      1)isnot
: 2) Emergency Switchgear Room Unit 2 D.      1)is
: 2) Emergency Switchgear Room Unit 2
 
Question:        53 Both Units are operating at 100% power.
Which ONE of the following water sources is collected directly into the High/Low Level Liquid Waste Tanks prior to transfer to the SRF?
A. Laundry Drains.
B. Contaminated Drain Tank.
C. Auxiliary Building sump pump discharge.
D. VCT Drain.
 
Question:      54 Given the following:
* Unit 1 is at 100%, Unit 2 is in a Refueling Shutdown.
* l-GW-RM-130A, Rad Monitor Process Vent Particulate indication spiked high causing the following alarms:
o 0-RMA-C5, Process Vent Rad Mon Trbl.
o 0-RMA-C6, Process Vent Part Alert I Hi.
Which ONE of the following describes the automatic plant response?
A. 1-IA-TV-lOlA, and 1-IA-TV-biB, Unit 1 Containment Instrument Air compressor suctions will swap to outside air.
B. i-CV-P-1A, and i-CV-P-i B, Unit 1 Containment vacuum pumps will trip.
C. i-SV-TV-103, Air Ejector Discharge to Vent-Vent Trip valve will automatically close.
D. i-GW-FCV-160, Unit 1 vacuum pump discharge valve, will automatically close.
 
Question:      55 Unit 2 is shutdown and has been borated to CSD boron concentration in preparation for Cooldown to CSD for a Refueling outage.
Chemistry has notified the Team that the RCS crud burst has been initiated.
Which ONE of the following describes:
: 1) The FIRST Radiation monitor that will detect the increased RCS Activity caused by the crud burst.
: 2) Which CVCS filter is monitored for differential pressure during the crud burst cleanup?
A. 1) Letdown Radiation monitor.
: 2) Reactor Coolant filter.
B. 1) Letdown Radiation Monitor.
: 2) Letdown filter.
C. 1) Auxiliary Building Control Area Radiation Monitor.
: 2) Reactor Coolant filter.
D. 1) Auxiliary Building Control Area Radiation Monitor.
: 2) Letdown filter.
 
Question:      56 Given the following:
* Unit 1 and Unit 2 are both operating at 100%.
* You are preparing for a Performance Test of Charging Pump SW pump, 1-SW-P-bA Appendix R controls.
* An operator needs to be stationed locally at 1-SW-P-i OA to observe the pump, and a second operator at the Appendix R controls for 1-SW-P-1OA to start and stop the pump.
The Charging Pump SW pump, 1-SW-P-iDA is located inside          (1), and the Appendix R controls for i-SW-P-bA are located inside Unit 1(2)          room.
A. 1) MER 4            2) Emergency Switchgear B. 1) MER 4            2) Cable Vault C. 1) MER 3            2) Cable Vault D. 1) MER 3            2) Emergency Switchgear
 
Question:    57 Which ONE of the following states:
: 1) The minimum canal level per Tech Spec 3.14, Circulation and Service Water Systems.
: 2) The channel coincidence required to cause BC SW isolation?
A. 1) 23.5 feet.
: 2) 2/4 Channel.
B. 1) 23.5 feet.
: 2) 3/4 Channels.
C. 1) 23.0 feet.
: 2) 2/4 Channels.
D. 1) 23.0 feet
: 2) 3/4 Channels.
 
Question:        58 A severe thunderstorm has caused perturbations on the grid. 0-AP-1 0.18 has been entered due to grid instabilities Initial Conditions:
* Unit 1 is at 100% power, Unit 2 is shutdown.
* The A and B Voltage regulators are in AUTO.
* The A Voltage Regulator is in service.
* Power System Stabilizer (PSS) is in service.
* 55 MVARS Out.
Current Conditions:
* The Operator reports a large rise in MVARS (Out).
* The following Annunciators have just alarmed:
o 1J-A8, OVEREXCITATION LIMIT.
o 1J-B7, VREG CHANNEL A LOCAL ALARM.
Which of the following occurs if the A Voltage Regulator is unable to lower Generator voltage in its current mode?
A.      A Voltage Regulator will shift to the V/Hz mode to control voltage. The B channel will remain in standby.
B.      A Voltage Regulator will trip into Emergency Manual. The B channel will automatically assume control.
C.      A Voltage Regulator will trip into Emergency Manual to control voltage.
The B channel will remain in standby.
D.      A Voltage Regulator will shift to the V/Hz mode to control voltage. The B channel automatically assume control.
 
Question:    59 Which ONE of the following describes the operation of Instrument Air compressor 1-IA-C-i when in AUTO?
A. Compressor will start and LOAD when pressure drops to 90 psig.
Compressor will then UNLOAD and LOAD at 105 psig and 95 psig, respectively.
B. Compressor will start and LOAD when pressure drops to 95 psig.
Compressor will then UNLOAD and LOAD at 105 psig and 95 psig, respectively.
C. Compressor will start and LOAD when pressure drops to 100 psig.
Compressor will then UNLOAD and LOAD at 110 psig and 100 psig, respectively.
D. Compressor will start and LOAD when pressure drops to 90 psig.
Compressor will then UNLOAD and LOAD at 110 psig and 100 psig, respectively.
 
Question:        60 Initial Conditions:
* Unit 1 was operating at 100%.
* Auto Reactor Trip and SI initiation occurs due to Large Break LOCA.
* Containment pressure peaks at 45 psia.
Current Conditions:
* RWST level has just reached 60% one minute ago and is lowering.
* Containment pressure is 22 psia and lowering.
Which ONE of the following describes:
: 1)  The status of Recirc Spray pumps.
: 2)  The minimum number of Containment Spray and Recirc Spray pumps needed to cool and depressurize the containment to < 1 psig in <60 minutes following a Design Basis LOCA.
A. 1) Both Outside Recirc Spray pumps are running, Inside Recirc Spray pumps are off.
: 2) One Containment Spray pump and two Recirculation Spray pumps.
B. 1) Both Inside Recirc Spray pumps are running, Outside Recirc Spray pumps are off.
: 2) One Containment Spray pump and two Recirculation Spray pumps.
C. 1) Both Outside Recirc Spray pumps are running, Inside Recirc Spray pumps are off.
: 2) One Containment Spray pump and          Recirculation Spray pump.
D. 1) Both Inside Recirc Spray pumps are running, Outside Recirc Spray pumps are off.
: 2) One Containment Spray pump and one Recirculation Spray pump.
 
Question:      61 The reactor is starting up following a refueling outage, in accordance with 1-GOP-i .8. Unit Startup, HSD to Max Allowable Power.
Which ONE of the following identifies:
: 1) The flowpath used when diluting to critical in accordance with 1-OP-CH-007, Blender Operations.
: 2) The method used to stabilize reactor power at 1 Q  8 amps.
A. 1) DilutetotheVCT Inlet.
: 2) Boration I Dilution.
B. 1) DilutetotheVCT Inlet.
: 2) Rods.
C. 1) Alternate dilute to CH pump suction.
: 2) Boration I Dilution.
D. 1) Alternate dilute to CH pump suction.
: 2) Rods.
 
Question:        62 Given the following conditions:
* Unit 1 is at 12% power.
* The team is currently performing 1-GOP-i .8, Unit Startup, and are checking trip status lights in preparation for blocking Intermediate Range and Power-Range (LO Setpoint) trips.
* The team depresses Intermediate-Range and Power-Range (LO Setpoint) Block pushbuttons.
* Trip Status lights are as follows:
Light#                      Noun name                      As-found          Required A3      P-b    NIS PWR RGE> 10%                            LIT              LIT Ci      NIS PWR RNG LO SP TRIP BLOCKED                  NOT LIT            LIT
* The team notes that status light Ci is in wrong state, checks bulb and finds bulb is good.
Which ONE of the following describes how the plant will respond if the team continues to raise power.
: 1) At what power will the reactor trip?
: 2) What is the coincidence for the reactor trip?
A. 1)35%.        2)1/4.
B. 1)23%.        2)2/4.
C. 1)23%.          2)1/4.
D. 1)35%.        2)2/4.
 
Question:        63 An Operator has been briefed and sent to perform 1-OPT-FW-OO1, Motor Driven Aux Feedwater Pump 1 -FW-P-3A. While placing 1 -FW-P-3A in the proper lineup for the test, a typographical error for a valve mark number is discovered.
Which ONE of the following completes the following statement regarding the actions to be perfomed in accordance with AD-AA-1 00, Technical Procedure Process Control, to address the issue?
After making a pen and ink change, the Operator_(1)..        required to have a supervisor initial and date the correction before proceeding. After completing the OPT, a procedure change request (FIP)
(2)_ required to be processed.
A. (1)is (2) is not B. (1)isnot (2) is not C. (1)isnot (2) is D. (1)is (2) is
 
__________
Question:        64 Unit 1 is currently Shutdown, and making preparations to perform 1 -OPT-ZZ-0O1, ESF Actuation with Undervoltage and Degraded Voltage 1H Bus. This procedure is an ICCE category Ill.
 
In accordance with OP-AA-1 06, Infrequently Conducted or Complex Evolutions, select the answer that correctly completes the following statements.
: 1) Specific criteria for terminating the test and contingency plans for unexpected occurrences required per Attachment 2 of OP-AA-1 06.
: 2) The          is specifically responsible for the safe operation of the station during performance of the test.
A. 1) is
: 2) Senior Operations Manager B. 1) is not
: 2) Shift Manager C. 1) is not
: 2) Senior Operations Manager D. 1) is
: 2) Shift Manager
 
Question:      65 Given the following:
* Unit 1 is operating at 100% power.
* A Subatmospheric Containment Entry is to be made in accordance with VPAP-01 06, to identify the source of a step change in Unidentified leakage of +0.4 gpm.
* The Shift Manager has entered Action Level 3 for RCS leakage and has notified the OMOC.
Which ONE of the following identifies:
: 1) The minimum level of authority for the containment entry is    (1).
: 2) The HP Shift Supervisor or designee must _(2)_.
A. (1) Plant Manager (2) Sign on to the In-Core Detector tagout B. (1) Plant Manager (2) Verify In-Core Detectors in storage location C. (1) Director, Nuclear Safety and Licensing (2) Sign on to the In-Core Detector tag out D. (1) Director, Nuclear Safety and Licensing (2) Verify In-Core Detectors in storage location
 
Question:        66 initial Conditions:
* Unit 1 is in a refueling outage.
* Fuel off-load is in progress.
Current Conditions:
* A report is received that a fuel assembly being removed from the core was significantly damaged while lifting it from the core.
* Large Bubbles were seen escaping from the damaged fuel assembly.
* NO radiation alarms have been received.
Which ONE of the following describes the actions required by O-AP-22.OO, Fuel Handling Abnormal Conditions:
: 1)  Closing 1-VS-MOD-i 03A and 1-VS-MOD-i 03C will secure
: 2)    Is Containment Evacuation required?
A. 1) 1-VS-F-15, MCR Exhaust
: 2) Yes.
B. 1) 1-VS-AC-4, MCR Supply
: 2) No.
C. 1) 1-VS-AC-4, MCR Supply
: 2) Yes.
D. 1) 1-VS-F-15, MCR Exhaust
: 2) No.
 
Question:    67 Which ONE of the choices below completes the following statement?
The Federal Dose limit for Lens of the Eye is      per year.
A. 15 Rem B. 1.5 Rem C. 5.0 Rem D. 50 Rem
 
Question:        68 Which of the following Critical Safety Function RED paths is the highest priority CSF that can be directly caused by procedurally directed operator action?
A. Subcriticality.
B. Core Cooling.
C. Heat Sink.
D. Containment.
 
Question:        69 The Station has just upgraded from an Alert to a Site Area Emergency.
Which ONE of the following actions is required for a Site Area Emergency in addition to those actions initiated for the Alert?
A. Off-Site monitoring Team Dispatched.
B. Emergency Response Personnel called in.
C. A Report of Radiological Conditions to the State is transmitted.
D. Accountability is performed.
 
Question:        70 Given the following:
* 0800: A large break LOCA occurred.
* 0810: A Site Area Emergency was declared.
In accordance with EPIP-2.01, when obtaining meteorological data from the MET panel:
: 1) The preferred source for wind speed, and wind direction is the Main Tower          (1)
: 2) The required Notification completion time is recorded following roll call after reading Item (2)
A. 1)LowerLevel 2)11, Additional Information B. 1)LowerLevel 2)1, Emergency Classification C. 1)UpperLevel 2)11, Additional Information D. 1)UpperLevel 2)1, Emergency Classification
 
Question:        71 Initial Conditions:
* Unit 2 operating at 100% power.
* A LOCA has occurred in Unit 2 Safeguards.
* Unit 2 is tripped and safety injection actuated.
* 2-Sl-MOV-2890C, LHSI to Cold Legs, has been closed.
* RCS Pressure is 1005 psig and rising.
* The Team has transitioned to 2-E-1, Loss of Reactor or Secondary Coolant.
In accordance with 2-E-1, Loss of Reactor or Secondary Coolant, which ONE of the following identifies:
: 1) The status of the LHSI pumps.
: 2) The position of the LHSI Suction Valves from the RWST, 2-Sl-MOV-2862A and B.
A. 1) Secured in PTL.
: 2) Closed.
B. 1) Secured in AUTO.
: 2) Closed.
C. 1) Secured in PTL.
: 2) Open.
D  1) Secured in AUTO.
: 2) Open.
 
Question:      72 Given the following:
* Unit 1 was operating at 100% when a large break LOCA occurred.
* RCS pressure is 25 psig.
* All ECCS equipment responded as designed.
* The crew is performing step 4 of 1-E-1, Loss of Reactor or Secondary coolant.
* The STA reports that red path for Integrity is satisfied and recommends FR-P.1.
Which of the following describes:
: 1) The actions the crew would take in response to the Integrity Red path.
: 2) The reason these actions are taken.
A. 1) Go to FR-P. 1, and after step 1 return to 1 -E-1.
: 2) Steam Generators are thermally disconnected from the RCS.
B. 1) Go to FR-P. 1, and after step 1 return to 1 -E-1.
: 2) Pressurized thermal shock is not a concern.
C. 1) Do not enter FR-P.1, continue in 1-E-1 until directed to transition.
: 2) Steam Generators are thermally disconnected from the RCS.
D  1) Do not enter FR-P.1, continue in 1-E-1 until directed to transition.
: 2) Pressurized thermal shock is not a concern.
 
Question:      74 Given the following:
* A Large Break LOCA has occurred.
* Crew is presently performing step 3 of ES-i .3
* RWST level is at 14%.
Which of the following completes the following statements.
i) Auto Swapoverto RMT will occur when              RWST level transmitters reach 13.5%.
: 2) In accordance with 1-ES-i .3, Transfer to Cold Leg Recirculation, step 5; IF RMT fails to automatically actuate the RO manually initiates RMT by depressing            pushbuttons for each train.
A. i) 2of4
: 2) 2of2 B. 1) 3of4
: 2) 2of2 C. 1) 3of4
: 2) lof2 D. i) 2of4
: 2) 1 of2
 
Question:      75 Initial Conditions:
* Both Units are operating at 100% power.
* A seismic event occurs which results in a Loss of Offsite Power and an automatic Reactor Trip on both Units.
Current Conditions:
* The Team has transitioned froml-E-0, Reactor Trip or Safety Injection to 1-ES-0.1, Reactor Trip Response.
* The STA reports that Containment Sump Level is 7.8 feet and rising.
Which ONE of the following identifies:
: 1) The Abnormal Procedure initiated by 1-E-0 Immediate Actions.
: 2) The PATH COLOR in effect on the Containment Status Tree.
A. 1) 0-AP-37.00, Seismic Event.
: 2) Red.
B. 1) 0-AP-37.00, Seismic Event.
: 2) Orange.
C. 1) 1-AP-10.07, Loss of Unit 1 Power.
: 2) Red.
D. 1) 1-AP-10.07, Loss of Unit 1 Power.
: 2) Orange.
 
RO EXAM LIST OF ATTACHMENTS Attachment # Attachment Description 1      Containment Ventilation 2      E-3 Table
 
2015 NRC ANSWER KEY Question #  Answer    Question Answer
                              #
RO 1        B          41      C 2        A          42      C 3        A          43      A 4        A          44      B 5        B          45      D 6        D          46      B 7        A          47      C 8        B          48      B 9        B          49      C 10        D          50      A 11        B          51      B 12        C          52      C 13        D          53      C 14        C          54      D 15        A          55      A 16        B          56      A 17        A          57      D 18        C          58      B 19        A          59      D 20        D          60      B 21        A          61      D 22        A          62      B 23        D          63      A 24        A          64      D 25        B          65      C 26        C          66      C 27        D          67      A 28        B          68      C 29        A          69      A 30        C          70      B 31        C          71      A 32        C          72      B 33        C          73      A 34        D          74      A 35        A          75      D 36        D 37        C 38        B 39        D 40        C NRC Validation Page 1
 
Question:        1 Initial Conditions:
* Reactor at 50% and stable.
* Tave at 558 &deg;F, Tref at 558 &deg;F.
Current Conditions:
* Median Tave fails such that Tave is 4.0 &deg;F lower than Tref.
* Rod Control is placed in manual 30 seconds after the failure occurs.
Which ONE of the following states:
: 1) The direction of rod motion immediately before the rods were placed in manual.
: 2) The number of steps the control rods must be moved to restore the control rods to their previous rod height (prior to the Tave failure).
A. 1) Out.
: 2) 16.
B. 1) Out.
: 2) 20.
C. 1) In.
: 2) 16.
D. 1) In.
: 2) 20.
 
________
Question:          2 Initial plant conditions:
* Unit 1 is at 100% power.
* Currently performing a test of Reactor Trip breaker A per 1 -PT-8. 1, Rx. Protection Logic testing.
* An automatic reactor trip signal occurs.
* Reactor Trip and Reactor Trip Bypass breaker position following the Trip are shown below.
* No operator actions have been taken.
REACTOR TRiP BKR RTA
[  REACTOR TRIP J    EKR RTB CONTROL ROD SOUD STATE POWER SUPPLY ROD CONTROL RTSYPASS                        RTBYPASS SKR BYA                          BKR BYB Which ONE of the following correctly completes the following statements:
: 1) The Reactor trip and Bypass breakers                            correctly.
: 2) With respect to the breaker under test, the operator is required to A.      1) did not
: 2) initiate a manual reactor trip per 1-E-0, Reactor Trip or SI B.      1) did not
: 2) locally trip the breaker per 1-FR-S.1, Response to Nuclear Generation/ATWS C.      1) did
: 2) initiate a manual reactor trip per 1-E-0, Reactor Trip or SI D.      1) did
: 2) locally trip the breaker per 1-FR-Si, Response to Nuclear Generation/ATWS
 
Question:        3 Initial Conditions:
* The Unit is in Cold Shutdown with the Team preparing to start the first RCP in accordance with 1 -OP-RC-001, Starting and Running Any Reactor Coolant Pump.
* Vacuum assist was unavailable during RCS Loop fill.
The following sequence of events occur:
* 0900, C RCP started for RCS Vent.
* 0902, C RCP secured due to low seal Differential Pressure.
* 0933, C RCP started for RCS Vent.
* 0938, C RCP secured due to low seal Differential Pressure.
* 1012, C RCP started for RCS Vent.
* 1027, C RCP secured due to the loss of both seal injection and thermal barrier flow.
Which ONE of the following states:
: 1)    What is the earliest time the fourth start of the C RCP may be attempted, in accordance with 1-OP-RC-001?
: 2)    When restoring seal injection and thermal barrier cooling to an RCP seal, which is restored first?
A. 1) 1128.
: 2) Thermal Barrier.
B. 1) 1128.
: 2) Seal Injection.
C. 1) 1058.
: 2) Thermal Barrier.
D. 1) 1058.
: 2) Seal Injection.
 
Question:      4 Unit I was operating at 100% operation when a failure occurred causing Letdow temper n        ature to rise.
Which of the following describes:
: 1) At what temperature will the Letdown divert valve, 1-CH-TCV-1 143 divert to the VCT?
: 2) What is the reason for this action?
A.      1) 145&deg;F.
: 2) Protect Ion Exchanger resin from damage due to high Letdown line temp.
B.      1) 145&deg;F.
: 2) Mitigate negative reactivity caused by boron release from Demins.
C.      1) 130&deg;F.
: 2) Protect Ion Exchanger resin from damage due to high Letdown line temp.
D. 1) 130&deg;F.
: 2) Mitigate negative reactivity caused by boron release from Demins.
 
Question:        5 Initial Conditions:
* Unit 1 is being cooled down to Cold Shutdown, with RHR in service.
Which ONE of the following states:
: 1) The power supply to 1-RH-MOV-1 700, RHR Inlet MOV.
: 2) The pressure transmitter that supplies the signal for the open (maximum pressure) interlock for 1-RH-MO V-i 700.
A. 1) iHi-2S-8C.
: 2) i-RC-PT-i402-1, RCS Pressure Wide Range.
B. 1) iHl-2S-SC.
: 2) i-RC-PT-i403, RCS Pressure Narrow Range.
C. 1) 1A1-1E-4B.
: 2) i-RC-PT-1402-i, RCS Pressure Wide Range.
D. 1) iAi-1E-4B.
: 2) i-RC-PT-i403, RCS Pressure Narrow Range.
 
Question:      6 Given the following conditions:
* RCS temperature is 175&deg;F.
* RCS pressure is 305 psig.
* The PRZR is solid.
* Charging flow control is in manual.
* RHR is in service, with the A RHR heat exchanger and 1-RH-P-lA in service.
* 1-RH-FCV-1 605, RHR H/X bypass, is in AUTO.
The A RHR heat exchanger suddenly develops a 150 gpm tube leak.
With NO Operator actions, which ONE of the following identifies the effect of this malfunction on:
: 1) Flow through the RHR pump.
: 2) RCS pressure.
A. 1) Flow remains the same.
: 2) Pressure lowers.
B. 1) Flow remains the same.
: 2) Pressure rises.
C. 1) Flow rises.
: 2) Pressure rises.
D. 1)Flowrises.
: 2) Pressure lowers.
 
_________
Question:        7 Initial Conditions:
* A Large Break LOCA is in progress.
* The Team is performing 1-E-0, Loss of Reactor or Secondary Coolant.
* The BOP operator is performing 1-E-0, Attachment 1, System Alignment Verification and is on Step 12 CHECK SI FLOW.
Current Conditions:
* RCS pressure is 30 psig.
* HHSI and LHSI pump amps are listed below:
PUMP        AMPS 1-CH-P-1A  70 1-.CH-P-1B  69 1-CH-P-1C  30 1-SI-P-lA  265 1-SI-P-lB    275 Which ONE of the following describes the status of the HHSI and LHSI pumps upon compl etion of , step 12.
: 1) The HHSI pump that will be secured is
: 2) The number of LHSI pumps that will be running is A. 1) l-CH-P-1C
: 2) two B. 1) 1-CH-P-1A
: 2) two C. 1) 1-CH-P-1C
: 2) one D. 1) 1-CH-P-1A
: 2) one
 
Question:        8 Given the following:
* Unit 1 operating at 100%.
* The crew experienced a spurious SI signal.
* Following the SI the Charging pump suction valves have the following positions:
o  1 -CH-MOV-1 11 5B,  CHG  pump suction from RWST; CLOSED.
o  1.-CH-MOV-1115C,    CHG  pump suction from VCT; OPEN.
o  1 -CH-MOV-1 11 5D,  CHG  pump suction from RWST; OPEN.
o  1-CH-MOV-1115E,    CHG  pump suction from VCT; CLOSED.
* All other auto SI actions occur as designed.
In the given alignment, the VCT _(1)          a source of HHSI flow, and the RWST _(2)            a source of HHSI flow.
A. 1)is              2)isnot B. 1)isnot          2)is C. 1)is              2)is D. 1) is not        2) is not
 
Question:        9 Initial Conditions:
* 1-RC-PT-1445, PRZR PRESS CNTRL, failed high.
* The Team has completed the Immediate Actions of 1-AP-31 .00, Increasing or Decrea sing RCS Pressure.
Current Conditions: (2 minutes later):
* PRT Pressure is 12 psig and stable.
* Annunciator 1C-F7, PRZR RELIEF TK HI PRESS is Lit.
Which ONE of the following identifies:
: 1) The PRZR PORV that was closed is_____
: 2) The procedure that will direct returning the PRT to normal pressure is________
A. 1) 1-RC-PCV-1455C
: 2) 1-AP-31.00, Increasing or Decreasing RCS Pressure B. 1) 1-RC-PCV-1456
: 2) ARP 1C-F7, PRZR RELIEF TK HI PRESS C. 1) 1-RC-PCV-1455C
: 2) ARP 1C-F7, PRZR RELIEF TK HI PRESS D. 1) 1-RC-PCV-1456
: 2) 1 -AP-31 .00, Increasing or Decreasing RCS Pressure
 
_____
__
Question:          10 Initial Conditions:
* Unit 1 is at 100%.
* Tave is at 573 &deg;F.
* Pressurizer Safety Valve 1-RC-SV-1551A inadvertently fails partially open.
* S/G B NR level channel 1, 1-FW-Ll-1484, fails high immediately following the Reactor trip.
* 30 seconds later SI automatically actuates.
Current Conditions (10 minutes later)
* Plant is stabilized with Tave at 552 &deg;F and RCS pressure at 1910 psig.
* Pressurizer vapor space temperature is steady at 630 &deg;F.
* Main Feedwater pumps have tripped, all Feed Reg valves are closed, and all Feed Reg Bypass valves are closed.
Which of the following describes:
: 1) The Main Feed pumps trip after the_______
: 2) The Feed Regulating Bypass valves initially closed due to the A. 1) reactor trip, but before the safety injection
: 2) reactor trip coincident with low Tave B. 1) reactor trip, but before the safety injection
: 2) safety injection C. 1) safety injection
: 2) reactor trip coincident with low Tave D. 1) safety injection
: 2) safety injection
 
Question:        11 Initial Conditions:
* Unit 1 reactor operating at 100% power.
* A tube leak develops in 1-CC-E-1A, A CCHX.
Which ONE of the following states:
: 1) The effect on CC Surge Tank level.
: 2) The CW lines that supply SW to the CCHXs.
A. 1) Rise.
: 2) lA/C.
B. 1) Lower.
: 2) IBID.
C. 1) Rise.
: 2) iB/D.
D. 1) Lower.
: 2) lA/C.
 
_____
Question:        12 Initial Conditions:
* Unit 1 and Unit 2 operating at 100%.
* LOCA on Unit 1 causing Reactor trip and SI.
* Charging pump, 1-CH-P-1B started then tripped on lockout, 1-CH-P-IA and C are running.
* Containment pressure is 16.2 psia and slowly rising.
Current conditions:
* RO reports loss of 1 H 4160 V bus. EDG 1 did not start.
* RCS pressure is 1082 psig and slowly lowering.
* CETC is 528 &deg;F and stable.
Which of the following states:
: 1) RCP Trip criteria is
: 2) In accordance with 1-E-1 Basis; the reason RCP5 are tripped is to A. 1) Met
: 2) Prevent excessive depletion of RCS inventory B. 1) Not met
: 2) Minimize heat input C. 1) Not met
: 2) Prevent excessive depletion of RCS inventory D. 1) Met
: 2) Minimize heat input
 
___
Question:      13 A ground has developed on DC Panel 1-2, causing 1-.RC-SOy-biB-I and 1-RC-SOV-1 O1B-2, PRZR Vent Valves, to fail open.
Which ONE of the following states:
: 1) The Master Pressure controller output will
: 2) The PRZR Vent Valves discharge to the A. 1) rise
: 2) Primary Vent Pot B. 1) rise
: 2) Reactor Cavity C. 1) lower
: 2) Primary Vent Pot D. 1) lower
: 2) Reactor Cavity
 
Question:          14 Initial conditions:
* Unit 1 is at 100% power.
* The breaker for 1 -SI-MOV-1 885C, LHSI Pump A Recirc Valve, was found open, and could not be reclosed.
* A Large Break LOCA occurs.
Current conditions:
* The RWST level is 12.5%.
* The Team is currently at 1-ES-i .3, Transfer to Cold Leg Recirculation; step 5, Align SI System for Recirc.
Which ONE of the following identifies:
: 1) Which LHSI pump(s) will automatically align to the RMT mode?
: 2) Per ES-i .3 CAP, after step 5, the operator will monitor for oscillating LHSI pump amps and flow to check for A.        1) Both LHSI pumps.
: 2) RWST <3%
B.      1) ONLY the B LHSI pump.
: 2) sump blockage C.      1) Both LHSI pumps.
: 2) sump blockage D.      i) ONLY the B LHSI pump.
: 2) RWST <3%
 
Question:        15 A loss of off-site power has resulted in the trip of both Units.
* 120 seconds have elapsed since the reactor trip.
Which ONE of the following identifies the Pressurizer heaters energized on Unit 1?
A. None.
B. E Group.
C. E and A Groups.
D. A Group.
 
Question:        16 Given the following:
* Unit 1 is at 100%.
* Power Range N-41 fails HIGH.
* 0-AP-53.00, Loss of Vital Instrumentation/Controls, immediate actions completed.
* Crew is presently performing 1-AP-4.00, Nuclear Instrumentation Malfunction, Attach ment ito place the failed Power range channel in trip.
Which one of the choices below completes the following statements?
: 1) In accordance with 1-AP-4.00, Attachment 1; OP L\T channel 1          have to be placed in trip.
: 2) OP z\T provides protection against A.        1) will
: 2) DNB B.      1) will
: 2) high power density C.      1) will not
: 2) DNB D.      1) will not
: 2) high power density
 
Question:          17 Initial Conditions:
* Unit 1 is heating up per 1-GOP-i .3, RCS Heatup from 345 &deg;F to HSD following a mid-cy cle outage.
* 40,000 gallons were transferred to the RWST from the blender.
* RWST Refrigeration Unit 1A is tagged out for compressor breaker replacement.
* RWST Refrigeration Unit 1 B is in operation.
* Annunciator 1A-C7, RWST HI TEMP has alarmed.
* RWST temperature is 42&deg;F on channel 1 and channel 2; (1-CS-TI-i OOA and bOB).
Current Conditions (5 mm. later)
* Operator reports RWST Refrigeration Unit 1 B has a low oil pressure trip and he is unable to reset. Operator requests maintenance support.
* Unit 1 RWST parameters are as follows:
Temp.          Boron 44&deg;F            2275 ppm In accordance with Tech Specs 3.3.A. 1, RWST; which of the following completes the statem ent.
With the current conditions the RWST LCO temperature limit is _(1), and the RWST Boron LCO limit is _(2)....
A. 1) met
: 2) not met B. 1) not met
: 2) met C. 1) not met
: 2) not met D. 1) met
: 2) met
 
_____
Question:          18 Initial Conditions:
* Unit 1 is at 100% power when a large break LOCA occurs.
* Containment pressure peaks at 45 psia.
Current Conditions:
* The crew is at 1-El, Loss of Reactor or Secondary Coolant, step 17 and is attempting to open 1-lA-TV-i 00.
* The RO reports that Containment pressure is slowly lowering and is as follow s:
o 1-LM-Pl-100A 15 psia.
o 1-LM-Pl-100B 15 psia.
o 1-LM-Pl-100C 14 psia.
o 1-LM-Pl-100D 15 psia.
* 1-Pl-IA-101, CTMT INST AIR, indicates 25 psig.
* The operator has depressed both CLS Train A (B) RESET buttons.
* SI has been reset.
Which one of the following correctly completes the statements below:
: 1) After depressing both CLS RESET buttons, CLS          reset.
: 2) When the operator attempts to open 1-IA-TV-i 00, the valve will A.      1) is        2) remain closed B.      1) is not    2) open C.      I) is not    2) remain closed D. 1) is        2) open
 
Question:        19 The reactor is operating at 100% power when the following sequence of events occur:
* Initial D Bank rod height 225 Steps.
* The RO is performing 1-OPT-RX-005, Control Rod Assembly partial Movem ent, for D Control Bank.
* Annunciator G-A6, Rod Cont Sys Urgent Failure is received when Contro Bank l      D begins to move inward.
* Rod Control In-Hold-Out switch placed in Hold.
The following indications are noted by the RO:
* Control  Bank D, Group 1 Step counter indicates 224 Steps.
* Control  Bank D, Group 2 Step counter indicates 222 Steps.
* Control  Bank D, CERPI Group 1 indicates 224 Steps.
* Control  Bank D, CERPI Group 2 indicates 222 Steps.
Which ONE of the following identifies the:
: 1) Power Cabinet affected by the Urgent Failure.
: 2) The procedure that would need to be entered to mitigate the malfunction.
A. 1) Power Cabinet 1BD.
: 2) 0-AP-1 .00, Rod Control System malfunction.
B. 1) Power Cabinet 1BD.
: 2) 0-AP-1 .02, Individual Rod Position Indicators.
C. 1) Power Cabinet 2BD.
: 2) 0-AP-1.00, Rod Control System malfunction.
D. 1) PowerCabinet2BD.
: 2) 0-AP-1.02, Individual Rod Position Indicators.
 
Question:        20 With Unit 1 at 100% power, an inadvertent phase Ill containment isolation occurs. Approximately 15 minutes later, the following RCP temperatures exist:
A RCP
* Upper Motor radial bearing                185&deg;F
* RCP lower bearing Seal Water Temp          215&deg;F
* Stator winding                            285&deg; F C RCP
* Upper Motor radial bearing                180&deg;F
* RCP lower bearing Seal Water Temp          210&deg;F
* Stator winding                              305&deg; F In order to mitigate these plant conditions, the crew will monitor RCP temper atures using (1)          ,then initiate 1-E-0, Reactor Trip or Safety Injection, trip the reactor, and stop (2)
A.      1) 1-AP-15.00, Loss of Component Cooling
: 2) C RCP B. 1) 1-AP-15.00, Loss of Component Cooling
: 2) A RCP C.      1) 1-AP-9.00, RCP Abnormal Conditions
: 2) A RCP D.      1) 1-AP-9.00, RCP Abnormal Conditions
: 2) C RCP
 
Question:        21 Unit 2 initially operating at 100% power, when the following occurs:
* A LOCA outside of CTMT.
* The Reactor is tripped and Safety Injection actuated.
* The RCPs have been tripped due to low RCS subcooling.
* RVLIS Full Range Indicates 42% and stable.
* RCS THOT indicates 650 &deg;F and stable.
* CETCs indicate 660 &deg;F and rising.
Which ONE of the following describes:
: 1) The temperature indication used on the Core Cooling Status tree.
: 2) The status of the Core Cooling Status Tree.
A. 1) CETC temperature.
: 2) Orange.
B. 1) CETC temperature.
: 2) Red.
C. 1)THOT.
: 2) Orange.
D. 1) THOT.
: 2) Red.
 
Question:        22 Unit 2 is performing a Reactor Startup following a forced outage. Shutdo wn banks are fully withdrawn.
During the outage, a substantial amount of work had been performed in the Pressurizer Cubicle in Containment.
Given the following data:
Initial        Condition Parameter                                  Condition        1 Day later PRT Level                                      78%              78%
PRT Pressure                                  6 psig          6 psig PRT Temperature                                82&deg;F            84&deg;F Weighted AVG CTMT Temperature                  972&deg;F            101 5&deg;F A PRZR SV Temperature                        129&deg;F            152&deg;F B PRZR SV Temperature                        140&deg;F            160&deg;F C PRZR SV Temperature                        121&deg;F            149&deg;F PRZR PORV Temperature                          121&deg;F            148&deg;F Shutdown bank CERPI Indication                  No change in CERPI Which ONE of the following states the cause for the changes noted betwee n the Initial Conditions and the Conditions found 1 Day later?
A.      Cubicle Ventilation Damper position change.
B.      CRDM Fan Trips.
C.      B PRZR SV Leaking.
D.      PRZR PORV leaking.
 
Question:        23 Initial Conditions:
* Unit 1 at 50% power and ramping up to 100% in accordance with GOP-i .5, Unit Startup, 2% to Max Allowable Power.
* Rod Control in manual due to hunting in automatic.
Current Conditions:
* Median Tave fails to a stable indication of 550 &deg;F.
* No Operator Actions have been taken.
Which ONE of the following states:
: 1) The Pressurizer level control setpoint is
: 2) The automatic charging low flow limit is A. 1) 24.8%
: 2) 30 gpm B. 1) 25.8%
: 2) 30 gpm C. 1) 24.8%
: 2) 25gpm D. 1) 25.8%
: 2) 25 gpm
 
Question:        24 Unit 2 is operating at 100% power with Chilled CC in service to containment.
* An operator is verifying the Plant Computer System displays and indications are functioning properly using the laptop computer at the Auxiliary Shutdown Panel.
* 2-CD-REF-i, Unit 2 Turbine Building Chiller trips.
Which ONE of the following states:
: 1) Containment partial pressure will
: 2) Containment saturation temperature is sensed at the_______
A. 1) lower
: 2) Containment air recirculation fan discharge B. 1) rise
: 2) Containment air recirculation fan discharge C. 1) rise
: 2) Containment dome D. 1) lower
: 2) Containment dome
 
_____
__
Question:        25 Initial Conditions:
* Unit 1 is in Cold Shutdown, at 190 &deg;F, on RHR, preparing to take the pressu rizer solid.
* A RHR pump is running with the A RHR HX in service.
* A CC pump running on Unit 1; D CC pump running on Unit 2. CC is cross-t ied.
Current Conditions:
* C RSST trips and locks out.
Which ONE of the following states:
: 1) The status ofA RHR pump.
: 2) The              CC pump is running on Unit 1, and the        CC pump is running on Unit 2.
A. 1) Running.
: 2) A; D B. 1) Tripped.
L;
: 2)        C C. 1) Running.
: 2) B; C D. 1) Tripped.
: 2)  ?;
 
Question:        26 Given the following:
* A Large Break LOCA has occurred on unit 1.
* An operator has been assigned to perform 1-E-O, Reactor Trip or SI; Attachment 4, CLS Component verification.
* When checking the valve lineup the operator notices that the red and green light bulbs for 1-SW-MOV-104A, RSHX A SW INLET are NOT lit.
Which one of the following indications does 1 -E-O, Attachment 4 direct the operator use to verify that there is adequate flow through the heat exchanger?
A. 1-SW-MOV-103A, RS HX A&D SW SUPPLY; and 1-SW-MOV-105A, RSHX A SW OUTLET red lights LIT.
B. Annunciator 1A-D6, RS HX 1A RAD MON PP NO FLOW is NOT LIT.
C. Flow indication on 1-SW-Fl-i 06A, RS HX A SW Outlet Flow.
D. 1-SW-P-5A, RS SW Radiation Monitor Sample pump red light is LIT.
 
_____
_____
__    _
Question:        27 Unit 1 is operating at 100% with the following conditions:
* 1-OPT-RC-10. 0, Computer leak Rate Program has trended a rise in Uniden tified leakage of 0.1 gpm.
* A Containment entry has been performed and the leak has been identified on the A SG Primary manway.
* HP has requested the Unit 1 Iodine filter fans, 1-VS-F-3A and 3B, be placed in service.
Which ONE of the following identifies:
: 1) The operator will place the control switch for the Iodine Filter Fans to to start the fans.
: 2) The Unit 1 Iodine Filter Fans are operated at the Ui Main Control Room panel.
A. 1) Auto
: 2) Ventilation B. 1) Auto
: 2) Post Accident Monitoring C.1)On
: 2) Post Accident Monitoring D. 1) On
: 2) Ventilation
 
___
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Question:          28 Initial Conditions:
* Unit 1 is at HSD with all RCPs running.
* Preparations for Unit startup are in progress per 1-GOP-1.4, Unit Startup.
* The Master Pressure Controller (MPC) and spray valve controllers are all in auto and set to maintain 2235 psig.
* Pressurizer pressure indicates 2250 psig on 1-RC-Pl-1444, and 1-RC-Pl-144 5.
Current Conditions (60 sec):
* Pressurizer pressure is 2130 psig.
* 1C-B8, PRZR LO PRESS is alarming.
* 1-RC-PC-1444G, PRZR Spray from Loop A, 1-RC-PCV-1455A indicates 100%.
* 1-RC-PC-1444H, PRZR Spray from Loop C, 1-RC.-PCV-1455B indicates 0%.
* 1-RC-PC-1444J, PRZR PRESS Master CNTRL, indicates 0%.
Which ONE of the following identifies:
: 1) The POT setting of the Master Pressure Controller for 2235 psig is
: 2) The expected operator action associated with the failure in accordance with 0-AP-53.00, Loss of Vital Instrumentation/Cont is to place              in manual and close the spray valve.
A. 1) 7.45
: 2) 1-RC-PC-1444G, PRZR Spray from Loop A, 1-RC-PCV-1455A B. 1)6.68
: 2) 1-RC-PC-1444G, PRZR Spray from Loop A, 1-RC-PCV-1455A C. 1)7.45
: 2) 1-RC-PC-1444H, PRZR Spray from Loop C, 1-RC-PCV-1455 D. 1)6.68
: 2) 1-RC-PC-1444H, PRZR Spray from Loop C, 1-RC-PCV-1455
 
____
Proposed Question:      29 Given the following:
* Pressurizer level channel transmitter 1-RC-LT-459, Pressurizer Level Protec tion  Channel I, is the upper channel.
* The reference leg of 1-RC-LT-459 develops a slow leak.
Which ONE of the following describes:
: 1) As a result of the reference leg leak, the level indication on 1 -RC-LI-1459 will
: 2) In accordance with D-AP-53.DO, Loss of Vital Instrumentation/Controls, the operator required to isolate letdown for this failure.
A. 1) rise
: 2) is not B. 1) rise
: 2) is C. 1) lower
: 2) is not D. 1) lower
: 2) is
 
____
Question:        30 Initial Conditions:
* Unit 1 operating at 100% power.
* Reactor Trip First-out annunciator Ctmt Hi Press.
* Crew is performing 1-E-0, Reactor Trip or Safety Injection, immediate actions.
* Both reactor trip breakers remain closed after E-0 step 1 performed.
Current Conditions:
* An operator has just been dispatched to open reactor trip breakers per 1-FR-S.1, step 8.
* Gamma-Metrics is reading 20%.
* Power Range NI channels are all reading 15%.
* Containment pressure is 22 psia and rising.
Which of the following completes the statements:
: 1) In accordance with 1-E-0, Reactor Trip or SI, Background; if any reactor trip breaker and associated bypass breaker is open, and neutron flux has decreased to less than 5
                                                                            %, the reactor considered tripped.
: 2) In accordance with 1-FR-Si, Response to Nuclear Generation/ATWS; the instrumentation the crew should be using to monitor neutron flux is A. 1) is
: 2) Power Range NI channels B. 1) is not
: 2) Gamma-Metrics C. 1) is
: 2) Gamma-Metrics D. 1) is not
: 2) Power Range NI channels
 
_
Question:        31 Initial Condition:
* Unit 2 Containment pressure has just reached atmospheric.
* The Team is preparing to place Unit 2 Containment on purge using 1-VS-F
                                                                                -58A, in accordance with 2-OP-VS-OO1, Containment Ventilation.
* The Personnel and Equipment Hatches are closed.
Which ONE of the following completes the following statement?
: 1) An allowable configuration would consist of
: 2) The            filter is used in the flowpath.
(REFERENCE PROVIDED)
A. 1) Containment Purge and Fuel Building Exhaust
: 2) CAT II B. 1) Containment Purge Only
: 2) CATI C. 1) Containment Purge and Fuel Building Exhaust
: 2) CATI D. 1) Containment Purge Only
: 2) CATII
 
Question:      32 Given the following:
* Unit 2 is currently stable at 75% power.
* The B Feed Reg Valve demand begins to slowly lower due to an instrument failure.
* Annunciator 2H-G6, STM GEN 1 B LVL ERROR, is Lit.
Which ONE of the following identifies:
: 1) The effect this will have on the indicated power by Instantaneous Calorimetric.
: 2) The procedure used to respond to this event.
A. 1) Lowers.
: 2) 2-AP-21 .00, Loss of Main Feedwater Flow.
B. 1) Rises.
: 2) 2-AP-21 .00, Loss of Main Feedwater Flow.
C. 1) Lowers.
: 2) 0-AP-53.00, Loss of Vital Instrumentation/Controls.
D. 1) Rises.
: 2) 0-AP-53.00, Loss of Vital Instrumentation/Controls.
 
Question:      33 The Operating Team is in E-3, Steam Generator Tube Rupture and has compl eted RCS cooldown and depressurization. CHG pump suction has been aligned to the VCT.
The following Unit conditions exist:
* PRZR level is 35% and slowly rising.
* S/G levels are as follows:
o A S/G is 68% and lowering.
o B S/G is 33% and rising.
o C S/G is 32% and rising.
* RCS pressure is 985 psig.
* S/G pressures are as follow:
o A S/G is 1000 psig and lowering.
o B S/G is 670 psig and rising.
o C S/G is 650 psig and rising.
Which ONE of the following is the MINIMUM actions required to be taken by the Operating Team in accordance with step 36 of E-3?
(REFERENCE PROVIDED)
A. Depressurize RCS and raise CHG flow.
B. Lower CHG flow and depressurize the RCS.
C. Turn on PRZR heaters.
D. Raise CHG flow.
 
Question:      34 Given the following:
* Unit 1 is at 100 % power.
* A complete separation of the Main steamline piping upstream of the MSR Steam Supply to the A & C MSRs (30 pipe) occurs.
Which ONE of the following describes the effect this will have on the...
: 1) Main Feed pumps.
: 2) Main Steam Trip valves.
A. 1) Remain running.
: 2) Remain open.
B. 1)Trip.
: 2) Remain open.
C. 1) Remain running.
: 2) Close.
D. 1)Trip.
: 2) Close.
 
Question:        35 Initial Conditions:
Unit 1 operating at 100% power.
* A Steam line in Unit 1 alleyway ruptures.
* Station Service buses are lost on swap-over to Reserve Station Service Transf ormers following a manual reactor trip.
* Individual MSTV close switches on Benchboard fail to operate.
* MSTV Emergency close switch on Vertical Board fails to close the MSTV s.
Which one of the following states:
: 1) The redundant MSTV Emergency Close Switch, is located on the Appen dix R panel in
: 2) Operation of this switch              the MSTV close SOVs.
A. 1) Unit 1 ESGR
: 2) Energizes B. 1) Unit 1 ESGR
: 2) Deenergizes C. 1) Unit 2 ESGR
: 2) Energizes D. 1) Unit 2 ESGR
: 2) Deenergizes
 
Question:        36 Unit 1 is placing the Unit on-line in accordance with 1-OP-TM-001, Turbine  - Generator Startup to 20%
- 25% Turbine Power.
* Steam Dumps are in Auto in steam pressure mode.
* Reactor Power has been raised to 8%.
* P-7 NIS POWER RANGE AND TURBINE POWER < 10% is LIT.
* When the second Generator output breaker, OCB-G1T240 is closed, Annun ciator iF-El, GEN BACKUP LOCKOUT REL TRIP, comes in due to a fault.
Which one of the following correctly describes the effect this will have on:
: 1) The reactor.
: 2) Main Generator output breakers.
Reactor                  Main Gen output breakers A. trip                      trip open after 30 seconds B. not trip                  trip open after 30 seconds C. trip                      trip open immediately D. not trip                  trip open immediately
 
____
Proposed Question:      37 Initial Conditions:
* The team was performing 1-E-0 in response to a faulted steam generator outside containment.
* Upon transition from 1-E-0, the STA reported a red path on HEAT SINK.
* The team has entered 1-FR-Hi, Loss of Secondary Heat Sink.
Current Conditions
* SG levels are A- 0% WR, B- 13% WR, C- 14% WR (all lowering).
* RCS Thot 640&deg;F and rising.
* Pressurizer level 80% and rising
* Pressurizer pressure 2345 psig and rising.
* 1-RC-PCV-1455C was cycling open/close and is now open.
Which ONE of the following states:
: 1) In accordance with 1 -FR-H. 1, Continuous Actions Page, RCS Bleed and Feed      required.
: 2) What is the reason for the Pressurizer PORV remaining open?
A. 1)is not
: 2) RCS expansion due to Loss of Heat sink.
B. i)is
: 2) Pressurizer fill due to safety injection.
C. i)is
: 2) RCS expansion due to Loss of Heat sink.
D. i)isnot
: 2) Pressurizer fill due to safety injection.
 
_____ _____
_________
Question:        38 Initial Conditions:
* Unit 1 operating at 100% power.
* A SGTR occurs on the A SG, the reactor is tripped and safety injection actuated.
* The Team has completed the Rapid Cooldown of I -E-3, Steam Generator Tube Rupture.
* The Air Ejector discharge has been re-aligned to Containment.
Current Conditions:
* The A SG faults inside of Containment.
* Hi and Hi-Hi CLS have actuated.
Which ONE of the following states:
: 1) The position of 1-SV-TV-102A, AE DISCH TO CTMT SFGD TV, is
: 2) The position of 1-SV-TV-102, AE DISCH TO CTMTTB TV, is A. 1) open
: 2) open B. 1) closed
: 2) closed C. 1) closed
: 2) open D. 1) open
: 2) closed
 
Question:    39 ECA-O.O, Loss of all AC Power, Step 24, directs the operator to:
Depress urize all Intact SGs to 300 psig Which ONE of the following describes the reason for stopping the pressure reduction at 300 psig?
A. Prevent losing pressurizer level.
B. Minimize inventory loss out of RCP seals.
C. Prevent voiding in the Reactor Vessel upper head.
D. Prevent SI Accumulator Nitrogen into the RCS.
 
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Question:        40 Initial Conditions:
* Unit 1 at 100%
* A transient causes the following annunciators to alarm:
o 1 K-B8, UPS SYSTEM 1 B TROUBLE.
o 1C-Bi, RCP lB CC RETURN LO FLOW.
o 1 E-G4, RX TRIP CH-2 PRZR LO PRESS.
Current Conditions:
* The non-licensed operator dispatched reports the red INVERTER SUPPLYING LOAD light is NOT lit for UPS lB-i.
* Indication on 1-FW-FCV-1488 (B FRV Controller) is:
o Auto Light NOT LIT.
 
o Manual Light NOT LIT.
* The control room team is currently performing actions per 1 K-B8, UPS System 1 B Trouble.
Which one of the following describes:
: 1) B S/G feed flow          be controlled by using the pushbuttons on the FRV controller.
: 2) The Abnormal Procedure that should be utilized is A.      1) can not
: 2) 1-AP-1 0.04, Loss of Vital Bus IV B.      1)can
: 2) 1-AP-i 0.02, Loss of Vital Bus II C.      1)cannot
: 2) 1-AP-10.02, Loss of Vital Bus II D.      1)can
: 2) 1-AP-1 0.04, Loss of Vital Bus IV
 
Question:      41 Which ONE of the following breakers, if open, will cause a Vital Bus UPS Static Switch to shift to the alternate source?
A. Battery Charger AC Input.
B. Battery Charger DC Output.
C. Inverter DC Input.
D. Battery Bus DC Input.
 
Question:      42 Unit 1 is currently at 60% power and is performing a startup.
1-FW-P-1B, B Main Feed Pump, is running.
Shortly after starting 1-FW-P-1A, A Main Feed Pump, the operator observes the Main Feed Pump tripping.
Which ONE of the following conditions could have caused 1-FW-P-1A, A Main Feed Pump trip?
to A. Feed pump Lube oil pressure at 8 psig.
B. C Station Service Bus voltage at 68%.
C. Feed flow    < 3000 gpm and Recirc valve, 1 -FW-FCV-i 50A not fully open.
D. Feed pump Suction pressure at 430 psig.
 
Question:      43 Given the following:
Power from the associated rack in the relay room, to the A FRV controller, 1-FW-FCV-1478 is lost.
With the conditions stated, which of the following answers the questions listed below:
: 1) What is the effect on the output of the controller?
: 2) Can this controller be controlled from the Main Control Room?
A. 1) Shift to manual and output will remain the same as prior to loss of power.
: 2) Yes.
B. 1) The output of the controller will raise to 100% demand.
: 2) Yes.
B. 1) The output of the controller will raise to 100% demand.
: 2) No.
D. 1) Shift to manual and output will remain the same as prior to loss of power.
: 2) No.
 
Question:      44 Given the following:
* An accidental gaseous radwaste release has occurred in the Waste Gas Decay Tank Room.
* A Site Area Emergency has been declared due to dose at the site boundary of 200 mRem/hr.
* Radiation protection has determined that radiation dose level in the room is 1,000 mRem/hr.
A Surry Power Station worker assigned to enter the room has a current year-to-date TEDE of 700 mRem.
The MAXIMUM total time the worker is allowed RCA access, to perform the work, with NO extensions is        hour(s)?
A. 0.50 B. 1.00 C. 1.85 D. 2.30
 
Question:      45 The team is performing 1-E-0, Reactor Trip or Safety Injection, with plant conditions as follows:
* Containment pressure is 27 psia and rising slowly.
* A SIG parameters o Pressure- 650 psig and lowering slowly.
o Level- 57% WR and lowering slowly.
* B SIG parameters o Pressure 120 psig and lowering rapidly.
o Level- 15% WR and lowering rapidly.
* C SIC parameters o Pressure 630 psig and lowering slowly.
o Level- 56% WR and lowering slowly.
* Pressurizer level 0%.
* Pressurizer pressure 1200 psig and lowering.
* RCS Tave- 512 &deg;F and lowering at a rate of 120 &deg;FIhr.
Which ONE of the following states the minimum required AFW flow to the S/Cs in accord ance with E-0, Reactor Trip or Safety Injection, Attachment 8?
A. A SIG- 100 gpm; B S/G- 100 gpm; C S/G-100 gpm.
B. A S/G- 175 gpm; B SIC- 0 gpm; C S/G- 175 gpm.
C. A S/G- 60 gpm; B SIG- 60 gpm; C SIG- 60 gpm.
D. A S/G- 225 gpm; B S/C- 0 gpm; C SIG- 225 gpm.
 
Question:        46 In accordance with 1-AP-21.01, Response to AFW Check Valve Backleakage, which ONE of the following identifies:
: 1) The temperature on an AFW pump casing where the pump is considered vapor bound.
: 2) Which of the AFW pumps is aligned and cooled FIRST if all AEW pumps are found to be vapor bound?
A. 1) 200&deg;F.
: 2) Motor Driven.
B. 1) 200&deg;F.
: 2) Turbine Driven.
C. 1) 165&deg;F.
: 2) Motor Driven.
D. 1) 165&deg;F.
: 2) Turbine Driven.
 
Question:        47 Initial Conditions:
Unit 1 A DC Bus is lost due to a fault, causing a reactor trip.
Current Conditions: (11 minutes following the reactor trip)
A Large Break LOCA occurs on Unit 1.
The Team decides to locally start 1-CS-P-lA, A CS Pump.
Which ONE of the following identifies:
: 1) The red breaker position indicating light          be used by the control room team to identify that 1-CS-P-lA has been successfully started.
: 2) 1-CS-P-lA breaker, 1-EP-BKR-14H5,                have overcurrent trip protection.
A. 1) can
: 2) does not B. 1) can
: 2) does C. 1) cannot
: 2) does D. 1) cannot
: 2) does not
 
_____
_ _____
__
Question:        48 Initial Conditions:
* Unit 1 is operating at 100%.
* 1-SW-P-i CA, CHG PUMP SW PUMP, is running in HAND, 1-SW-P-lOB, CHG PUMP SW PUMP is in Auto.
* 1-CH-P-1C, CHARGING PUMP is running.
* 1 D-G5, SW OR CC PPS DISCH TO CHG PPS LO PRESS has just alarmed.
Current Conditions:
* Reactor Operator reports the following:
o 1-SW-P-bA has tripped, and i-SW-P-lOB remains in standby.
o Highest reading Charging pump bearing temperature is 179&deg;F and rising.
Which ONE of the following describes:
: 1) The Reactor Operator can monitor Charging pump SW flow on the
: 2) 0-AP-1 2.00, Service Water Abnormal, states that the affected Charging pump should be secured once bearing temperature exceeds a minimum of A. 1) Vertical board        2)195&deg;F B. 1) PCS                    2)185&deg;F C. 1)PCS                    2)195&deg;F D. 1) Vertical board        2)185&deg;F
 
__________
Question:      49 Given the following conditions:
* Unit 1 tripped from 100% power due to loss of on-site and off-site power.
* The team is performing 1-ECA-0.0, Loss of all AC Power.
* The AAC EDG has not been loaded on an emergency bus.
Which ONE of the following identifies:
: 1) The power source for Unit 1 Annunciator System is
: 2) The Black Battery supplies the A. 1) A Station Battery
: 2) Seal Oil Backup Pump B. 1) B Station Battery
: 2) Emergency Oil Pump C. 1) A Station Battery
: 2) Emergency Oil Pump D. 1) B Station Battery
: 2) Seal Oil Backup Pump
 
Question:      50 Which one of the following supplies the DC control power to #1 EDG output breaker, 1 -EP-BKR-1 5H3?
A. A DC bus.
B. B DC bus.
C. Black battery DC bus.
D. #1 EDG DC system.
 
Question:    51
* O-VSP-C8, Fire Detected, has alarmed with Unit 1 ESGR indicated on the fire display panel.
* The BOP has dispatched an operator to investigate Unit 1 ESGR for a fire.
Which ONE of the following identifies:
: 1) The maximum time limit for the operator to report fire status.
: 2) The reason for this time limit in accordance with O-VSP-C8.
A. 1) 5 minutes.
: 2) Ensure adequate time for EAL classification and transmission, if required.
B. 1) 5 minutes.
: 2) Prompt response is necessary to prevent significant damage.
C. 1) 3 minutes.
: 2) Ensure adequate time for EAL classification and transmission, if required.
D. 1) 3 minutes.
: 2) Prompt response is necessary to prevent significant damage.
 
________
____
Question:          52 Initial Conditions
* Both units at 100% power.
* The Control Room is evacuated due to a Limiting Main Control Room Fire.
* All actions per 0-FCA-001, Limiting MCR Fire were taken prior to evacuation.
Current Conditions (20 minutes later)
* Operator dispatched to perform 0-FCA-1 1.0, Remote Monitoring.
* Operator reports that Unit 1, Neutron flux indicators are reading as shown below:
Operator reports the following additional        NEUT FLUX      NEUT FLUX 1-NM-NFI-190A2 nformation:                                                  1-1iMMFI-190B2 10          CO
* 1-NM-NFI-190A2 has been steady at presentvalueforlast5 minutes.
* 1-NM-NFI-190B2 has lowered from 1 x iO to present value over last 5                            R      102 minutes.                                            io S
P O
10&deg;
                                                                              .7 p      10 10I 5 17e4          375.7 Unit Supervisor directs the operator to switch 1 -NM-NFl-i 90A & B to the alternate power supply using the Appendix R switch.
Which of the following describes:
: 1) The Nuclear Instrument indication at the Remote Monitoring panel                as expected.
: 2) The location of the alternate power App R switch for 1-NM-NFl-i 90A & B is located in the A.      1) is not
: 2) Cable Tray Room Unit 2 B.      i)is
: 2) Cable Tray Room Unit 2 C.      1)isnot
: 2) Emergency Switchgear Room Unit 2 D.      1)is
: 2) Emergency Switchgear Room Unit 2
 
Question:        53 Both Units are operating at 100% power.
Which ONE of the following water sources is collected directly into the High/Low Level Liquid Waste Tanks prior to transfer to the SRF?
A. Laundry Drains.
B. Contaminated Drain Tank.
C. Auxiliary Building sump pump discharge.
D. VCT Drain.
 
Question:      54 Given the following:
* Unit 1 is at 100%, Unit 2 is in a Refueling Shutdown.
* l-GW-RM-130A, Rad Monitor Process Vent Particulate indication spiked high causing the following alarms:
o 0-RMA-C5, Process Vent Rad Mon Trbl.
o 0-RMA-C6, Process Vent Part Alert I Hi.
Which ONE of the following describes the automatic plant response?
A. 1-IA-TV-lOlA, and 1-IA-TV-biB, Unit 1 Containment Instrument Air compressor suctions will swap to outside air.
B. i-CV-P-1A, and i-CV-P-i B, Unit 1 Containment vacuum pumps will trip.
C. i-SV-TV-103, Air Ejector Discharge to Vent-Vent Trip valve will automatically close.
D. i-GW-FCV-160, Unit 1 vacuum pump discharge valve, will automatically close.
 
Question:      55 Unit 2 is shutdown and has been borated to CSD boron concentration in preparation for Cooldown to CSD for a Refueling outage.
Chemistry has notified the Team that the RCS crud burst has been initiated.
Which ONE of the following describes:
: 1) The FIRST Radiation monitor that will detect the increased RCS Activity caused by the crud burst.
: 2) Which CVCS filter is monitored for differential pressure during the crud burst cleanup?
A. 1) Letdown Radiation monitor.
: 2) Reactor Coolant filter.
B. 1) Letdown Radiation Monitor.
: 2) Letdown filter.
C. 1) Auxiliary Building Control Area Radiation Monitor.
: 2) Reactor Coolant filter.
D. 1) Auxiliary Building Control Area Radiation Monitor.
: 2) Letdown filter.
 
Question:      56 Given the following:
* Unit 1 and Unit 2 are both operating at 100%.
* You are preparing for a Performance Test of Charging Pump SW pump, 1-SW-P-bA Appendix R controls.
* An operator needs to be stationed locally at 1-SW-P-i OA to observe the pump, and a second operator at the Appendix R controls for 1-SW-P-1OA to start and stop the pump.
The Charging Pump SW pump, 1-SW-P-iDA is located inside          (1), and the Appendix R controls for i-SW-P-bA are located inside Unit 1(2)          room.
A. 1) MER 4            2) Emergency Switchgear B. 1) MER 4            2) Cable Vault C. 1) MER 3            2) Cable Vault D. 1) MER 3            2) Emergency Switchgear
 
Question:    57 Which ONE of the following states:
: 1) The minimum canal level per Tech Spec 3.14, Circulation and Service Water Systems.
: 2) The channel coincidence required to cause BC SW isolation?
A. 1) 23.5 feet.
: 2) 2/4 Channel.
B. 1) 23.5 feet.
: 2) 3/4 Channels.
C. 1) 23.0 feet.
: 2) 2/4 Channels.
D. 1) 23.0 feet
: 2) 3/4 Channels.
 
Question:        58 A severe thunderstorm has caused perturbations on the grid. 0-AP-1 0.18 has been entered due to grid instabilities Initial Conditions:
* Unit 1 is at 100% power, Unit 2 is shutdown.
* The A and B Voltage regulators are in AUTO.
* The A Voltage Regulator is in service.
* Power System Stabilizer (PSS) is in service.
* 55 MVARS Out.
Current Conditions:
* The Operator reports a large rise in MVARS (Out).
* The following Annunciators have just alarmed:
o 1J-A8, OVEREXCITATION LIMIT.
o 1J-B7, VREG CHANNEL A LOCAL ALARM.
Which of the following occurs if the A Voltage Regulator is unable to lower Generator voltage in its current mode?
A.      A Voltage Regulator will shift to the V/Hz mode to control voltage. The B channel will remain in standby.
B.      A Voltage Regulator will trip into Emergency Manual. The B channel will automatically assume control.
C.      A Voltage Regulator will trip into Emergency Manual to control voltage.
The B channel will remain in standby.
D.      A Voltage Regulator will shift to the V/Hz mode to control voltage. The B channel automatically assume control.
 
Question:    59 Which ONE of the following describes the operation of Instrument Air compressor 1-IA-C-i when in AUTO?
A. Compressor will start and LOAD when pressure drops to 90 psig.
Compressor will then UNLOAD and LOAD at 105 psig and 95 psig, respectively.
B. Compressor will start and LOAD when pressure drops to 95 psig.
Compressor will then UNLOAD and LOAD at 105 psig and 95 psig, respectively.
C. Compressor will start and LOAD when pressure drops to 100 psig.
Compressor will then UNLOAD and LOAD at 110 psig and 100 psig, respectively.
D. Compressor will start and LOAD when pressure drops to 90 psig.
Compressor will then UNLOAD and LOAD at 110 psig and 100 psig, respectively.
 
Question:        60 Initial Conditions:
* Unit 1 was operating at 100%.
* Auto Reactor Trip and SI initiation occurs due to Large Break LOCA.
* Containment pressure peaks at 45 psia.
Current Conditions:
* RWST level has just reached 60% one minute ago and is lowering.
* Containment pressure is 22 psia and lowering.
Which ONE of the following describes:
: 1)  The status of Recirc Spray pumps.
: 2)  The minimum number of Containment Spray and Recirc Spray pumps needed to cool and depressurize the containment to < 1 psig in <60 minutes following a Design Basis LOCA.
A. 1) Both Outside Recirc Spray pumps are running, Inside Recirc Spray pumps are off.
: 2) One Containment Spray pump and two Recirculation Spray pumps.
B. 1) Both Inside Recirc Spray pumps are running, Outside Recirc Spray pumps are off.
: 2) One Containment Spray pump and two Recirculation Spray pumps.
C. 1) Both Outside Recirc Spray pumps are running, Inside Recirc Spray pumps are off.
: 2) One Containment Spray pump and          Recirculation Spray pump.
D. 1) Both Inside Recirc Spray pumps are running, Outside Recirc Spray pumps are off.
: 2) One Containment Spray pump and one Recirculation Spray pump.
 
Question:      61 The reactor is starting up following a refueling outage, in accordance with 1-GOP-i .8. Unit Startup, HSD to Max Allowable Power.
Which ONE of the following identifies:
: 1) The flowpath used when diluting to critical in accordance with 1-OP-CH-007, Blender Operations.
: 2) The method used to stabilize reactor power at 1 Q  8 amps.
A. 1) DilutetotheVCT Inlet.
: 2) Boration I Dilution.
B. 1) DilutetotheVCT Inlet.
: 2) Rods.
C. 1) Alternate dilute to CH pump suction.
: 2) Boration I Dilution.
D. 1) Alternate dilute to CH pump suction.
: 2) Rods.
 
Question:        62 Given the following conditions:
* Unit 1 is at 12% power.
* The team is currently performing 1-GOP-i .8, Unit Startup, and are checking trip status lights in preparation for blocking Intermediate Range and Power-Range (LO Setpoint) trips.
* The team depresses Intermediate-Range and Power-Range (LO Setpoint) Block pushbuttons.
* Trip Status lights are as follows:
Light#                      Noun name                      As-found          Required A3      P-b    NIS PWR RGE> 10%                            LIT              LIT Ci      NIS PWR RNG LO SP TRIP BLOCKED                  NOT LIT            LIT
* The team notes that status light Ci is in wrong state, checks bulb and finds bulb is good.
Which ONE of the following describes how the plant will respond if the team continues to raise power.
: 1) At what power will the reactor trip?
: 2) What is the coincidence for the reactor trip?
A. 1)35%.        2)1/4.
B. 1)23%.        2)2/4.
C. 1)23%.          2)1/4.
D. 1)35%.        2)2/4.
 
Question:        63 An Operator has been briefed and sent to perform 1-OPT-FW-OO1, Motor Driven Aux Feedwater Pump 1 -FW-P-3A. While placing 1 -FW-P-3A in the proper lineup for the test, a typographical error for a valve mark number is discovered.
Which ONE of the following completes the following statement regarding the actions to be perfomed in accordance with AD-AA-1 00, Technical Procedure Process Control, to address the issue?
After making a pen and ink change, the Operator_(1)..        required to have a supervisor initial and date the correction before proceeding. After completing the OPT, a procedure change request (FIP)
(2)_ required to be processed.
A. (1)is (2) is not B. (1)isnot (2) is not C. (1)isnot (2) is D. (1)is (2) is
 
__________
Question:        64 Unit 1 is currently Shutdown, and making preparations to perform 1 -OPT-ZZ-0O1, ESF Actuation with Undervoltage and Degraded Voltage 1H Bus. This procedure is an ICCE category Ill.
 
In accordance with OP-AA-1 06, Infrequently Conducted or Complex Evolutions, select the answer that correctly completes the following statements.
: 1) Specific criteria for terminating the test and contingency plans for unexpected occurrences required per Attachment 2 of OP-AA-1 06.
: 2) The          is specifically responsible for the safe operation of the station during performance of the test.
A. 1) is
: 2) Senior Operations Manager B. 1) is not
: 2) Shift Manager C. 1) is not
: 2) Senior Operations Manager D. 1) is
: 2) Shift Manager
 
Question:      65 Given the following:
* Unit 1 is operating at 100% power.
* A Subatmospheric Containment Entry is to be made in accordance with VPAP-01 06, to identify the source of a step change in Unidentified leakage of +0.4 gpm.
* The Shift Manager has entered Action Level 3 for RCS leakage and has notified the OMOC.
Which ONE of the following identifies:
: 1) The minimum level of authority for the containment entry is    (1).
: 2) The HP Shift Supervisor or designee must _(2)_.
A. (1) Plant Manager (2) Sign on to the In-Core Detector tagout B. (1) Plant Manager (2) Verify In-Core Detectors in storage location C. (1) Director, Nuclear Safety and Licensing (2) Sign on to the In-Core Detector tag out D. (1) Director, Nuclear Safety and Licensing (2) Verify In-Core Detectors in storage location
 
Question:        66 initial Conditions:
* Unit 1 is in a refueling outage.
* Fuel off-load is in progress.
Current Conditions:
* A report is received that a fuel assembly being removed from the core was significantly damaged while lifting it from the core.
* Large Bubbles were seen escaping from the damaged fuel assembly.
* NO radiation alarms have been received.
Which ONE of the following describes the actions required by O-AP-22.OO, Fuel Handling Abnormal Conditions:
: 1)  Closing 1-VS-MOD-i 03A and 1-VS-MOD-i 03C will secure
: 2)    Is Containment Evacuation required?
A. 1) 1-VS-F-15, MCR Exhaust
: 2) Yes.
B. 1) 1-VS-AC-4, MCR Supply
: 2) No.
C. 1) 1-VS-AC-4, MCR Supply
: 2) Yes.
D. 1) 1-VS-F-15, MCR Exhaust
: 2) No.
 
Question:    67 Which ONE of the choices below completes the following statement?
The Federal Dose limit for Lens of the Eye is      per year.
A. 15 Rem B. 1.5 Rem C. 5.0 Rem D. 50 Rem
 
Question:        68 Which of the following Critical Safety Function RED paths is the highest priority CSF that can be directly caused by procedurally directed operator action?
A. Subcriticality.
B. Core Cooling.
C. Heat Sink.
D. Containment.
 
Question:        69 The Station has just upgraded from an Alert to a Site Area Emergency.
Which ONE of the following actions is required for a Site Area Emergency in addition to those actions initiated for the Alert?
A. Off-Site monitoring Team Dispatched.
B. Emergency Response Personnel called in.
C. A Report of Radiological Conditions to the State is transmitted.
D. Accountability is performed.
 
Question:        70 Given the following:
* 0800: A large break LOCA occurred.
* 0810: A Site Area Emergency was declared.
In accordance with EPIP-2.01, when obtaining meteorological data from the MET panel:
: 1) The preferred source for wind speed, and wind direction is the Main Tower          (1)
: 2) The required Notification completion time is recorded following roll call after reading Item (2)
A. 1)LowerLevel 2)11, Additional Information B. 1)LowerLevel 2)1, Emergency Classification C. 1)UpperLevel 2)11, Additional Information D. 1)UpperLevel 2)1, Emergency Classification
 
Question:        71 Initial Conditions:
* Unit 2 operating at 100% power.
* A LOCA has occurred in Unit 2 Safeguards.
* Unit 2 is tripped and safety injection actuated.
* 2-Sl-MOV-2890C, LHSI to Cold Legs, has been closed.
* RCS Pressure is 1005 psig and rising.
* The Team has transitioned to 2-E-1, Loss of Reactor or Secondary Coolant.
In accordance with 2-E-1, Loss of Reactor or Secondary Coolant, which ONE of the following identifies:
: 1) The status of the LHSI pumps.
: 2) The position of the LHSI Suction Valves from the RWST, 2-Sl-MOV-2862A and B.
A. 1) Secured in PTL.
: 2) Closed.
B. 1) Secured in AUTO.
: 2) Closed.
C. 1) Secured in PTL.
: 2) Open.
D  1) Secured in AUTO.
: 2) Open.
 
Question:      72 Given the following:
* Unit 1 was operating at 100% when a large break LOCA occurred.
* RCS pressure is 25 psig.
* All ECCS equipment responded as designed.
* The crew is performing step 4 of 1-E-1, Loss of Reactor or Secondary coolant.
* The STA reports that red path for Integrity is satisfied and recommends FR-P.1.
Which of the following describes:
: 1) The actions the crew would take in response to the Integrity Red path.
: 2) The reason these actions are taken.
A. 1) Go to FR-P. 1, and after step 1 return to 1 -E-1.
: 2) Steam Generators are thermally disconnected from the RCS.
B. 1) Go to FR-P. 1, and after step 1 return to 1 -E-1.
: 2) Pressurized thermal shock is not a concern.
C. 1) Do not enter FR-P.1, continue in 1-E-1 until directed to transition.
: 2) Steam Generators are thermally disconnected from the RCS.
D  1) Do not enter FR-P.1, continue in 1-E-1 until directed to transition.
: 2) Pressurized thermal shock is not a concern.
 
Question:      74 Given the following:
* A Large Break LOCA has occurred.
* Crew is presently performing step 3 of ES-i .3
* RWST level is at 14%.
Which of the following completes the following statements.
i) Auto Swapoverto RMT will occur when              RWST level transmitters reach 13.5%.
: 2) In accordance with 1-ES-i .3, Transfer to Cold Leg Recirculation, step 5; IF RMT fails to automatically actuate the RO manually initiates RMT by depressing            pushbuttons for each train.
A. i) 2of4
: 2) 2of2 B. 1) 3of4
: 2) 2of2 C. 1) 3of4
: 2) lof2 D. i) 2of4
: 2) 1 of2
 
Question:      75 Initial Conditions:
* Both Units are operating at 100% power.
* A seismic event occurs which results in a Loss of Offsite Power and an automatic Reactor Trip on both Units.
Current Conditions:
* The Team has transitioned froml-E-0, Reactor Trip or Safety Injection to 1-ES-0.1, Reactor Trip Response.
* The STA reports that Containment Sump Level is 7.8 feet and rising.
Which ONE of the following identifies:
: 1) The Abnormal Procedure initiated by 1-E-0 Immediate Actions.
: 2) The PATH COLOR in effect on the Containment Status Tree.
A. 1) 0-AP-37.00, Seismic Event.
: 2) Red.
B. 1) 0-AP-37.00, Seismic Event.
: 2) Orange.
C. 1) 1-AP-10.07, Loss of Unit 1 Power.
: 2) Red.
D. 1) 1-AP-10.07, Loss of Unit 1 Power.
: 2) Orange.
 
RO EXAM LIST OF ATTACHMENTS Attachment # Attachment Description 1      Containment Ventilation 2      E-3 Table
 
2015 NRC ANSWER KEY Question #  Answer    Question Answer
                              #
RO 1        B          41      C 2        A          42      C 3        A          43      A 4        A          44      B 5        B          45      D 6        D          46      B 7        A          47      C 8        B          48      B 9        B          49      C 10        D          50      A 11        B          51      B 12        C          52      C 13        D          53      C 14        C          54      D 15        A          55      A 16        B          56      A 17        A          57      D 18        C          58      B 19        A          59      D 20        D          60      B 21        A          61      D 22        A          62      B 23        D          63      A 24        A          64      D 25        B          65      C 26        C          66      C 27        D          67      A 28        B          68      C 29        A          69      A 30        C          70      B 31        C          71      A 32        C          72      B 33        C          73      A 34        D          74      A 35        A          75      D 36        D 37        C 38        B 39        D 40        C NRC Validation Page 1}}

Revision as of 06:31, 31 October 2019

301 RO as Given Written Exam Answer Key Reference List
ML15293A072
Person / Time
Site: Surry  Dominion icon.png
Issue date: 10/20/2015
From:
Division of Reactor Safety II
To:
Virginia Electric & Power Co (VEPCO)
References
Download: ML15293A072 (76)
v • d • e


Text

Question: 1 Initial Conditions:

  • Reactor at 50% and stable.
  • Tave at 558 °F, Tref at 558 °F.

Current Conditions:

  • Median Tave fails such that Tave is 4.0 °F lower than Tref.
  • Rod Control is placed in manual 30 seconds after the failure occurs.

Which ONE of the following states:

1) The direction of rod motion immediately before the rods were placed in manual.
2) The number of steps the control rods must be moved to restore the control rods to their previous rod height (prior to the Tave failure).

A. 1) Out.

2) 16.

B. 1) Out.

2) 20.

C. 1) In.

2) 16.

D. 1) In.

2) 20.

________

Question: 2 Initial plant conditions:

  • Unit 1 is at 100% power.
  • Currently performing a test of Reactor Trip breaker A per 1 -PT-8. 1, Rx. Protection Logic testing.
  • No operator actions have been taken.

REACTOR TRiP BKR RTA

[ REACTOR TRIP J EKR RTB CONTROL ROD SOUD STATE POWER SUPPLY ROD CONTROL RTSYPASS RTBYPASS SKR BYA BKR BYB Which ONE of the following correctly completes the following statements:

1) The Reactor trip and Bypass breakers correctly.
2) With respect to the breaker under test, the operator is required to A. 1) did not
2) initiate a manual reactor trip per 1-E-0, Reactor Trip or SI B. 1) did not
2) locally trip the breaker per 1-FR-S.1, Response to Nuclear Generation/ATWS C. 1) did
2) initiate a manual reactor trip per 1-E-0, Reactor Trip or SI D. 1) did
2) locally trip the breaker per 1-FR-Si, Response to Nuclear Generation/ATWS

Question: 3 Initial Conditions:

  • The Unit is in Cold Shutdown with the Team preparing to start the first RCP in accordance with 1 -OP-RC-001, Starting and Running Any Reactor Coolant Pump.
  • Vacuum assist was unavailable during RCS Loop fill.

The following sequence of events occur:

  • 0900, C RCP started for RCS Vent.
  • 0902, C RCP secured due to low seal Differential Pressure.
  • 0933, C RCP started for RCS Vent.
  • 0938, C RCP secured due to low seal Differential Pressure.
  • 1012, C RCP started for RCS Vent.
  • 1027, C RCP secured due to the loss of both seal injection and thermal barrier flow.

Which ONE of the following states:

1) What is the earliest time the fourth start of the C RCP may be attempted, in accordance with 1-OP-RC-001?
2) When restoring seal injection and thermal barrier cooling to an RCP seal, which is restored first?

A. 1) 1128.

2) Thermal Barrier.

B. 1) 1128.

2) Seal Injection.

C. 1) 1058.

2) Thermal Barrier.

D. 1) 1058.

2) Seal Injection.

Question: 4 Unit I was operating at 100% operation when a failure occurred causing Letdow temper n ature to rise.

Which of the following describes:

1) At what temperature will the Letdown divert valve, 1-CH-TCV-1 143 divert to the VCT?
2) What is the reason for this action?

A. 1) 145°F.

2) Protect Ion Exchanger resin from damage due to high Letdown line temp.

B. 1) 145°F.

2) Mitigate negative reactivity caused by boron release from Demins.

C. 1) 130°F.

2) Protect Ion Exchanger resin from damage due to high Letdown line temp.

D. 1) 130°F.

2) Mitigate negative reactivity caused by boron release from Demins.

Question: 5 Initial Conditions:

  • Unit 1 is being cooled down to Cold Shutdown, with RHR in service.

Which ONE of the following states:

1) The power supply to 1-RH-MOV-1 700, RHR Inlet MOV.
2) The pressure transmitter that supplies the signal for the open (maximum pressure) interlock for 1-RH-MO V-i 700.

A. 1) iHi-2S-8C.

2) i-RC-PT-i402-1, RCS Pressure Wide Range.

B. 1) iHl-2S-SC.

2) i-RC-PT-i403, RCS Pressure Narrow Range.

C. 1) 1A1-1E-4B.

2) i-RC-PT-1402-i, RCS Pressure Wide Range.

D. 1) iAi-1E-4B.

2) i-RC-PT-i403, RCS Pressure Narrow Range.

Question: 6 Given the following conditions:

  • RCS temperature is 175°F.
  • RCS pressure is 305 psig.
  • The PRZR is solid.
  • Charging flow control is in manual.
  • RHR is in service, with the A RHR heat exchanger and 1-RH-P-lA in service.
  • 1-RH-FCV-1 605, RHR H/X bypass, is in AUTO.

The A RHR heat exchanger suddenly develops a 150 gpm tube leak.

With NO Operator actions, which ONE of the following identifies the effect of this malfunction on:

1) Flow through the RHR pump.
2) RCS pressure.

A. 1) Flow remains the same.

2) Pressure lowers.

B. 1) Flow remains the same.

2) Pressure rises.

C. 1) Flow rises.

2) Pressure rises.

D. 1)Flowrises.

2) Pressure lowers.

_________

Question: 7 Initial Conditions:

  • A Large Break LOCA is in progress.
  • The Team is performing 1-E-0, Loss of Reactor or Secondary Coolant.
  • The BOP operator is performing 1-E-0, Attachment 1, System Alignment Verification and is on Step 12 CHECK SI FLOW.

Current Conditions:

  • RCS pressure is 30 psig.
  • HHSI and LHSI pump amps are listed below:

PUMP AMPS 1-CH-P-1A 70 1-.CH-P-1B 69 1-CH-P-1C 30 1-SI-P-lA 265 1-SI-P-lB 275 Which ONE of the following describes the status of the HHSI and LHSI pumps upon compl etion of , step 12.

1) The HHSI pump that will be secured is
2) The number of LHSI pumps that will be running is A. 1) l-CH-P-1C
2) two B. 1) 1-CH-P-1A
2) two C. 1) 1-CH-P-1C
2) one D. 1) 1-CH-P-1A
2) one

Question: 8 Given the following:

  • Unit 1 operating at 100%.
  • The crew experienced a spurious SI signal.
  • Following the SI the Charging pump suction valves have the following positions:

o 1 -CH-MOV-1 11 5B, CHG pump suction from RWST; CLOSED.

o 1.-CH-MOV-1115C, CHG pump suction from VCT; OPEN.

o 1 -CH-MOV-1 11 5D, CHG pump suction from RWST; OPEN.

o 1-CH-MOV-1115E, CHG pump suction from VCT; CLOSED.

  • All other auto SI actions occur as designed.

In the given alignment, the VCT _(1) a source of HHSI flow, and the RWST _(2) a source of HHSI flow.

A. 1)is 2)isnot B. 1)isnot 2)is C. 1)is 2)is D. 1) is not 2) is not

Question: 9 Initial Conditions:

  • 1-RC-PT-1445, PRZR PRESS CNTRL, failed high.
  • The Team has completed the Immediate Actions of 1-AP-31 .00, Increasing or Decrea sing RCS Pressure.

Current Conditions: (2 minutes later):

  • PRT Pressure is 12 psig and stable.

Which ONE of the following identifies:

1) The PRZR PORV that was closed is_____
2) The procedure that will direct returning the PRT to normal pressure is________

A. 1) 1-RC-PCV-1455C

2) 1-AP-31.00, Increasing or Decreasing RCS Pressure B. 1) 1-RC-PCV-1456
2) ARP 1C-F7, PRZR RELIEF TK HI PRESS C. 1) 1-RC-PCV-1455C
2) ARP 1C-F7, PRZR RELIEF TK HI PRESS D. 1) 1-RC-PCV-1456
2) 1 -AP-31 .00, Increasing or Decreasing RCS Pressure

_____

__

Question: 10 Initial Conditions:

  • Unit 1 is at 100%.
  • Tave is at 573 °F.
  • Pressurizer Safety Valve 1-RC-SV-1551A inadvertently fails partially open.
  • S/G B NR level channel 1, 1-FW-Ll-1484, fails high immediately following the Reactor trip.
  • 30 seconds later SI automatically actuates.

Current Conditions (10 minutes later)

  • Plant is stabilized with Tave at 552 °F and RCS pressure at 1910 psig.
  • Pressurizer vapor space temperature is steady at 630 °F.
  • Main Feedwater pumps have tripped, all Feed Reg valves are closed, and all Feed Reg Bypass valves are closed.

Which of the following describes:

1) The Main Feed pumps trip after the_______
2) The Feed Regulating Bypass valves initially closed due to the A. 1) reactor trip, but before the safety injection
2) reactor trip coincident with low Tave B. 1) reactor trip, but before the safety injection
2) safety injection C. 1) safety injection
2) reactor trip coincident with low Tave D. 1) safety injection
2) safety injection

Question: 11 Initial Conditions:

  • Unit 1 reactor operating at 100% power.
  • A tube leak develops in 1-CC-E-1A, A CCHX.

Which ONE of the following states:

1) The effect on CC Surge Tank level.
2) The CW lines that supply SW to the CCHXs.

A. 1) Rise.

2) lA/C.

B. 1) Lower.

2) IBID.

C. 1) Rise.

2) iB/D.

D. 1) Lower.

2) lA/C.

_____

Question: 12 Initial Conditions:

  • Unit 1 and Unit 2 operating at 100%.
  • Charging pump, 1-CH-P-1B started then tripped on lockout, 1-CH-P-IA and C are running.
  • Containment pressure is 16.2 psia and slowly rising.

Current conditions:

  • RO reports loss of 1 H 4160 V bus. EDG 1 did not start.
  • RCS pressure is 1082 psig and slowly lowering.
  • CETC is 528 °F and stable.

Which of the following states:

1) RCP Trip criteria is
2) In accordance with 1-E-1 Basis; the reason RCP5 are tripped is to A. 1) Met
2) Prevent excessive depletion of RCS inventory B. 1) Not met
2) Minimize heat input C. 1) Not met
2) Prevent excessive depletion of RCS inventory D. 1) Met
2) Minimize heat input

___

Question: 13 A ground has developed on DC Panel 1-2, causing 1-.RC-SOy-biB-I and 1-RC-SOV-1 O1B-2, PRZR Vent Valves, to fail open.

Which ONE of the following states:

1) The Master Pressure controller output will
2) The PRZR Vent Valves discharge to the A. 1) rise
2) Primary Vent Pot B. 1) rise
2) Reactor Cavity C. 1) lower
2) Primary Vent Pot D. 1) lower
2) Reactor Cavity

Question: 14 Initial conditions:

  • Unit 1 is at 100% power.
  • The breaker for 1 -SI-MOV-1 885C, LHSI Pump A Recirc Valve, was found open, and could not be reclosed.
  • A Large Break LOCA occurs.

Current conditions:

  • The RWST level is 12.5%.
  • The Team is currently at 1-ES-i .3, Transfer to Cold Leg Recirculation; step 5, Align SI System for Recirc.

Which ONE of the following identifies:

1) Which LHSI pump(s) will automatically align to the RMT mode?
2) Per ES-i .3 CAP, after step 5, the operator will monitor for oscillating LHSI pump amps and flow to check for A. 1) Both LHSI pumps.
2) RWST <3%

B. 1) ONLY the B LHSI pump.

2) sump blockage C. 1) Both LHSI pumps.
2) sump blockage D. i) ONLY the B LHSI pump.
2) RWST <3%

Question: 15 A loss of off-site power has resulted in the trip of both Units.

Which ONE of the following identifies the Pressurizer heaters energized on Unit 1?

A. None.

B. E Group.

C. E and A Groups.

D. A Group.

Question: 16 Given the following:

  • Unit 1 is at 100%.
  • Power Range N-41 fails HIGH.
  • 0-AP-53.00, Loss of Vital Instrumentation/Controls, immediate actions completed.
  • Crew is presently performing 1-AP-4.00, Nuclear Instrumentation Malfunction, Attach ment ito place the failed Power range channel in trip.

Which one of the choices below completes the following statements?

1) In accordance with 1-AP-4.00, Attachment 1; OP L\T channel 1 have to be placed in trip.
2) OP z\T provides protection against A. 1) will
2) DNB B. 1) will
2) high power density C. 1) will not
2) DNB D. 1) will not
2) high power density

Question: 17 Initial Conditions:

  • Unit 1 is heating up per 1-GOP-i .3, RCS Heatup from 345 °F to HSD following a mid-cy cle outage.
  • 40,000 gallons were transferred to the RWST from the blender.
  • RWST Refrigeration Unit 1A is tagged out for compressor breaker replacement.
  • RWST Refrigeration Unit 1 B is in operation.
  • RWST temperature is 42°F on channel 1 and channel 2; (1-CS-TI-i OOA and bOB).

Current Conditions (5 mm. later)

  • Operator reports RWST Refrigeration Unit 1 B has a low oil pressure trip and he is unable to reset. Operator requests maintenance support.
  • Unit 1 RWST parameters are as follows:

Temp. Boron 44°F 2275 ppm In accordance with Tech Specs 3.3.A. 1, RWST; which of the following completes the statem ent.

With the current conditions the RWST LCO temperature limit is _(1), and the RWST Boron LCO limit is _(2)....

A. 1) met

2) not met B. 1) not met
2) met C. 1) not met
2) not met D. 1) met
2) met

_____

Question: 18 Initial Conditions:

  • Unit 1 is at 100% power when a large break LOCA occurs.
  • Containment pressure peaks at 45 psia.

Current Conditions:

  • The crew is at 1-El, Loss of Reactor or Secondary Coolant, step 17 and is attempting to open 1-lA-TV-i 00.
  • The RO reports that Containment pressure is slowly lowering and is as follow s:

o 1-LM-Pl-100A 15 psia.

o 1-LM-Pl-100B 15 psia.

o 1-LM-Pl-100C 14 psia.

o 1-LM-Pl-100D 15 psia.

  • 1-Pl-IA-101, CTMT INST AIR, indicates 25 psig.
  • The operator has depressed both CLS Train A (B) RESET buttons.
  • SI has been reset.

Which one of the following correctly completes the statements below:

1) After depressing both CLS RESET buttons, CLS reset.
2) When the operator attempts to open 1-IA-TV-i 00, the valve will A. 1) is 2) remain closed B. 1) is not 2) open C. I) is not 2) remain closed D. 1) is 2) open

Question: 19 The reactor is operating at 100% power when the following sequence of events occur:

  • Initial D Bank rod height 225 Steps.
  • The RO is performing 1-OPT-RX-005, Control Rod Assembly partial Movem ent, for D Control Bank.
  • Annunciator G-A6, Rod Cont Sys Urgent Failure is received when Contro Bank l D begins to move inward.
  • Rod Control In-Hold-Out switch placed in Hold.

The following indications are noted by the RO:

  • Control Bank D, Group 1 Step counter indicates 224 Steps.
  • Control Bank D, Group 2 Step counter indicates 222 Steps.
  • Control Bank D, CERPI Group 1 indicates 224 Steps.
  • Control Bank D, CERPI Group 2 indicates 222 Steps.

Which ONE of the following identifies the:

1) Power Cabinet affected by the Urgent Failure.
2) The procedure that would need to be entered to mitigate the malfunction.

A. 1) Power Cabinet 1BD.

2) 0-AP-1 .00, Rod Control System malfunction.

B. 1) Power Cabinet 1BD.

2) 0-AP-1 .02, Individual Rod Position Indicators.

C. 1) Power Cabinet 2BD.

2) 0-AP-1.00, Rod Control System malfunction.

D. 1) PowerCabinet2BD.

2) 0-AP-1.02, Individual Rod Position Indicators.

Question: 20 With Unit 1 at 100% power, an inadvertent phase Ill containment isolation occurs. Approximately 15 minutes later, the following RCP temperatures exist:

A RCP

  • Upper Motor radial bearing 185°F
  • RCP lower bearing Seal Water Temp 215°F
  • Upper Motor radial bearing 180°F
  • RCP lower bearing Seal Water Temp 210°F
  • Stator winding 305° F In order to mitigate these plant conditions, the crew will monitor RCP temper atures using (1) ,then initiate 1-E-0, Reactor Trip or Safety Injection, trip the reactor, and stop (2)

A. 1) 1-AP-15.00, Loss of Component Cooling

2) C RCP B. 1) 1-AP-15.00, Loss of Component Cooling
2) A RCP C. 1) 1-AP-9.00, RCP Abnormal Conditions
2) A RCP D. 1) 1-AP-9.00, RCP Abnormal Conditions
2) C RCP

Question: 21 Unit 2 initially operating at 100% power, when the following occurs:

  • The Reactor is tripped and Safety Injection actuated.
  • The RCPs have been tripped due to low RCS subcooling.
  • RVLIS Full Range Indicates 42% and stable.
  • RCS THOT indicates 650 °F and stable.
  • CETCs indicate 660 °F and rising.

Which ONE of the following describes:

1) The temperature indication used on the Core Cooling Status tree.
2) The status of the Core Cooling Status Tree.

A. 1) CETC temperature.

2) Orange.

B. 1) CETC temperature.

2) Red.

C. 1)THOT.

2) Orange.

D. 1) THOT.

2) Red.

Question: 22 Unit 2 is performing a Reactor Startup following a forced outage. Shutdo wn banks are fully withdrawn.

During the outage, a substantial amount of work had been performed in the Pressurizer Cubicle in Containment.

Given the following data:

Initial Condition Parameter Condition 1 Day later PRT Level 78% 78%

PRT Pressure 6 psig 6 psig PRT Temperature 82°F 84°F Weighted AVG CTMT Temperature 972°F 101 5°F A PRZR SV Temperature 129°F 152°F B PRZR SV Temperature 140°F 160°F C PRZR SV Temperature 121°F 149°F PRZR PORV Temperature 121°F 148°F Shutdown bank CERPI Indication No change in CERPI Which ONE of the following states the cause for the changes noted betwee n the Initial Conditions and the Conditions found 1 Day later?

A. Cubicle Ventilation Damper position change.

B. CRDM Fan Trips.

C. B PRZR SV Leaking.

D. PRZR PORV leaking.

Question: 23 Initial Conditions:

  • Unit 1 at 50% power and ramping up to 100% in accordance with GOP-i .5, Unit Startup, 2% to Max Allowable Power.
  • Rod Control in manual due to hunting in automatic.

Current Conditions:

  • Median Tave fails to a stable indication of 550 °F.
  • No Operator Actions have been taken.

Which ONE of the following states:

1) The Pressurizer level control setpoint is
2) The automatic charging low flow limit is A. 1) 24.8%
2) 30 gpm B. 1) 25.8%
2) 30 gpm C. 1) 24.8%
2) 25gpm D. 1) 25.8%
2) 25 gpm

Question: 24 Unit 2 is operating at 100% power with Chilled CC in service to containment.

  • An operator is verifying the Plant Computer System displays and indications are functioning properly using the laptop computer at the Auxiliary Shutdown Panel.
  • 2-CD-REF-i, Unit 2 Turbine Building Chiller trips.

Which ONE of the following states:

1) Containment partial pressure will
2) Containment saturation temperature is sensed at the_______

A. 1) lower

2) Containment air recirculation fan discharge B. 1) rise
2) Containment air recirculation fan discharge C. 1) rise
2) Containment dome D. 1) lower
2) Containment dome

_____

__

Question: 25 Initial Conditions:

  • Unit 1 is in Cold Shutdown, at 190 °F, on RHR, preparing to take the pressu rizer solid.
  • A RHR pump is running with the A RHR HX in service.
  • A CC pump running on Unit 1; D CC pump running on Unit 2. CC is cross-t ied.

Current Conditions:

  • C RSST trips and locks out.

Which ONE of the following states:

1) The status ofA RHR pump.
2) The CC pump is running on Unit 1, and the CC pump is running on Unit 2.

A. 1) Running.

2) A; D B. 1) Tripped.

L;

2) C C. 1) Running.
2) B; C D. 1) Tripped.
2)  ?;

Question: 26 Given the following:

  • A Large Break LOCA has occurred on unit 1.
  • An operator has been assigned to perform 1-E-O, Reactor Trip or SI; Attachment 4, CLS Component verification.
  • When checking the valve lineup the operator notices that the red and green light bulbs for 1-SW-MOV-104A, RSHX A SW INLET are NOT lit.

Which one of the following indications does 1 -E-O, Attachment 4 direct the operator use to verify that there is adequate flow through the heat exchanger?

A. 1-SW-MOV-103A, RS HX A&D SW SUPPLY; and 1-SW-MOV-105A, RSHX A SW OUTLET red lights LIT.

B. Annunciator 1A-D6, RS HX 1A RAD MON PP NO FLOW is NOT LIT.

C. Flow indication on 1-SW-Fl-i 06A, RS HX A SW Outlet Flow.

D. 1-SW-P-5A, RS SW Radiation Monitor Sample pump red light is LIT.

_____

_____

__ _

Question: 27 Unit 1 is operating at 100% with the following conditions:

  • 1-OPT-RC-10. 0, Computer leak Rate Program has trended a rise in Uniden tified leakage of 0.1 gpm.
  • A Containment entry has been performed and the leak has been identified on the A SG Primary manway.
  • HP has requested the Unit 1 Iodine filter fans, 1-VS-F-3A and 3B, be placed in service.

Which ONE of the following identifies:

1) The operator will place the control switch for the Iodine Filter Fans to to start the fans.
2) The Unit 1 Iodine Filter Fans are operated at the Ui Main Control Room panel.

A. 1) Auto

2) Ventilation B. 1) Auto
2) Post Accident Monitoring C.1)On
2) Post Accident Monitoring D. 1) On
2) Ventilation

___

_____

Question: 28 Initial Conditions:

  • Unit 1 is at HSD with all RCPs running.
  • Preparations for Unit startup are in progress per 1-GOP-1.4, Unit Startup.
  • The Master Pressure Controller (MPC) and spray valve controllers are all in auto and set to maintain 2235 psig.
  • Pressurizer pressure indicates 2250 psig on 1-RC-Pl-1444, and 1-RC-Pl-144 5.

Current Conditions (60 sec):

  • Pressurizer pressure is 2130 psig.
  • 1-RC-PC-1444G, PRZR Spray from Loop A, 1-RC-PCV-1455A indicates 100%.
  • 1-RC-PC-1444H, PRZR Spray from Loop C, 1-RC.-PCV-1455B indicates 0%.
  • 1-RC-PC-1444J, PRZR PRESS Master CNTRL, indicates 0%.

Which ONE of the following identifies:

1) The POT setting of the Master Pressure Controller for 2235 psig is
2) The expected operator action associated with the failure in accordance with 0-AP-53.00, Loss of Vital Instrumentation/Cont is to place in manual and close the spray valve.

A. 1) 7.45

2) 1-RC-PC-1444G, PRZR Spray from Loop A, 1-RC-PCV-1455A B. 1)6.68
2) 1-RC-PC-1444G, PRZR Spray from Loop A, 1-RC-PCV-1455A C. 1)7.45
2) 1-RC-PC-1444H, PRZR Spray from Loop C, 1-RC-PCV-1455 D. 1)6.68
2) 1-RC-PC-1444H, PRZR Spray from Loop C, 1-RC-PCV-1455

____

Proposed Question: 29 Given the following:

  • Pressurizer level channel transmitter 1-RC-LT-459, Pressurizer Level Protec tion Channel I, is the upper channel.
  • The reference leg of 1-RC-LT-459 develops a slow leak.

Which ONE of the following describes:

1) As a result of the reference leg leak, the level indication on 1 -RC-LI-1459 will
2) In accordance with D-AP-53.DO, Loss of Vital Instrumentation/Controls, the operator required to isolate letdown for this failure.

A. 1) rise

2) is not B. 1) rise
2) is C. 1) lower
2) is not D. 1) lower
2) is

____

Question: 30 Initial Conditions:

  • Unit 1 operating at 100% power.
  • Crew is performing 1-E-0, Reactor Trip or Safety Injection, immediate actions.
  • Both reactor trip breakers remain closed after E-0 step 1 performed.

Current Conditions:

  • An operator has just been dispatched to open reactor trip breakers per 1-FR-S.1, step 8.
  • Gamma-Metrics is reading 20%.
  • Power Range NI channels are all reading 15%.
  • Containment pressure is 22 psia and rising.

Which of the following completes the statements:

1) In accordance with 1-E-0, Reactor Trip or SI, Background; if any reactor trip breaker and associated bypass breaker is open, and neutron flux has decreased to less than 5

%, the reactor considered tripped.

2) In accordance with 1-FR-Si, Response to Nuclear Generation/ATWS; the instrumentation the crew should be using to monitor neutron flux is A. 1) is
2) Power Range NI channels B. 1) is not
2) Gamma-Metrics C. 1) is
2) Gamma-Metrics D. 1) is not
2) Power Range NI channels

_

Question: 31 Initial Condition:

  • Unit 2 Containment pressure has just reached atmospheric.
  • The Team is preparing to place Unit 2 Containment on purge using 1-VS-F

-58A, in accordance with 2-OP-VS-OO1, Containment Ventilation.

  • The Personnel and Equipment Hatches are closed.

Which ONE of the following completes the following statement?

1) An allowable configuration would consist of
2) The filter is used in the flowpath.

(REFERENCE PROVIDED)

A. 1) Containment Purge and Fuel Building Exhaust

2) CAT II B. 1) Containment Purge Only
2) CATI C. 1) Containment Purge and Fuel Building Exhaust
2) CATI D. 1) Containment Purge Only
2) CATII

Question: 32 Given the following:

  • Unit 2 is currently stable at 75% power.
  • The B Feed Reg Valve demand begins to slowly lower due to an instrument failure.

Which ONE of the following identifies:

1) The effect this will have on the indicated power by Instantaneous Calorimetric.
2) The procedure used to respond to this event.

A. 1) Lowers.

2) 2-AP-21 .00, Loss of Main Feedwater Flow.

B. 1) Rises.

2) 2-AP-21 .00, Loss of Main Feedwater Flow.

C. 1) Lowers.

2) 0-AP-53.00, Loss of Vital Instrumentation/Controls.

D. 1) Rises.

2) 0-AP-53.00, Loss of Vital Instrumentation/Controls.

Question: 33 The Operating Team is in E-3, Steam Generator Tube Rupture and has compl eted RCS cooldown and depressurization. CHG pump suction has been aligned to the VCT.

The following Unit conditions exist:

  • PRZR level is 35% and slowly rising.
  • S/G levels are as follows:

o A S/G is 68% and lowering.

o B S/G is 33% and rising.

o C S/G is 32% and rising.

  • RCS pressure is 985 psig.
  • S/G pressures are as follow:

o A S/G is 1000 psig and lowering.

o B S/G is 670 psig and rising.

o C S/G is 650 psig and rising.

Which ONE of the following is the MINIMUM actions required to be taken by the Operating Team in accordance with step 36 of E-3?

(REFERENCE PROVIDED)

A. Depressurize RCS and raise CHG flow.

B. Lower CHG flow and depressurize the RCS.

C. Turn on PRZR heaters.

D. Raise CHG flow.

Question: 34 Given the following:

  • Unit 1 is at 100 % power.
  • A complete separation of the Main steamline piping upstream of the MSR Steam Supply to the A & C MSRs (30 pipe) occurs.

Which ONE of the following describes the effect this will have on the...

1) Main Feed pumps.
2) Main Steam Trip valves.

A. 1) Remain running.

2) Remain open.

B. 1)Trip.

2) Remain open.

C. 1) Remain running.

2) Close.

D. 1)Trip.

2) Close.

Question: 35 Initial Conditions:

Unit 1 operating at 100% power.

  • A Steam line in Unit 1 alleyway ruptures.
  • Station Service buses are lost on swap-over to Reserve Station Service Transf ormers following a manual reactor trip.
  • Individual MSTV close switches on Benchboard fail to operate.
  • MSTV Emergency close switch on Vertical Board fails to close the MSTV s.

Which one of the following states:

1) The redundant MSTV Emergency Close Switch, is located on the Appen dix R panel in
2) Operation of this switch the MSTV close SOVs.

A. 1) Unit 1 ESGR

2) Energizes B. 1) Unit 1 ESGR
2) Deenergizes C. 1) Unit 2 ESGR
2) Energizes D. 1) Unit 2 ESGR
2) Deenergizes

Question: 36 Unit 1 is placing the Unit on-line in accordance with 1-OP-TM-001, Turbine - Generator Startup to 20%

- 25% Turbine Power.

  • Steam Dumps are in Auto in steam pressure mode.
  • Reactor Power has been raised to 8%.
  • P-7 NIS POWER RANGE AND TURBINE POWER < 10% is LIT.
  • When the second Generator output breaker, OCB-G1T240 is closed, Annun ciator iF-El, GEN BACKUP LOCKOUT REL TRIP, comes in due to a fault.

Which one of the following correctly describes the effect this will have on:

1) The reactor.
2) Main Generator output breakers.

Reactor Main Gen output breakers A. trip trip open after 30 seconds B. not trip trip open after 30 seconds C. trip trip open immediately D. not trip trip open immediately

____

Proposed Question: 37 Initial Conditions:

  • The team was performing 1-E-0 in response to a faulted steam generator outside containment.
  • Upon transition from 1-E-0, the STA reported a red path on HEAT SINK.
  • The team has entered 1-FR-Hi, Loss of Secondary Heat Sink.

Current Conditions

  • SG levels are A- 0% WR, B- 13% WR, C- 14% WR (all lowering).
  • RCS Thot 640°F and rising.
  • Pressurizer level 80% and rising
  • Pressurizer pressure 2345 psig and rising.
  • 1-RC-PCV-1455C was cycling open/close and is now open.

Which ONE of the following states:

1) In accordance with 1 -FR-H. 1, Continuous Actions Page, RCS Bleed and Feed required.
2) What is the reason for the Pressurizer PORV remaining open?

A. 1)is not

2) RCS expansion due to Loss of Heat sink.

B. i)is

2) Pressurizer fill due to safety injection.

C. i)is

2) RCS expansion due to Loss of Heat sink.

D. i)isnot

2) Pressurizer fill due to safety injection.

_____ _____

_________

Question: 38 Initial Conditions:

  • Unit 1 operating at 100% power.
  • A SGTR occurs on the A SG, the reactor is tripped and safety injection actuated.
  • The Team has completed the Rapid Cooldown of I -E-3, Steam Generator Tube Rupture.
  • The Air Ejector discharge has been re-aligned to Containment.

Current Conditions:

  • The A SG faults inside of Containment.
  • Hi and Hi-Hi CLS have actuated.

Which ONE of the following states:

1) The position of 1-SV-TV-102A, AE DISCH TO CTMT SFGD TV, is
2) The position of 1-SV-TV-102, AE DISCH TO CTMTTB TV, is A. 1) open
2) open B. 1) closed
2) closed C. 1) closed
2) open D. 1) open
2) closed

Question: 39 ECA-O.O, Loss of all AC Power, Step 24, directs the operator to:

Depress urize all Intact SGs to 300 psig Which ONE of the following describes the reason for stopping the pressure reduction at 300 psig?

A. Prevent losing pressurizer level.

B. Minimize inventory loss out of RCP seals.

C. Prevent voiding in the Reactor Vessel upper head.

D. Prevent SI Accumulator Nitrogen into the RCS.

_____

Question: 40 Initial Conditions:

  • Unit 1 at 100%

o 1 K-B8, UPS SYSTEM 1 B TROUBLE.

o 1C-Bi, RCP lB CC RETURN LO FLOW.

o 1 E-G4, RX TRIP CH-2 PRZR LO PRESS.

Current Conditions:

  • The non-licensed operator dispatched reports the red INVERTER SUPPLYING LOAD light is NOT lit for UPS lB-i.
  • Indication on 1-FW-FCV-1488 (B FRV Controller) is:

o Auto Light NOT LIT.

o Manual Light NOT LIT.

  • The control room team is currently performing actions per 1 K-B8, UPS System 1 B Trouble.

Which one of the following describes:

1) B S/G feed flow be controlled by using the pushbuttons on the FRV controller.
2) The Abnormal Procedure that should be utilized is A. 1) can not
2) 1-AP-1 0.04, Loss of Vital Bus IV B. 1)can
2) 1-AP-i 0.02, Loss of Vital Bus II C. 1)cannot
2) 1-AP-10.02, Loss of Vital Bus II D. 1)can
2) 1-AP-1 0.04, Loss of Vital Bus IV

Question: 41 Which ONE of the following breakers, if open, will cause a Vital Bus UPS Static Switch to shift to the alternate source?

A. Battery Charger AC Input.

B. Battery Charger DC Output.

C. Inverter DC Input.

D. Battery Bus DC Input.

Question: 42 Unit 1 is currently at 60% power and is performing a startup.

1-FW-P-1B, B Main Feed Pump, is running.

Shortly after starting 1-FW-P-1A, A Main Feed Pump, the operator observes the Main Feed Pump tripping.

Which ONE of the following conditions could have caused 1-FW-P-1A, A Main Feed Pump trip?

to A. Feed pump Lube oil pressure at 8 psig.

B. C Station Service Bus voltage at 68%.

C. Feed flow < 3000 gpm and Recirc valve, 1 -FW-FCV-i 50A not fully open.

D. Feed pump Suction pressure at 430 psig.

Question: 43 Given the following:

Power from the associated rack in the relay room, to the A FRV controller, 1-FW-FCV-1478 is lost.

With the conditions stated, which of the following answers the questions listed below:

1) What is the effect on the output of the controller?
2) Can this controller be controlled from the Main Control Room?

A. 1) Shift to manual and output will remain the same as prior to loss of power.

2) Yes.

B. 1) The output of the controller will raise to 100% demand.

2) Yes.

B. 1) The output of the controller will raise to 100% demand.

2) No.

D. 1) Shift to manual and output will remain the same as prior to loss of power.

2) No.

Question: 44 Given the following:

  • An accidental gaseous radwaste release has occurred in the Waste Gas Decay Tank Room.
  • A Site Area Emergency has been declared due to dose at the site boundary of 200 mRem/hr.
  • Radiation protection has determined that radiation dose level in the room is 1,000 mRem/hr.

A Surry Power Station worker assigned to enter the room has a current year-to-date TEDE of 700 mRem.

The MAXIMUM total time the worker is allowed RCA access, to perform the work, with NO extensions is hour(s)?

A. 0.50 B. 1.00 C. 1.85 D. 2.30

Question: 45 The team is performing 1-E-0, Reactor Trip or Safety Injection, with plant conditions as follows:

  • Containment pressure is 27 psia and rising slowly.
  • A SIG parameters o Pressure- 650 psig and lowering slowly.

o Level- 57% WR and lowering slowly.

  • B SIG parameters o Pressure 120 psig and lowering rapidly.

o Level- 15% WR and lowering rapidly.

  • C SIC parameters o Pressure 630 psig and lowering slowly.

o Level- 56% WR and lowering slowly.

  • Pressurizer level 0%.
  • Pressurizer pressure 1200 psig and lowering.
  • RCS Tave- 512 °F and lowering at a rate of 120 °FIhr.

Which ONE of the following states the minimum required AFW flow to the S/Cs in accord ance with E-0, Reactor Trip or Safety Injection, Attachment 8?

A. A SIG- 100 gpm; B S/G- 100 gpm; C S/G-100 gpm.

B. A S/G- 175 gpm; B SIC- 0 gpm; C S/G- 175 gpm.

C. A S/G- 60 gpm; B SIG- 60 gpm; C SIG- 60 gpm.

D. A S/G- 225 gpm; B S/C- 0 gpm; C SIG- 225 gpm.

Question: 46 In accordance with 1-AP-21.01, Response to AFW Check Valve Backleakage, which ONE of the following identifies:

1) The temperature on an AFW pump casing where the pump is considered vapor bound.
2) Which of the AFW pumps is aligned and cooled FIRST if all AEW pumps are found to be vapor bound?

A. 1) 200°F.

2) Motor Driven.

B. 1) 200°F.

2) Turbine Driven.

C. 1) 165°F.

2) Motor Driven.

D. 1) 165°F.

2) Turbine Driven.

Question: 47 Initial Conditions:

Unit 1 A DC Bus is lost due to a fault, causing a reactor trip.

Current Conditions: (11 minutes following the reactor trip)

A Large Break LOCA occurs on Unit 1.

The Team decides to locally start 1-CS-P-lA, A CS Pump.

Which ONE of the following identifies:

1) The red breaker position indicating light be used by the control room team to identify that 1-CS-P-lA has been successfully started.
2) 1-CS-P-lA breaker, 1-EP-BKR-14H5, have overcurrent trip protection.

A. 1) can

2) does not B. 1) can
2) does C. 1) cannot
2) does D. 1) cannot
2) does not

_____

_ _____

__

Question: 48 Initial Conditions:

  • Unit 1 is operating at 100%.
  • 1-SW-P-i CA, CHG PUMP SW PUMP, is running in HAND, 1-SW-P-lOB, CHG PUMP SW PUMP is in Auto.
  • 1-CH-P-1C, CHARGING PUMP is running.

Current Conditions:

  • Reactor Operator reports the following:

o 1-SW-P-bA has tripped, and i-SW-P-lOB remains in standby.

o Highest reading Charging pump bearing temperature is 179°F and rising.

Which ONE of the following describes:

1) The Reactor Operator can monitor Charging pump SW flow on the
2) 0-AP-1 2.00, Service Water Abnormal, states that the affected Charging pump should be secured once bearing temperature exceeds a minimum of A. 1) Vertical board 2)195°F B. 1) PCS 2)185°F C. 1)PCS 2)195°F D. 1) Vertical board 2)185°F

__________

Question: 49 Given the following conditions:

  • Unit 1 tripped from 100% power due to loss of on-site and off-site power.
  • The team is performing 1-ECA-0.0, Loss of all AC Power.
  • The AAC EDG has not been loaded on an emergency bus.

Which ONE of the following identifies:

1) The power source for Unit 1 Annunciator System is
2) The Black Battery supplies the A. 1) A Station Battery
2) Seal Oil Backup Pump B. 1) B Station Battery
2) Emergency Oil Pump C. 1) A Station Battery
2) Emergency Oil Pump D. 1) B Station Battery
2) Seal Oil Backup Pump

Question: 50 Which one of the following supplies the DC control power to #1 EDG output breaker, 1 -EP-BKR-1 5H3?

A. A DC bus.

B. B DC bus.

C. Black battery DC bus.

D. #1 EDG DC system.

Question: 51

  • O-VSP-C8, Fire Detected, has alarmed with Unit 1 ESGR indicated on the fire display panel.
  • The BOP has dispatched an operator to investigate Unit 1 ESGR for a fire.

Which ONE of the following identifies:

1) The maximum time limit for the operator to report fire status.
2) The reason for this time limit in accordance with O-VSP-C8.

A. 1) 5 minutes.

2) Ensure adequate time for EAL classification and transmission, if required.

B. 1) 5 minutes.

2) Prompt response is necessary to prevent significant damage.

C. 1) 3 minutes.

2) Ensure adequate time for EAL classification and transmission, if required.

D. 1) 3 minutes.

2) Prompt response is necessary to prevent significant damage.

________

____

Question: 52 Initial Conditions

  • Both units at 100% power.
  • The Control Room is evacuated due to a Limiting Main Control Room Fire.
  • All actions per 0-FCA-001, Limiting MCR Fire were taken prior to evacuation.

Current Conditions (20 minutes later)

  • Operator dispatched to perform 0-FCA-1 1.0, Remote Monitoring.
  • Operator reports that Unit 1, Neutron flux indicators are reading as shown below:

Operator reports the following additional NEUT FLUX NEUT FLUX 1-NM-NFI-190A2 nformation: 1-1iMMFI-190B2 10 CO

  • 1-NM-NFI-190A2 has been steady at presentvalueforlast5 minutes.
  • 1-NM-NFI-190B2 has lowered from 1 x iO to present value over last 5 R 102 minutes. io S

P O

10°

.7 p 10 10I 5 17e4 375.7 Unit Supervisor directs the operator to switch 1 -NM-NFl-i 90A & B to the alternate power supply using the Appendix R switch.

Which of the following describes:

1) The Nuclear Instrument indication at the Remote Monitoring panel as expected.
2) The location of the alternate power App R switch for 1-NM-NFl-i 90A & B is located in the A. 1) is not
2) Cable Tray Room Unit 2 B. i)is
2) Cable Tray Room Unit 2 C. 1)isnot
2) Emergency Switchgear Room Unit 2 D. 1)is
2) Emergency Switchgear Room Unit 2

Question: 53 Both Units are operating at 100% power.

Which ONE of the following water sources is collected directly into the High/Low Level Liquid Waste Tanks prior to transfer to the SRF?

A. Laundry Drains.

B. Contaminated Drain Tank.

C. Auxiliary Building sump pump discharge.

D. VCT Drain.

Question: 54 Given the following:

  • Unit 1 is at 100%, Unit 2 is in a Refueling Shutdown.
  • l-GW-RM-130A, Rad Monitor Process Vent Particulate indication spiked high causing the following alarms:

o 0-RMA-C5, Process Vent Rad Mon Trbl.

o 0-RMA-C6, Process Vent Part Alert I Hi.

Which ONE of the following describes the automatic plant response?

A. 1-IA-TV-lOlA, and 1-IA-TV-biB, Unit 1 Containment Instrument Air compressor suctions will swap to outside air.

B. i-CV-P-1A, and i-CV-P-i B, Unit 1 Containment vacuum pumps will trip.

C. i-SV-TV-103, Air Ejector Discharge to Vent-Vent Trip valve will automatically close.

D. i-GW-FCV-160, Unit 1 vacuum pump discharge valve, will automatically close.

Question: 55 Unit 2 is shutdown and has been borated to CSD boron concentration in preparation for Cooldown to CSD for a Refueling outage.

Chemistry has notified the Team that the RCS crud burst has been initiated.

Which ONE of the following describes:

1) The FIRST Radiation monitor that will detect the increased RCS Activity caused by the crud burst.
2) Which CVCS filter is monitored for differential pressure during the crud burst cleanup?

A. 1) Letdown Radiation monitor.

2) Reactor Coolant filter.

B. 1) Letdown Radiation Monitor.

2) Letdown filter.

C. 1) Auxiliary Building Control Area Radiation Monitor.

2) Reactor Coolant filter.

D. 1) Auxiliary Building Control Area Radiation Monitor.

2) Letdown filter.

Question: 56 Given the following:

  • Unit 1 and Unit 2 are both operating at 100%.
  • You are preparing for a Performance Test of Charging Pump SW pump, 1-SW-P-bA Appendix R controls.
  • An operator needs to be stationed locally at 1-SW-P-i OA to observe the pump, and a second operator at the Appendix R controls for 1-SW-P-1OA to start and stop the pump.

The Charging Pump SW pump, 1-SW-P-iDA is located inside (1), and the Appendix R controls for i-SW-P-bA are located inside Unit 1(2) room.

A. 1) MER 4 2) Emergency Switchgear B. 1) MER 4 2) Cable Vault C. 1) MER 3 2) Cable Vault D. 1) MER 3 2) Emergency Switchgear

Question: 57 Which ONE of the following states:

1) The minimum canal level per Tech Spec 3.14, Circulation and Service Water Systems.
2) The channel coincidence required to cause BC SW isolation?

A. 1) 23.5 feet.

2) 2/4 Channel.

B. 1) 23.5 feet.

2) 3/4 Channels.

C. 1) 23.0 feet.

2) 2/4 Channels.

D. 1) 23.0 feet

2) 3/4 Channels.

Question: 58 A severe thunderstorm has caused perturbations on the grid. 0-AP-1 0.18 has been entered due to grid instabilities Initial Conditions:

  • Unit 1 is at 100% power, Unit 2 is shutdown.
  • The A and B Voltage regulators are in AUTO.
  • The A Voltage Regulator is in service.
  • Power System Stabilizer (PSS) is in service.
  • 55 MVARS Out.

Current Conditions:

  • The Operator reports a large rise in MVARS (Out).

o 1J-A8, OVEREXCITATION LIMIT.

o 1J-B7, VREG CHANNEL A LOCAL ALARM.

Which of the following occurs if the A Voltage Regulator is unable to lower Generator voltage in its current mode?

A. A Voltage Regulator will shift to the V/Hz mode to control voltage. The B channel will remain in standby.

B. A Voltage Regulator will trip into Emergency Manual. The B channel will automatically assume control.

C. A Voltage Regulator will trip into Emergency Manual to control voltage.

The B channel will remain in standby.

D. A Voltage Regulator will shift to the V/Hz mode to control voltage. The B channel automatically assume control.

Question: 59 Which ONE of the following describes the operation of Instrument Air compressor 1-IA-C-i when in AUTO?

A. Compressor will start and LOAD when pressure drops to 90 psig.

Compressor will then UNLOAD and LOAD at 105 psig and 95 psig, respectively.

B. Compressor will start and LOAD when pressure drops to 95 psig.

Compressor will then UNLOAD and LOAD at 105 psig and 95 psig, respectively.

C. Compressor will start and LOAD when pressure drops to 100 psig.

Compressor will then UNLOAD and LOAD at 110 psig and 100 psig, respectively.

D. Compressor will start and LOAD when pressure drops to 90 psig.

Compressor will then UNLOAD and LOAD at 110 psig and 100 psig, respectively.

Question: 60 Initial Conditions:

  • Unit 1 was operating at 100%.
  • Containment pressure peaks at 45 psia.

Current Conditions:

  • RWST level has just reached 60% one minute ago and is lowering.
  • Containment pressure is 22 psia and lowering.

Which ONE of the following describes:

1) The status of Recirc Spray pumps.
2) The minimum number of Containment Spray and Recirc Spray pumps needed to cool and depressurize the containment to < 1 psig in <60 minutes following a Design Basis LOCA.

A. 1) Both Outside Recirc Spray pumps are running, Inside Recirc Spray pumps are off.

2) One Containment Spray pump and two Recirculation Spray pumps.

B. 1) Both Inside Recirc Spray pumps are running, Outside Recirc Spray pumps are off.

2) One Containment Spray pump and two Recirculation Spray pumps.

C. 1) Both Outside Recirc Spray pumps are running, Inside Recirc Spray pumps are off.

2) One Containment Spray pump and Recirculation Spray pump.

D. 1) Both Inside Recirc Spray pumps are running, Outside Recirc Spray pumps are off.

2) One Containment Spray pump and one Recirculation Spray pump.

Question: 61 The reactor is starting up following a refueling outage, in accordance with 1-GOP-i .8. Unit Startup, HSD to Max Allowable Power.

Which ONE of the following identifies:

1) The flowpath used when diluting to critical in accordance with 1-OP-CH-007, Blender Operations.
2) The method used to stabilize reactor power at 1 Q 8 amps.

A. 1) DilutetotheVCT Inlet.

2) Boration I Dilution.

B. 1) DilutetotheVCT Inlet.

2) Rods.

C. 1) Alternate dilute to CH pump suction.

2) Boration I Dilution.

D. 1) Alternate dilute to CH pump suction.

2) Rods.

Question: 62 Given the following conditions:

  • Unit 1 is at 12% power.
  • The team is currently performing 1-GOP-i .8, Unit Startup, and are checking trip status lights in preparation for blocking Intermediate Range and Power-Range (LO Setpoint) trips.
  • The team depresses Intermediate-Range and Power-Range (LO Setpoint) Block pushbuttons.
  • Trip Status lights are as follows:

Light# Noun name As-found Required A3 P-b NIS PWR RGE> 10% LIT LIT Ci NIS PWR RNG LO SP TRIP BLOCKED NOT LIT LIT

  • The team notes that status light Ci is in wrong state, checks bulb and finds bulb is good.

Which ONE of the following describes how the plant will respond if the team continues to raise power.

1) At what power will the reactor trip?
2) What is the coincidence for the reactor trip?

A. 1)35%. 2)1/4.

B. 1)23%. 2)2/4.

C. 1)23%. 2)1/4.

D. 1)35%. 2)2/4.

Question: 63 An Operator has been briefed and sent to perform 1-OPT-FW-OO1, Motor Driven Aux Feedwater Pump 1 -FW-P-3A. While placing 1 -FW-P-3A in the proper lineup for the test, a typographical error for a valve mark number is discovered.

Which ONE of the following completes the following statement regarding the actions to be perfomed in accordance with AD-AA-1 00, Technical Procedure Process Control, to address the issue?

After making a pen and ink change, the Operator_(1).. required to have a supervisor initial and date the correction before proceeding. After completing the OPT, a procedure change request (FIP)

(2)_ required to be processed.

A. (1)is (2) is not B. (1)isnot (2) is not C. (1)isnot (2) is D. (1)is (2) is

__________

Question: 64 Unit 1 is currently Shutdown, and making preparations to perform 1 -OPT-ZZ-0O1, ESF Actuation with Undervoltage and Degraded Voltage 1H Bus. This procedure is an ICCE category Ill.

In accordance with OP-AA-1 06, Infrequently Conducted or Complex Evolutions, select the answer that correctly completes the following statements.

1) Specific criteria for terminating the test and contingency plans for unexpected occurrences required per Attachment 2 of OP-AA-1 06.
2) The is specifically responsible for the safe operation of the station during performance of the test.

A. 1) is

2) Senior Operations Manager B. 1) is not
2) Shift Manager C. 1) is not
2) Senior Operations Manager D. 1) is
2) Shift Manager

Question: 65 Given the following:

  • Unit 1 is operating at 100% power.
  • A Subatmospheric Containment Entry is to be made in accordance with VPAP-01 06, to identify the source of a step change in Unidentified leakage of +0.4 gpm.
  • The Shift Manager has entered Action Level 3 for RCS leakage and has notified the OMOC.

Which ONE of the following identifies:

1) The minimum level of authority for the containment entry is (1).
2) The HP Shift Supervisor or designee must _(2)_.

A. (1) Plant Manager (2) Sign on to the In-Core Detector tagout B. (1) Plant Manager (2) Verify In-Core Detectors in storage location C. (1) Director, Nuclear Safety and Licensing (2) Sign on to the In-Core Detector tag out D. (1) Director, Nuclear Safety and Licensing (2) Verify In-Core Detectors in storage location

Question: 66 initial Conditions:

  • Unit 1 is in a refueling outage.
  • Fuel off-load is in progress.

Current Conditions:

  • A report is received that a fuel assembly being removed from the core was significantly damaged while lifting it from the core.
  • Large Bubbles were seen escaping from the damaged fuel assembly.
  • NO radiation alarms have been received.

Which ONE of the following describes the actions required by O-AP-22.OO, Fuel Handling Abnormal Conditions:

1) Closing 1-VS-MOD-i 03A and 1-VS-MOD-i 03C will secure
2) Is Containment Evacuation required?

A. 1) 1-VS-F-15, MCR Exhaust

2) Yes.

B. 1) 1-VS-AC-4, MCR Supply

2) No.

C. 1) 1-VS-AC-4, MCR Supply

2) Yes.

D. 1) 1-VS-F-15, MCR Exhaust

2) No.

Question: 67 Which ONE of the choices below completes the following statement?

The Federal Dose limit for Lens of the Eye is per year.

A. 15 Rem B. 1.5 Rem C. 5.0 Rem D. 50 Rem

Question: 68 Which of the following Critical Safety Function RED paths is the highest priority CSF that can be directly caused by procedurally directed operator action?

A. Subcriticality.

B. Core Cooling.

C. Heat Sink.

D. Containment.

Question: 69 The Station has just upgraded from an Alert to a Site Area Emergency.

Which ONE of the following actions is required for a Site Area Emergency in addition to those actions initiated for the Alert?

A. Off-Site monitoring Team Dispatched.

B. Emergency Response Personnel called in.

C. A Report of Radiological Conditions to the State is transmitted.

D. Accountability is performed.

Question: 70 Given the following:

  • 0800: A large break LOCA occurred.
  • 0810: A Site Area Emergency was declared.

In accordance with EPIP-2.01, when obtaining meteorological data from the MET panel:

1) The preferred source for wind speed, and wind direction is the Main Tower (1)
2) The required Notification completion time is recorded following roll call after reading Item (2)

A. 1)LowerLevel 2)11, Additional Information B. 1)LowerLevel 2)1, Emergency Classification C. 1)UpperLevel 2)11, Additional Information D. 1)UpperLevel 2)1, Emergency Classification

Question: 71 Initial Conditions:

  • Unit 2 operating at 100% power.
  • A LOCA has occurred in Unit 2 Safeguards.
  • Unit 2 is tripped and safety injection actuated.
  • 2-Sl-MOV-2890C, LHSI to Cold Legs, has been closed.
  • RCS Pressure is 1005 psig and rising.
  • The Team has transitioned to 2-E-1, Loss of Reactor or Secondary Coolant.

In accordance with 2-E-1, Loss of Reactor or Secondary Coolant, which ONE of the following identifies:

1) The status of the LHSI pumps.
2) The position of the LHSI Suction Valves from the RWST, 2-Sl-MOV-2862A and B.

A. 1) Secured in PTL.

2) Closed.

B. 1) Secured in AUTO.

2) Closed.

C. 1) Secured in PTL.

2) Open.

D 1) Secured in AUTO.

2) Open.

Question: 72 Given the following:

  • Unit 1 was operating at 100% when a large break LOCA occurred.
  • RCS pressure is 25 psig.
  • All ECCS equipment responded as designed.
  • The crew is performing step 4 of 1-E-1, Loss of Reactor or Secondary coolant.
  • The STA reports that red path for Integrity is satisfied and recommends FR-P.1.

Which of the following describes:

1) The actions the crew would take in response to the Integrity Red path.
2) The reason these actions are taken.

A. 1) Go to FR-P. 1, and after step 1 return to 1 -E-1.

2) Steam Generators are thermally disconnected from the RCS.

B. 1) Go to FR-P. 1, and after step 1 return to 1 -E-1.

2) Pressurized thermal shock is not a concern.

C. 1) Do not enter FR-P.1, continue in 1-E-1 until directed to transition.

2) Steam Generators are thermally disconnected from the RCS.

D 1) Do not enter FR-P.1, continue in 1-E-1 until directed to transition.

2) Pressurized thermal shock is not a concern.

Question: 74 Given the following:

  • A Large Break LOCA has occurred.
  • Crew is presently performing step 3 of ES-i .3
  • RWST level is at 14%.

Which of the following completes the following statements.

i) Auto Swapoverto RMT will occur when RWST level transmitters reach 13.5%.

2) In accordance with 1-ES-i .3, Transfer to Cold Leg Recirculation, step 5; IF RMT fails to automatically actuate the RO manually initiates RMT by depressing pushbuttons for each train.

A. i) 2of4

2) 2of2 B. 1) 3of4
2) 2of2 C. 1) 3of4
2) lof2 D. i) 2of4
2) 1 of2

Question: 75 Initial Conditions:

  • Both Units are operating at 100% power.

Current Conditions:

  • The STA reports that Containment Sump Level is 7.8 feet and rising.

Which ONE of the following identifies:

1) The Abnormal Procedure initiated by 1-E-0 Immediate Actions.
2) The PATH COLOR in effect on the Containment Status Tree.

A. 1) 0-AP-37.00, Seismic Event.

2) Red.

B. 1) 0-AP-37.00, Seismic Event.

2) Orange.

C. 1) 1-AP-10.07, Loss of Unit 1 Power.

2) Red.

D. 1) 1-AP-10.07, Loss of Unit 1 Power.

2) Orange.

RO EXAM LIST OF ATTACHMENTS Attachment # Attachment Description 1 Containment Ventilation 2 E-3 Table

2015 NRC ANSWER KEY Question # Answer Question Answer

RO 1 B 41 C 2 A 42 C 3 A 43 A 4 A 44 B 5 B 45 D 6 D 46 B 7 A 47 C 8 B 48 B 9 B 49 C 10 D 50 A 11 B 51 B 12 C 52 C 13 D 53 C 14 C 54 D 15 A 55 A 16 B 56 A 17 A 57 D 18 C 58 B 19 A 59 D 20 D 60 B 21 A 61 D 22 A 62 B 23 D 63 A 24 A 64 D 25 B 65 C 26 C 66 C 27 D 67 A 28 B 68 C 29 A 69 A 30 C 70 B 31 C 71 A 32 C 72 B 33 C 73 A 34 D 74 A 35 A 75 D 36 D 37 C 38 B 39 D 40 C NRC Validation Page 1

Question: 1 Initial Conditions:

  • Reactor at 50% and stable.
  • Tave at 558 °F, Tref at 558 °F.

Current Conditions:

  • Median Tave fails such that Tave is 4.0 °F lower than Tref.
  • Rod Control is placed in manual 30 seconds after the failure occurs.

Which ONE of the following states:

1) The direction of rod motion immediately before the rods were placed in manual.
2) The number of steps the control rods must be moved to restore the control rods to their previous rod height (prior to the Tave failure).

A. 1) Out.

2) 16.

B. 1) Out.

2) 20.

C. 1) In.

2) 16.

D. 1) In.

2) 20.

________

Question: 2 Initial plant conditions:

  • Unit 1 is at 100% power.
  • Currently performing a test of Reactor Trip breaker A per 1 -PT-8. 1, Rx. Protection Logic testing.
  • No operator actions have been taken.

REACTOR TRiP BKR RTA

[ REACTOR TRIP J EKR RTB CONTROL ROD SOUD STATE POWER SUPPLY ROD CONTROL RTSYPASS RTBYPASS SKR BYA BKR BYB Which ONE of the following correctly completes the following statements:

1) The Reactor trip and Bypass breakers correctly.
2) With respect to the breaker under test, the operator is required to A. 1) did not
2) initiate a manual reactor trip per 1-E-0, Reactor Trip or SI B. 1) did not
2) locally trip the breaker per 1-FR-S.1, Response to Nuclear Generation/ATWS C. 1) did
2) initiate a manual reactor trip per 1-E-0, Reactor Trip or SI D. 1) did
2) locally trip the breaker per 1-FR-Si, Response to Nuclear Generation/ATWS

Question: 3 Initial Conditions:

  • The Unit is in Cold Shutdown with the Team preparing to start the first RCP in accordance with 1 -OP-RC-001, Starting and Running Any Reactor Coolant Pump.
  • Vacuum assist was unavailable during RCS Loop fill.

The following sequence of events occur:

  • 0900, C RCP started for RCS Vent.
  • 0902, C RCP secured due to low seal Differential Pressure.
  • 0933, C RCP started for RCS Vent.
  • 0938, C RCP secured due to low seal Differential Pressure.
  • 1012, C RCP started for RCS Vent.
  • 1027, C RCP secured due to the loss of both seal injection and thermal barrier flow.

Which ONE of the following states:

1) What is the earliest time the fourth start of the C RCP may be attempted, in accordance with 1-OP-RC-001?
2) When restoring seal injection and thermal barrier cooling to an RCP seal, which is restored first?

A. 1) 1128.

2) Thermal Barrier.

B. 1) 1128.

2) Seal Injection.

C. 1) 1058.

2) Thermal Barrier.

D. 1) 1058.

2) Seal Injection.

Question: 4 Unit I was operating at 100% operation when a failure occurred causing Letdow temper n ature to rise.

Which of the following describes:

1) At what temperature will the Letdown divert valve, 1-CH-TCV-1 143 divert to the VCT?
2) What is the reason for this action?

A. 1) 145°F.

2) Protect Ion Exchanger resin from damage due to high Letdown line temp.

B. 1) 145°F.

2) Mitigate negative reactivity caused by boron release from Demins.

C. 1) 130°F.

2) Protect Ion Exchanger resin from damage due to high Letdown line temp.

D. 1) 130°F.

2) Mitigate negative reactivity caused by boron release from Demins.

Question: 5 Initial Conditions:

  • Unit 1 is being cooled down to Cold Shutdown, with RHR in service.

Which ONE of the following states:

1) The power supply to 1-RH-MOV-1 700, RHR Inlet MOV.
2) The pressure transmitter that supplies the signal for the open (maximum pressure) interlock for 1-RH-MO V-i 700.

A. 1) iHi-2S-8C.

2) i-RC-PT-i402-1, RCS Pressure Wide Range.

B. 1) iHl-2S-SC.

2) i-RC-PT-i403, RCS Pressure Narrow Range.

C. 1) 1A1-1E-4B.

2) i-RC-PT-1402-i, RCS Pressure Wide Range.

D. 1) iAi-1E-4B.

2) i-RC-PT-i403, RCS Pressure Narrow Range.

Question: 6 Given the following conditions:

  • RCS temperature is 175°F.
  • RCS pressure is 305 psig.
  • The PRZR is solid.
  • Charging flow control is in manual.
  • RHR is in service, with the A RHR heat exchanger and 1-RH-P-lA in service.
  • 1-RH-FCV-1 605, RHR H/X bypass, is in AUTO.

The A RHR heat exchanger suddenly develops a 150 gpm tube leak.

With NO Operator actions, which ONE of the following identifies the effect of this malfunction on:

1) Flow through the RHR pump.
2) RCS pressure.

A. 1) Flow remains the same.

2) Pressure lowers.

B. 1) Flow remains the same.

2) Pressure rises.

C. 1) Flow rises.

2) Pressure rises.

D. 1)Flowrises.

2) Pressure lowers.

_________

Question: 7 Initial Conditions:

  • A Large Break LOCA is in progress.
  • The Team is performing 1-E-0, Loss of Reactor or Secondary Coolant.
  • The BOP operator is performing 1-E-0, Attachment 1, System Alignment Verification and is on Step 12 CHECK SI FLOW.

Current Conditions:

  • RCS pressure is 30 psig.
  • HHSI and LHSI pump amps are listed below:

PUMP AMPS 1-CH-P-1A 70 1-.CH-P-1B 69 1-CH-P-1C 30 1-SI-P-lA 265 1-SI-P-lB 275 Which ONE of the following describes the status of the HHSI and LHSI pumps upon compl etion of , step 12.

1) The HHSI pump that will be secured is
2) The number of LHSI pumps that will be running is A. 1) l-CH-P-1C
2) two B. 1) 1-CH-P-1A
2) two C. 1) 1-CH-P-1C
2) one D. 1) 1-CH-P-1A
2) one

Question: 8 Given the following:

  • Unit 1 operating at 100%.
  • The crew experienced a spurious SI signal.
  • Following the SI the Charging pump suction valves have the following positions:

o 1 -CH-MOV-1 11 5B, CHG pump suction from RWST; CLOSED.

o 1.-CH-MOV-1115C, CHG pump suction from VCT; OPEN.

o 1 -CH-MOV-1 11 5D, CHG pump suction from RWST; OPEN.

o 1-CH-MOV-1115E, CHG pump suction from VCT; CLOSED.

  • All other auto SI actions occur as designed.

In the given alignment, the VCT _(1) a source of HHSI flow, and the RWST _(2) a source of HHSI flow.

A. 1)is 2)isnot B. 1)isnot 2)is C. 1)is 2)is D. 1) is not 2) is not

Question: 9 Initial Conditions:

  • 1-RC-PT-1445, PRZR PRESS CNTRL, failed high.
  • The Team has completed the Immediate Actions of 1-AP-31 .00, Increasing or Decrea sing RCS Pressure.

Current Conditions: (2 minutes later):

  • PRT Pressure is 12 psig and stable.

Which ONE of the following identifies:

1) The PRZR PORV that was closed is_____
2) The procedure that will direct returning the PRT to normal pressure is________

A. 1) 1-RC-PCV-1455C

2) 1-AP-31.00, Increasing or Decreasing RCS Pressure B. 1) 1-RC-PCV-1456
2) ARP 1C-F7, PRZR RELIEF TK HI PRESS C. 1) 1-RC-PCV-1455C
2) ARP 1C-F7, PRZR RELIEF TK HI PRESS D. 1) 1-RC-PCV-1456
2) 1 -AP-31 .00, Increasing or Decreasing RCS Pressure

_____

__

Question: 10 Initial Conditions:

  • Unit 1 is at 100%.
  • Tave is at 573 °F.
  • Pressurizer Safety Valve 1-RC-SV-1551A inadvertently fails partially open.
  • S/G B NR level channel 1, 1-FW-Ll-1484, fails high immediately following the Reactor trip.
  • 30 seconds later SI automatically actuates.

Current Conditions (10 minutes later)

  • Plant is stabilized with Tave at 552 °F and RCS pressure at 1910 psig.
  • Pressurizer vapor space temperature is steady at 630 °F.
  • Main Feedwater pumps have tripped, all Feed Reg valves are closed, and all Feed Reg Bypass valves are closed.

Which of the following describes:

1) The Main Feed pumps trip after the_______
2) The Feed Regulating Bypass valves initially closed due to the A. 1) reactor trip, but before the safety injection
2) reactor trip coincident with low Tave B. 1) reactor trip, but before the safety injection
2) safety injection C. 1) safety injection
2) reactor trip coincident with low Tave D. 1) safety injection
2) safety injection

Question: 11 Initial Conditions:

  • Unit 1 reactor operating at 100% power.
  • A tube leak develops in 1-CC-E-1A, A CCHX.

Which ONE of the following states:

1) The effect on CC Surge Tank level.
2) The CW lines that supply SW to the CCHXs.

A. 1) Rise.

2) lA/C.

B. 1) Lower.

2) IBID.

C. 1) Rise.

2) iB/D.

D. 1) Lower.

2) lA/C.

_____

Question: 12 Initial Conditions:

  • Unit 1 and Unit 2 operating at 100%.
  • Charging pump, 1-CH-P-1B started then tripped on lockout, 1-CH-P-IA and C are running.
  • Containment pressure is 16.2 psia and slowly rising.

Current conditions:

  • RO reports loss of 1 H 4160 V bus. EDG 1 did not start.
  • RCS pressure is 1082 psig and slowly lowering.
  • CETC is 528 °F and stable.

Which of the following states:

1) RCP Trip criteria is
2) In accordance with 1-E-1 Basis; the reason RCP5 are tripped is to A. 1) Met
2) Prevent excessive depletion of RCS inventory B. 1) Not met
2) Minimize heat input C. 1) Not met
2) Prevent excessive depletion of RCS inventory D. 1) Met
2) Minimize heat input

___

Question: 13 A ground has developed on DC Panel 1-2, causing 1-.RC-SOy-biB-I and 1-RC-SOV-1 O1B-2, PRZR Vent Valves, to fail open.

Which ONE of the following states:

1) The Master Pressure controller output will
2) The PRZR Vent Valves discharge to the A. 1) rise
2) Primary Vent Pot B. 1) rise
2) Reactor Cavity C. 1) lower
2) Primary Vent Pot D. 1) lower
2) Reactor Cavity

Question: 14 Initial conditions:

  • Unit 1 is at 100% power.
  • The breaker for 1 -SI-MOV-1 885C, LHSI Pump A Recirc Valve, was found open, and could not be reclosed.
  • A Large Break LOCA occurs.

Current conditions:

  • The RWST level is 12.5%.
  • The Team is currently at 1-ES-i .3, Transfer to Cold Leg Recirculation; step 5, Align SI System for Recirc.

Which ONE of the following identifies:

1) Which LHSI pump(s) will automatically align to the RMT mode?
2) Per ES-i .3 CAP, after step 5, the operator will monitor for oscillating LHSI pump amps and flow to check for A. 1) Both LHSI pumps.
2) RWST <3%

B. 1) ONLY the B LHSI pump.

2) sump blockage C. 1) Both LHSI pumps.
2) sump blockage D. i) ONLY the B LHSI pump.
2) RWST <3%

Question: 15 A loss of off-site power has resulted in the trip of both Units.

Which ONE of the following identifies the Pressurizer heaters energized on Unit 1?

A. None.

B. E Group.

C. E and A Groups.

D. A Group.

Question: 16 Given the following:

  • Unit 1 is at 100%.
  • Power Range N-41 fails HIGH.
  • 0-AP-53.00, Loss of Vital Instrumentation/Controls, immediate actions completed.
  • Crew is presently performing 1-AP-4.00, Nuclear Instrumentation Malfunction, Attach ment ito place the failed Power range channel in trip.

Which one of the choices below completes the following statements?

1) In accordance with 1-AP-4.00, Attachment 1; OP L\T channel 1 have to be placed in trip.
2) OP z\T provides protection against A. 1) will
2) DNB B. 1) will
2) high power density C. 1) will not
2) DNB D. 1) will not
2) high power density

Question: 17 Initial Conditions:

  • Unit 1 is heating up per 1-GOP-i .3, RCS Heatup from 345 °F to HSD following a mid-cy cle outage.
  • 40,000 gallons were transferred to the RWST from the blender.
  • RWST Refrigeration Unit 1A is tagged out for compressor breaker replacement.
  • RWST Refrigeration Unit 1 B is in operation.
  • RWST temperature is 42°F on channel 1 and channel 2; (1-CS-TI-i OOA and bOB).

Current Conditions (5 mm. later)

  • Operator reports RWST Refrigeration Unit 1 B has a low oil pressure trip and he is unable to reset. Operator requests maintenance support.
  • Unit 1 RWST parameters are as follows:

Temp. Boron 44°F 2275 ppm In accordance with Tech Specs 3.3.A. 1, RWST; which of the following completes the statem ent.

With the current conditions the RWST LCO temperature limit is _(1), and the RWST Boron LCO limit is _(2)....

A. 1) met

2) not met B. 1) not met
2) met C. 1) not met
2) not met D. 1) met
2) met

_____

Question: 18 Initial Conditions:

  • Unit 1 is at 100% power when a large break LOCA occurs.
  • Containment pressure peaks at 45 psia.

Current Conditions:

  • The crew is at 1-El, Loss of Reactor or Secondary Coolant, step 17 and is attempting to open 1-lA-TV-i 00.
  • The RO reports that Containment pressure is slowly lowering and is as follow s:

o 1-LM-Pl-100A 15 psia.

o 1-LM-Pl-100B 15 psia.

o 1-LM-Pl-100C 14 psia.

o 1-LM-Pl-100D 15 psia.

  • 1-Pl-IA-101, CTMT INST AIR, indicates 25 psig.
  • The operator has depressed both CLS Train A (B) RESET buttons.
  • SI has been reset.

Which one of the following correctly completes the statements below:

1) After depressing both CLS RESET buttons, CLS reset.
2) When the operator attempts to open 1-IA-TV-i 00, the valve will A. 1) is 2) remain closed B. 1) is not 2) open C. I) is not 2) remain closed D. 1) is 2) open

Question: 19 The reactor is operating at 100% power when the following sequence of events occur:

  • Initial D Bank rod height 225 Steps.
  • The RO is performing 1-OPT-RX-005, Control Rod Assembly partial Movem ent, for D Control Bank.
  • Annunciator G-A6, Rod Cont Sys Urgent Failure is received when Contro Bank l D begins to move inward.
  • Rod Control In-Hold-Out switch placed in Hold.

The following indications are noted by the RO:

  • Control Bank D, Group 1 Step counter indicates 224 Steps.
  • Control Bank D, Group 2 Step counter indicates 222 Steps.
  • Control Bank D, CERPI Group 1 indicates 224 Steps.
  • Control Bank D, CERPI Group 2 indicates 222 Steps.

Which ONE of the following identifies the:

1) Power Cabinet affected by the Urgent Failure.
2) The procedure that would need to be entered to mitigate the malfunction.

A. 1) Power Cabinet 1BD.

2) 0-AP-1 .00, Rod Control System malfunction.

B. 1) Power Cabinet 1BD.

2) 0-AP-1 .02, Individual Rod Position Indicators.

C. 1) Power Cabinet 2BD.

2) 0-AP-1.00, Rod Control System malfunction.

D. 1) PowerCabinet2BD.

2) 0-AP-1.02, Individual Rod Position Indicators.

Question: 20 With Unit 1 at 100% power, an inadvertent phase Ill containment isolation occurs. Approximately 15 minutes later, the following RCP temperatures exist:

A RCP

  • Upper Motor radial bearing 185°F
  • RCP lower bearing Seal Water Temp 215°F
  • Upper Motor radial bearing 180°F
  • RCP lower bearing Seal Water Temp 210°F
  • Stator winding 305° F In order to mitigate these plant conditions, the crew will monitor RCP temper atures using (1) ,then initiate 1-E-0, Reactor Trip or Safety Injection, trip the reactor, and stop (2)

A. 1) 1-AP-15.00, Loss of Component Cooling

2) C RCP B. 1) 1-AP-15.00, Loss of Component Cooling
2) A RCP C. 1) 1-AP-9.00, RCP Abnormal Conditions
2) A RCP D. 1) 1-AP-9.00, RCP Abnormal Conditions
2) C RCP

Question: 21 Unit 2 initially operating at 100% power, when the following occurs:

  • The Reactor is tripped and Safety Injection actuated.
  • The RCPs have been tripped due to low RCS subcooling.
  • RVLIS Full Range Indicates 42% and stable.
  • RCS THOT indicates 650 °F and stable.
  • CETCs indicate 660 °F and rising.

Which ONE of the following describes:

1) The temperature indication used on the Core Cooling Status tree.
2) The status of the Core Cooling Status Tree.

A. 1) CETC temperature.

2) Orange.

B. 1) CETC temperature.

2) Red.

C. 1)THOT.

2) Orange.

D. 1) THOT.

2) Red.

Question: 22 Unit 2 is performing a Reactor Startup following a forced outage. Shutdo wn banks are fully withdrawn.

During the outage, a substantial amount of work had been performed in the Pressurizer Cubicle in Containment.

Given the following data:

Initial Condition Parameter Condition 1 Day later PRT Level 78% 78%

PRT Pressure 6 psig 6 psig PRT Temperature 82°F 84°F Weighted AVG CTMT Temperature 972°F 101 5°F A PRZR SV Temperature 129°F 152°F B PRZR SV Temperature 140°F 160°F C PRZR SV Temperature 121°F 149°F PRZR PORV Temperature 121°F 148°F Shutdown bank CERPI Indication No change in CERPI Which ONE of the following states the cause for the changes noted betwee n the Initial Conditions and the Conditions found 1 Day later?

A. Cubicle Ventilation Damper position change.

B. CRDM Fan Trips.

C. B PRZR SV Leaking.

D. PRZR PORV leaking.

Question: 23 Initial Conditions:

  • Unit 1 at 50% power and ramping up to 100% in accordance with GOP-i .5, Unit Startup, 2% to Max Allowable Power.
  • Rod Control in manual due to hunting in automatic.

Current Conditions:

  • Median Tave fails to a stable indication of 550 °F.
  • No Operator Actions have been taken.

Which ONE of the following states:

1) The Pressurizer level control setpoint is
2) The automatic charging low flow limit is A. 1) 24.8%
2) 30 gpm B. 1) 25.8%
2) 30 gpm C. 1) 24.8%
2) 25gpm D. 1) 25.8%
2) 25 gpm

Question: 24 Unit 2 is operating at 100% power with Chilled CC in service to containment.

  • An operator is verifying the Plant Computer System displays and indications are functioning properly using the laptop computer at the Auxiliary Shutdown Panel.
  • 2-CD-REF-i, Unit 2 Turbine Building Chiller trips.

Which ONE of the following states:

1) Containment partial pressure will
2) Containment saturation temperature is sensed at the_______

A. 1) lower

2) Containment air recirculation fan discharge B. 1) rise
2) Containment air recirculation fan discharge C. 1) rise
2) Containment dome D. 1) lower
2) Containment dome

_____

__

Question: 25 Initial Conditions:

  • Unit 1 is in Cold Shutdown, at 190 °F, on RHR, preparing to take the pressu rizer solid.
  • A RHR pump is running with the A RHR HX in service.
  • A CC pump running on Unit 1; D CC pump running on Unit 2. CC is cross-t ied.

Current Conditions:

  • C RSST trips and locks out.

Which ONE of the following states:

1) The status ofA RHR pump.
2) The CC pump is running on Unit 1, and the CC pump is running on Unit 2.

A. 1) Running.

2) A; D B. 1) Tripped.

L;

2) C C. 1) Running.
2) B; C D. 1) Tripped.
2)  ?;

Question: 26 Given the following:

  • A Large Break LOCA has occurred on unit 1.
  • An operator has been assigned to perform 1-E-O, Reactor Trip or SI; Attachment 4, CLS Component verification.
  • When checking the valve lineup the operator notices that the red and green light bulbs for 1-SW-MOV-104A, RSHX A SW INLET are NOT lit.

Which one of the following indications does 1 -E-O, Attachment 4 direct the operator use to verify that there is adequate flow through the heat exchanger?

A. 1-SW-MOV-103A, RS HX A&D SW SUPPLY; and 1-SW-MOV-105A, RSHX A SW OUTLET red lights LIT.

B. Annunciator 1A-D6, RS HX 1A RAD MON PP NO FLOW is NOT LIT.

C. Flow indication on 1-SW-Fl-i 06A, RS HX A SW Outlet Flow.

D. 1-SW-P-5A, RS SW Radiation Monitor Sample pump red light is LIT.

_____

_____

__ _

Question: 27 Unit 1 is operating at 100% with the following conditions:

  • 1-OPT-RC-10. 0, Computer leak Rate Program has trended a rise in Uniden tified leakage of 0.1 gpm.
  • A Containment entry has been performed and the leak has been identified on the A SG Primary manway.
  • HP has requested the Unit 1 Iodine filter fans, 1-VS-F-3A and 3B, be placed in service.

Which ONE of the following identifies:

1) The operator will place the control switch for the Iodine Filter Fans to to start the fans.
2) The Unit 1 Iodine Filter Fans are operated at the Ui Main Control Room panel.

A. 1) Auto

2) Ventilation B. 1) Auto
2) Post Accident Monitoring C.1)On
2) Post Accident Monitoring D. 1) On
2) Ventilation

___

_____

Question: 28 Initial Conditions:

  • Unit 1 is at HSD with all RCPs running.
  • Preparations for Unit startup are in progress per 1-GOP-1.4, Unit Startup.
  • The Master Pressure Controller (MPC) and spray valve controllers are all in auto and set to maintain 2235 psig.
  • Pressurizer pressure indicates 2250 psig on 1-RC-Pl-1444, and 1-RC-Pl-144 5.

Current Conditions (60 sec):

  • Pressurizer pressure is 2130 psig.
  • 1-RC-PC-1444G, PRZR Spray from Loop A, 1-RC-PCV-1455A indicates 100%.
  • 1-RC-PC-1444H, PRZR Spray from Loop C, 1-RC.-PCV-1455B indicates 0%.
  • 1-RC-PC-1444J, PRZR PRESS Master CNTRL, indicates 0%.

Which ONE of the following identifies:

1) The POT setting of the Master Pressure Controller for 2235 psig is
2) The expected operator action associated with the failure in accordance with 0-AP-53.00, Loss of Vital Instrumentation/Cont is to place in manual and close the spray valve.

A. 1) 7.45

2) 1-RC-PC-1444G, PRZR Spray from Loop A, 1-RC-PCV-1455A B. 1)6.68
2) 1-RC-PC-1444G, PRZR Spray from Loop A, 1-RC-PCV-1455A C. 1)7.45
2) 1-RC-PC-1444H, PRZR Spray from Loop C, 1-RC-PCV-1455 D. 1)6.68
2) 1-RC-PC-1444H, PRZR Spray from Loop C, 1-RC-PCV-1455

____

Proposed Question: 29 Given the following:

  • Pressurizer level channel transmitter 1-RC-LT-459, Pressurizer Level Protec tion Channel I, is the upper channel.
  • The reference leg of 1-RC-LT-459 develops a slow leak.

Which ONE of the following describes:

1) As a result of the reference leg leak, the level indication on 1 -RC-LI-1459 will
2) In accordance with D-AP-53.DO, Loss of Vital Instrumentation/Controls, the operator required to isolate letdown for this failure.

A. 1) rise

2) is not B. 1) rise
2) is C. 1) lower
2) is not D. 1) lower
2) is

____

Question: 30 Initial Conditions:

  • Unit 1 operating at 100% power.
  • Crew is performing 1-E-0, Reactor Trip or Safety Injection, immediate actions.
  • Both reactor trip breakers remain closed after E-0 step 1 performed.

Current Conditions:

  • An operator has just been dispatched to open reactor trip breakers per 1-FR-S.1, step 8.
  • Gamma-Metrics is reading 20%.
  • Power Range NI channels are all reading 15%.
  • Containment pressure is 22 psia and rising.

Which of the following completes the statements:

1) In accordance with 1-E-0, Reactor Trip or SI, Background; if any reactor trip breaker and associated bypass breaker is open, and neutron flux has decreased to less than 5

%, the reactor considered tripped.

2) In accordance with 1-FR-Si, Response to Nuclear Generation/ATWS; the instrumentation the crew should be using to monitor neutron flux is A. 1) is
2) Power Range NI channels B. 1) is not
2) Gamma-Metrics C. 1) is
2) Gamma-Metrics D. 1) is not
2) Power Range NI channels

_

Question: 31 Initial Condition:

  • Unit 2 Containment pressure has just reached atmospheric.
  • The Team is preparing to place Unit 2 Containment on purge using 1-VS-F

-58A, in accordance with 2-OP-VS-OO1, Containment Ventilation.

  • The Personnel and Equipment Hatches are closed.

Which ONE of the following completes the following statement?

1) An allowable configuration would consist of
2) The filter is used in the flowpath.

(REFERENCE PROVIDED)

A. 1) Containment Purge and Fuel Building Exhaust

2) CAT II B. 1) Containment Purge Only
2) CATI C. 1) Containment Purge and Fuel Building Exhaust
2) CATI D. 1) Containment Purge Only
2) CATII

Question: 32 Given the following:

  • Unit 2 is currently stable at 75% power.
  • The B Feed Reg Valve demand begins to slowly lower due to an instrument failure.

Which ONE of the following identifies:

1) The effect this will have on the indicated power by Instantaneous Calorimetric.
2) The procedure used to respond to this event.

A. 1) Lowers.

2) 2-AP-21 .00, Loss of Main Feedwater Flow.

B. 1) Rises.

2) 2-AP-21 .00, Loss of Main Feedwater Flow.

C. 1) Lowers.

2) 0-AP-53.00, Loss of Vital Instrumentation/Controls.

D. 1) Rises.

2) 0-AP-53.00, Loss of Vital Instrumentation/Controls.

Question: 33 The Operating Team is in E-3, Steam Generator Tube Rupture and has compl eted RCS cooldown and depressurization. CHG pump suction has been aligned to the VCT.

The following Unit conditions exist:

  • PRZR level is 35% and slowly rising.
  • S/G levels are as follows:

o A S/G is 68% and lowering.

o B S/G is 33% and rising.

o C S/G is 32% and rising.

  • RCS pressure is 985 psig.
  • S/G pressures are as follow:

o A S/G is 1000 psig and lowering.

o B S/G is 670 psig and rising.

o C S/G is 650 psig and rising.

Which ONE of the following is the MINIMUM actions required to be taken by the Operating Team in accordance with step 36 of E-3?

(REFERENCE PROVIDED)

A. Depressurize RCS and raise CHG flow.

B. Lower CHG flow and depressurize the RCS.

C. Turn on PRZR heaters.

D. Raise CHG flow.

Question: 34 Given the following:

  • Unit 1 is at 100 % power.
  • A complete separation of the Main steamline piping upstream of the MSR Steam Supply to the A & C MSRs (30 pipe) occurs.

Which ONE of the following describes the effect this will have on the...

1) Main Feed pumps.
2) Main Steam Trip valves.

A. 1) Remain running.

2) Remain open.

B. 1)Trip.

2) Remain open.

C. 1) Remain running.

2) Close.

D. 1)Trip.

2) Close.

Question: 35 Initial Conditions:

Unit 1 operating at 100% power.

  • A Steam line in Unit 1 alleyway ruptures.
  • Station Service buses are lost on swap-over to Reserve Station Service Transf ormers following a manual reactor trip.
  • Individual MSTV close switches on Benchboard fail to operate.
  • MSTV Emergency close switch on Vertical Board fails to close the MSTV s.

Which one of the following states:

1) The redundant MSTV Emergency Close Switch, is located on the Appen dix R panel in
2) Operation of this switch the MSTV close SOVs.

A. 1) Unit 1 ESGR

2) Energizes B. 1) Unit 1 ESGR
2) Deenergizes C. 1) Unit 2 ESGR
2) Energizes D. 1) Unit 2 ESGR
2) Deenergizes

Question: 36 Unit 1 is placing the Unit on-line in accordance with 1-OP-TM-001, Turbine - Generator Startup to 20%

- 25% Turbine Power.

  • Steam Dumps are in Auto in steam pressure mode.
  • Reactor Power has been raised to 8%.
  • P-7 NIS POWER RANGE AND TURBINE POWER < 10% is LIT.
  • When the second Generator output breaker, OCB-G1T240 is closed, Annun ciator iF-El, GEN BACKUP LOCKOUT REL TRIP, comes in due to a fault.

Which one of the following correctly describes the effect this will have on:

1) The reactor.
2) Main Generator output breakers.

Reactor Main Gen output breakers A. trip trip open after 30 seconds B. not trip trip open after 30 seconds C. trip trip open immediately D. not trip trip open immediately

____

Proposed Question: 37 Initial Conditions:

  • The team was performing 1-E-0 in response to a faulted steam generator outside containment.
  • Upon transition from 1-E-0, the STA reported a red path on HEAT SINK.
  • The team has entered 1-FR-Hi, Loss of Secondary Heat Sink.

Current Conditions

  • SG levels are A- 0% WR, B- 13% WR, C- 14% WR (all lowering).
  • RCS Thot 640°F and rising.
  • Pressurizer level 80% and rising
  • Pressurizer pressure 2345 psig and rising.
  • 1-RC-PCV-1455C was cycling open/close and is now open.

Which ONE of the following states:

1) In accordance with 1 -FR-H. 1, Continuous Actions Page, RCS Bleed and Feed required.
2) What is the reason for the Pressurizer PORV remaining open?

A. 1)is not

2) RCS expansion due to Loss of Heat sink.

B. i)is

2) Pressurizer fill due to safety injection.

C. i)is

2) RCS expansion due to Loss of Heat sink.

D. i)isnot

2) Pressurizer fill due to safety injection.

_____ _____

_________

Question: 38 Initial Conditions:

  • Unit 1 operating at 100% power.
  • A SGTR occurs on the A SG, the reactor is tripped and safety injection actuated.
  • The Team has completed the Rapid Cooldown of I -E-3, Steam Generator Tube Rupture.
  • The Air Ejector discharge has been re-aligned to Containment.

Current Conditions:

  • The A SG faults inside of Containment.
  • Hi and Hi-Hi CLS have actuated.

Which ONE of the following states:

1) The position of 1-SV-TV-102A, AE DISCH TO CTMT SFGD TV, is
2) The position of 1-SV-TV-102, AE DISCH TO CTMTTB TV, is A. 1) open
2) open B. 1) closed
2) closed C. 1) closed
2) open D. 1) open
2) closed

Question: 39 ECA-O.O, Loss of all AC Power, Step 24, directs the operator to:

Depress urize all Intact SGs to 300 psig Which ONE of the following describes the reason for stopping the pressure reduction at 300 psig?

A. Prevent losing pressurizer level.

B. Minimize inventory loss out of RCP seals.

C. Prevent voiding in the Reactor Vessel upper head.

D. Prevent SI Accumulator Nitrogen into the RCS.

_____

Question: 40 Initial Conditions:

  • Unit 1 at 100%

o 1 K-B8, UPS SYSTEM 1 B TROUBLE.

o 1C-Bi, RCP lB CC RETURN LO FLOW.

o 1 E-G4, RX TRIP CH-2 PRZR LO PRESS.

Current Conditions:

  • The non-licensed operator dispatched reports the red INVERTER SUPPLYING LOAD light is NOT lit for UPS lB-i.
  • Indication on 1-FW-FCV-1488 (B FRV Controller) is:

o Auto Light NOT LIT.

o Manual Light NOT LIT.

  • The control room team is currently performing actions per 1 K-B8, UPS System 1 B Trouble.

Which one of the following describes:

1) B S/G feed flow be controlled by using the pushbuttons on the FRV controller.
2) The Abnormal Procedure that should be utilized is A. 1) can not
2) 1-AP-1 0.04, Loss of Vital Bus IV B. 1)can
2) 1-AP-i 0.02, Loss of Vital Bus II C. 1)cannot
2) 1-AP-10.02, Loss of Vital Bus II D. 1)can
2) 1-AP-1 0.04, Loss of Vital Bus IV

Question: 41 Which ONE of the following breakers, if open, will cause a Vital Bus UPS Static Switch to shift to the alternate source?

A. Battery Charger AC Input.

B. Battery Charger DC Output.

C. Inverter DC Input.

D. Battery Bus DC Input.

Question: 42 Unit 1 is currently at 60% power and is performing a startup.

1-FW-P-1B, B Main Feed Pump, is running.

Shortly after starting 1-FW-P-1A, A Main Feed Pump, the operator observes the Main Feed Pump tripping.

Which ONE of the following conditions could have caused 1-FW-P-1A, A Main Feed Pump trip?

to A. Feed pump Lube oil pressure at 8 psig.

B. C Station Service Bus voltage at 68%.

C. Feed flow < 3000 gpm and Recirc valve, 1 -FW-FCV-i 50A not fully open.

D. Feed pump Suction pressure at 430 psig.

Question: 43 Given the following:

Power from the associated rack in the relay room, to the A FRV controller, 1-FW-FCV-1478 is lost.

With the conditions stated, which of the following answers the questions listed below:

1) What is the effect on the output of the controller?
2) Can this controller be controlled from the Main Control Room?

A. 1) Shift to manual and output will remain the same as prior to loss of power.

2) Yes.

B. 1) The output of the controller will raise to 100% demand.

2) Yes.

B. 1) The output of the controller will raise to 100% demand.

2) No.

D. 1) Shift to manual and output will remain the same as prior to loss of power.

2) No.

Question: 44 Given the following:

  • An accidental gaseous radwaste release has occurred in the Waste Gas Decay Tank Room.
  • A Site Area Emergency has been declared due to dose at the site boundary of 200 mRem/hr.
  • Radiation protection has determined that radiation dose level in the room is 1,000 mRem/hr.

A Surry Power Station worker assigned to enter the room has a current year-to-date TEDE of 700 mRem.

The MAXIMUM total time the worker is allowed RCA access, to perform the work, with NO extensions is hour(s)?

A. 0.50 B. 1.00 C. 1.85 D. 2.30

Question: 45 The team is performing 1-E-0, Reactor Trip or Safety Injection, with plant conditions as follows:

  • Containment pressure is 27 psia and rising slowly.
  • A SIG parameters o Pressure- 650 psig and lowering slowly.

o Level- 57% WR and lowering slowly.

  • B SIG parameters o Pressure 120 psig and lowering rapidly.

o Level- 15% WR and lowering rapidly.

  • C SIC parameters o Pressure 630 psig and lowering slowly.

o Level- 56% WR and lowering slowly.

  • Pressurizer level 0%.
  • Pressurizer pressure 1200 psig and lowering.
  • RCS Tave- 512 °F and lowering at a rate of 120 °FIhr.

Which ONE of the following states the minimum required AFW flow to the S/Cs in accord ance with E-0, Reactor Trip or Safety Injection, Attachment 8?

A. A SIG- 100 gpm; B S/G- 100 gpm; C S/G-100 gpm.

B. A S/G- 175 gpm; B SIC- 0 gpm; C S/G- 175 gpm.

C. A S/G- 60 gpm; B SIG- 60 gpm; C SIG- 60 gpm.

D. A S/G- 225 gpm; B S/C- 0 gpm; C SIG- 225 gpm.

Question: 46 In accordance with 1-AP-21.01, Response to AFW Check Valve Backleakage, which ONE of the following identifies:

1) The temperature on an AFW pump casing where the pump is considered vapor bound.
2) Which of the AFW pumps is aligned and cooled FIRST if all AEW pumps are found to be vapor bound?

A. 1) 200°F.

2) Motor Driven.

B. 1) 200°F.

2) Turbine Driven.

C. 1) 165°F.

2) Motor Driven.

D. 1) 165°F.

2) Turbine Driven.

Question: 47 Initial Conditions:

Unit 1 A DC Bus is lost due to a fault, causing a reactor trip.

Current Conditions: (11 minutes following the reactor trip)

A Large Break LOCA occurs on Unit 1.

The Team decides to locally start 1-CS-P-lA, A CS Pump.

Which ONE of the following identifies:

1) The red breaker position indicating light be used by the control room team to identify that 1-CS-P-lA has been successfully started.
2) 1-CS-P-lA breaker, 1-EP-BKR-14H5, have overcurrent trip protection.

A. 1) can

2) does not B. 1) can
2) does C. 1) cannot
2) does D. 1) cannot
2) does not

_____

_ _____

__

Question: 48 Initial Conditions:

  • Unit 1 is operating at 100%.
  • 1-SW-P-i CA, CHG PUMP SW PUMP, is running in HAND, 1-SW-P-lOB, CHG PUMP SW PUMP is in Auto.
  • 1-CH-P-1C, CHARGING PUMP is running.

Current Conditions:

  • Reactor Operator reports the following:

o 1-SW-P-bA has tripped, and i-SW-P-lOB remains in standby.

o Highest reading Charging pump bearing temperature is 179°F and rising.

Which ONE of the following describes:

1) The Reactor Operator can monitor Charging pump SW flow on the
2) 0-AP-1 2.00, Service Water Abnormal, states that the affected Charging pump should be secured once bearing temperature exceeds a minimum of A. 1) Vertical board 2)195°F B. 1) PCS 2)185°F C. 1)PCS 2)195°F D. 1) Vertical board 2)185°F

__________

Question: 49 Given the following conditions:

  • Unit 1 tripped from 100% power due to loss of on-site and off-site power.
  • The team is performing 1-ECA-0.0, Loss of all AC Power.
  • The AAC EDG has not been loaded on an emergency bus.

Which ONE of the following identifies:

1) The power source for Unit 1 Annunciator System is
2) The Black Battery supplies the A. 1) A Station Battery
2) Seal Oil Backup Pump B. 1) B Station Battery
2) Emergency Oil Pump C. 1) A Station Battery
2) Emergency Oil Pump D. 1) B Station Battery
2) Seal Oil Backup Pump

Question: 50 Which one of the following supplies the DC control power to #1 EDG output breaker, 1 -EP-BKR-1 5H3?

A. A DC bus.

B. B DC bus.

C. Black battery DC bus.

D. #1 EDG DC system.

Question: 51

  • O-VSP-C8, Fire Detected, has alarmed with Unit 1 ESGR indicated on the fire display panel.
  • The BOP has dispatched an operator to investigate Unit 1 ESGR for a fire.

Which ONE of the following identifies:

1) The maximum time limit for the operator to report fire status.
2) The reason for this time limit in accordance with O-VSP-C8.

A. 1) 5 minutes.

2) Ensure adequate time for EAL classification and transmission, if required.

B. 1) 5 minutes.

2) Prompt response is necessary to prevent significant damage.

C. 1) 3 minutes.

2) Ensure adequate time for EAL classification and transmission, if required.

D. 1) 3 minutes.

2) Prompt response is necessary to prevent significant damage.

________

____

Question: 52 Initial Conditions

  • Both units at 100% power.
  • The Control Room is evacuated due to a Limiting Main Control Room Fire.
  • All actions per 0-FCA-001, Limiting MCR Fire were taken prior to evacuation.

Current Conditions (20 minutes later)

  • Operator dispatched to perform 0-FCA-1 1.0, Remote Monitoring.
  • Operator reports that Unit 1, Neutron flux indicators are reading as shown below:

Operator reports the following additional NEUT FLUX NEUT FLUX 1-NM-NFI-190A2 nformation: 1-1iMMFI-190B2 10 CO

  • 1-NM-NFI-190A2 has been steady at presentvalueforlast5 minutes.
  • 1-NM-NFI-190B2 has lowered from 1 x iO to present value over last 5 R 102 minutes. io S

P O

10°

.7 p 10 10I 5 17e4 375.7 Unit Supervisor directs the operator to switch 1 -NM-NFl-i 90A & B to the alternate power supply using the Appendix R switch.

Which of the following describes:

1) The Nuclear Instrument indication at the Remote Monitoring panel as expected.
2) The location of the alternate power App R switch for 1-NM-NFl-i 90A & B is located in the A. 1) is not
2) Cable Tray Room Unit 2 B. i)is
2) Cable Tray Room Unit 2 C. 1)isnot
2) Emergency Switchgear Room Unit 2 D. 1)is
2) Emergency Switchgear Room Unit 2

Question: 53 Both Units are operating at 100% power.

Which ONE of the following water sources is collected directly into the High/Low Level Liquid Waste Tanks prior to transfer to the SRF?

A. Laundry Drains.

B. Contaminated Drain Tank.

C. Auxiliary Building sump pump discharge.

D. VCT Drain.

Question: 54 Given the following:

  • Unit 1 is at 100%, Unit 2 is in a Refueling Shutdown.
  • l-GW-RM-130A, Rad Monitor Process Vent Particulate indication spiked high causing the following alarms:

o 0-RMA-C5, Process Vent Rad Mon Trbl.

o 0-RMA-C6, Process Vent Part Alert I Hi.

Which ONE of the following describes the automatic plant response?

A. 1-IA-TV-lOlA, and 1-IA-TV-biB, Unit 1 Containment Instrument Air compressor suctions will swap to outside air.

B. i-CV-P-1A, and i-CV-P-i B, Unit 1 Containment vacuum pumps will trip.

C. i-SV-TV-103, Air Ejector Discharge to Vent-Vent Trip valve will automatically close.

D. i-GW-FCV-160, Unit 1 vacuum pump discharge valve, will automatically close.

Question: 55 Unit 2 is shutdown and has been borated to CSD boron concentration in preparation for Cooldown to CSD for a Refueling outage.

Chemistry has notified the Team that the RCS crud burst has been initiated.

Which ONE of the following describes:

1) The FIRST Radiation monitor that will detect the increased RCS Activity caused by the crud burst.
2) Which CVCS filter is monitored for differential pressure during the crud burst cleanup?

A. 1) Letdown Radiation monitor.

2) Reactor Coolant filter.

B. 1) Letdown Radiation Monitor.

2) Letdown filter.

C. 1) Auxiliary Building Control Area Radiation Monitor.

2) Reactor Coolant filter.

D. 1) Auxiliary Building Control Area Radiation Monitor.

2) Letdown filter.

Question: 56 Given the following:

  • Unit 1 and Unit 2 are both operating at 100%.
  • You are preparing for a Performance Test of Charging Pump SW pump, 1-SW-P-bA Appendix R controls.
  • An operator needs to be stationed locally at 1-SW-P-i OA to observe the pump, and a second operator at the Appendix R controls for 1-SW-P-1OA to start and stop the pump.

The Charging Pump SW pump, 1-SW-P-iDA is located inside (1), and the Appendix R controls for i-SW-P-bA are located inside Unit 1(2) room.

A. 1) MER 4 2) Emergency Switchgear B. 1) MER 4 2) Cable Vault C. 1) MER 3 2) Cable Vault D. 1) MER 3 2) Emergency Switchgear

Question: 57 Which ONE of the following states:

1) The minimum canal level per Tech Spec 3.14, Circulation and Service Water Systems.
2) The channel coincidence required to cause BC SW isolation?

A. 1) 23.5 feet.

2) 2/4 Channel.

B. 1) 23.5 feet.

2) 3/4 Channels.

C. 1) 23.0 feet.

2) 2/4 Channels.

D. 1) 23.0 feet

2) 3/4 Channels.

Question: 58 A severe thunderstorm has caused perturbations on the grid. 0-AP-1 0.18 has been entered due to grid instabilities Initial Conditions:

  • Unit 1 is at 100% power, Unit 2 is shutdown.
  • The A and B Voltage regulators are in AUTO.
  • The A Voltage Regulator is in service.
  • Power System Stabilizer (PSS) is in service.
  • 55 MVARS Out.

Current Conditions:

  • The Operator reports a large rise in MVARS (Out).

o 1J-A8, OVEREXCITATION LIMIT.

o 1J-B7, VREG CHANNEL A LOCAL ALARM.

Which of the following occurs if the A Voltage Regulator is unable to lower Generator voltage in its current mode?

A. A Voltage Regulator will shift to the V/Hz mode to control voltage. The B channel will remain in standby.

B. A Voltage Regulator will trip into Emergency Manual. The B channel will automatically assume control.

C. A Voltage Regulator will trip into Emergency Manual to control voltage.

The B channel will remain in standby.

D. A Voltage Regulator will shift to the V/Hz mode to control voltage. The B channel automatically assume control.

Question: 59 Which ONE of the following describes the operation of Instrument Air compressor 1-IA-C-i when in AUTO?

A. Compressor will start and LOAD when pressure drops to 90 psig.

Compressor will then UNLOAD and LOAD at 105 psig and 95 psig, respectively.

B. Compressor will start and LOAD when pressure drops to 95 psig.

Compressor will then UNLOAD and LOAD at 105 psig and 95 psig, respectively.

C. Compressor will start and LOAD when pressure drops to 100 psig.

Compressor will then UNLOAD and LOAD at 110 psig and 100 psig, respectively.

D. Compressor will start and LOAD when pressure drops to 90 psig.

Compressor will then UNLOAD and LOAD at 110 psig and 100 psig, respectively.

Question: 60 Initial Conditions:

  • Unit 1 was operating at 100%.
  • Containment pressure peaks at 45 psia.

Current Conditions:

  • RWST level has just reached 60% one minute ago and is lowering.
  • Containment pressure is 22 psia and lowering.

Which ONE of the following describes:

1) The status of Recirc Spray pumps.
2) The minimum number of Containment Spray and Recirc Spray pumps needed to cool and depressurize the containment to < 1 psig in <60 minutes following a Design Basis LOCA.

A. 1) Both Outside Recirc Spray pumps are running, Inside Recirc Spray pumps are off.

2) One Containment Spray pump and two Recirculation Spray pumps.

B. 1) Both Inside Recirc Spray pumps are running, Outside Recirc Spray pumps are off.

2) One Containment Spray pump and two Recirculation Spray pumps.

C. 1) Both Outside Recirc Spray pumps are running, Inside Recirc Spray pumps are off.

2) One Containment Spray pump and Recirculation Spray pump.

D. 1) Both Inside Recirc Spray pumps are running, Outside Recirc Spray pumps are off.

2) One Containment Spray pump and one Recirculation Spray pump.

Question: 61 The reactor is starting up following a refueling outage, in accordance with 1-GOP-i .8. Unit Startup, HSD to Max Allowable Power.

Which ONE of the following identifies:

1) The flowpath used when diluting to critical in accordance with 1-OP-CH-007, Blender Operations.
2) The method used to stabilize reactor power at 1 Q 8 amps.

A. 1) DilutetotheVCT Inlet.

2) Boration I Dilution.

B. 1) DilutetotheVCT Inlet.

2) Rods.

C. 1) Alternate dilute to CH pump suction.

2) Boration I Dilution.

D. 1) Alternate dilute to CH pump suction.

2) Rods.

Question: 62 Given the following conditions:

  • Unit 1 is at 12% power.
  • The team is currently performing 1-GOP-i .8, Unit Startup, and are checking trip status lights in preparation for blocking Intermediate Range and Power-Range (LO Setpoint) trips.
  • The team depresses Intermediate-Range and Power-Range (LO Setpoint) Block pushbuttons.
  • Trip Status lights are as follows:

Light# Noun name As-found Required A3 P-b NIS PWR RGE> 10% LIT LIT Ci NIS PWR RNG LO SP TRIP BLOCKED NOT LIT LIT

  • The team notes that status light Ci is in wrong state, checks bulb and finds bulb is good.

Which ONE of the following describes how the plant will respond if the team continues to raise power.

1) At what power will the reactor trip?
2) What is the coincidence for the reactor trip?

A. 1)35%. 2)1/4.

B. 1)23%. 2)2/4.

C. 1)23%. 2)1/4.

D. 1)35%. 2)2/4.

Question: 63 An Operator has been briefed and sent to perform 1-OPT-FW-OO1, Motor Driven Aux Feedwater Pump 1 -FW-P-3A. While placing 1 -FW-P-3A in the proper lineup for the test, a typographical error for a valve mark number is discovered.

Which ONE of the following completes the following statement regarding the actions to be perfomed in accordance with AD-AA-1 00, Technical Procedure Process Control, to address the issue?

After making a pen and ink change, the Operator_(1).. required to have a supervisor initial and date the correction before proceeding. After completing the OPT, a procedure change request (FIP)

(2)_ required to be processed.

A. (1)is (2) is not B. (1)isnot (2) is not C. (1)isnot (2) is D. (1)is (2) is

__________

Question: 64 Unit 1 is currently Shutdown, and making preparations to perform 1 -OPT-ZZ-0O1, ESF Actuation with Undervoltage and Degraded Voltage 1H Bus. This procedure is an ICCE category Ill.

In accordance with OP-AA-1 06, Infrequently Conducted or Complex Evolutions, select the answer that correctly completes the following statements.

1) Specific criteria for terminating the test and contingency plans for unexpected occurrences required per Attachment 2 of OP-AA-1 06.
2) The is specifically responsible for the safe operation of the station during performance of the test.

A. 1) is

2) Senior Operations Manager B. 1) is not
2) Shift Manager C. 1) is not
2) Senior Operations Manager D. 1) is
2) Shift Manager

Question: 65 Given the following:

  • Unit 1 is operating at 100% power.
  • A Subatmospheric Containment Entry is to be made in accordance with VPAP-01 06, to identify the source of a step change in Unidentified leakage of +0.4 gpm.
  • The Shift Manager has entered Action Level 3 for RCS leakage and has notified the OMOC.

Which ONE of the following identifies:

1) The minimum level of authority for the containment entry is (1).
2) The HP Shift Supervisor or designee must _(2)_.

A. (1) Plant Manager (2) Sign on to the In-Core Detector tagout B. (1) Plant Manager (2) Verify In-Core Detectors in storage location C. (1) Director, Nuclear Safety and Licensing (2) Sign on to the In-Core Detector tag out D. (1) Director, Nuclear Safety and Licensing (2) Verify In-Core Detectors in storage location

Question: 66 initial Conditions:

  • Unit 1 is in a refueling outage.
  • Fuel off-load is in progress.

Current Conditions:

  • A report is received that a fuel assembly being removed from the core was significantly damaged while lifting it from the core.
  • Large Bubbles were seen escaping from the damaged fuel assembly.
  • NO radiation alarms have been received.

Which ONE of the following describes the actions required by O-AP-22.OO, Fuel Handling Abnormal Conditions:

1) Closing 1-VS-MOD-i 03A and 1-VS-MOD-i 03C will secure
2) Is Containment Evacuation required?

A. 1) 1-VS-F-15, MCR Exhaust

2) Yes.

B. 1) 1-VS-AC-4, MCR Supply

2) No.

C. 1) 1-VS-AC-4, MCR Supply

2) Yes.

D. 1) 1-VS-F-15, MCR Exhaust

2) No.

Question: 67 Which ONE of the choices below completes the following statement?

The Federal Dose limit for Lens of the Eye is per year.

A. 15 Rem B. 1.5 Rem C. 5.0 Rem D. 50 Rem

Question: 68 Which of the following Critical Safety Function RED paths is the highest priority CSF that can be directly caused by procedurally directed operator action?

A. Subcriticality.

B. Core Cooling.

C. Heat Sink.

D. Containment.

Question: 69 The Station has just upgraded from an Alert to a Site Area Emergency.

Which ONE of the following actions is required for a Site Area Emergency in addition to those actions initiated for the Alert?

A. Off-Site monitoring Team Dispatched.

B. Emergency Response Personnel called in.

C. A Report of Radiological Conditions to the State is transmitted.

D. Accountability is performed.

Question: 70 Given the following:

  • 0800: A large break LOCA occurred.
  • 0810: A Site Area Emergency was declared.

In accordance with EPIP-2.01, when obtaining meteorological data from the MET panel:

1) The preferred source for wind speed, and wind direction is the Main Tower (1)
2) The required Notification completion time is recorded following roll call after reading Item (2)

A. 1)LowerLevel 2)11, Additional Information B. 1)LowerLevel 2)1, Emergency Classification C. 1)UpperLevel 2)11, Additional Information D. 1)UpperLevel 2)1, Emergency Classification

Question: 71 Initial Conditions:

  • Unit 2 operating at 100% power.
  • A LOCA has occurred in Unit 2 Safeguards.
  • Unit 2 is tripped and safety injection actuated.
  • 2-Sl-MOV-2890C, LHSI to Cold Legs, has been closed.
  • RCS Pressure is 1005 psig and rising.
  • The Team has transitioned to 2-E-1, Loss of Reactor or Secondary Coolant.

In accordance with 2-E-1, Loss of Reactor or Secondary Coolant, which ONE of the following identifies:

1) The status of the LHSI pumps.
2) The position of the LHSI Suction Valves from the RWST, 2-Sl-MOV-2862A and B.

A. 1) Secured in PTL.

2) Closed.

B. 1) Secured in AUTO.

2) Closed.

C. 1) Secured in PTL.

2) Open.

D 1) Secured in AUTO.

2) Open.

Question: 72 Given the following:

  • Unit 1 was operating at 100% when a large break LOCA occurred.
  • RCS pressure is 25 psig.
  • All ECCS equipment responded as designed.
  • The crew is performing step 4 of 1-E-1, Loss of Reactor or Secondary coolant.
  • The STA reports that red path for Integrity is satisfied and recommends FR-P.1.

Which of the following describes:

1) The actions the crew would take in response to the Integrity Red path.
2) The reason these actions are taken.

A. 1) Go to FR-P. 1, and after step 1 return to 1 -E-1.

2) Steam Generators are thermally disconnected from the RCS.

B. 1) Go to FR-P. 1, and after step 1 return to 1 -E-1.

2) Pressurized thermal shock is not a concern.

C. 1) Do not enter FR-P.1, continue in 1-E-1 until directed to transition.

2) Steam Generators are thermally disconnected from the RCS.

D 1) Do not enter FR-P.1, continue in 1-E-1 until directed to transition.

2) Pressurized thermal shock is not a concern.

Question: 74 Given the following:

  • A Large Break LOCA has occurred.
  • Crew is presently performing step 3 of ES-i .3
  • RWST level is at 14%.

Which of the following completes the following statements.

i) Auto Swapoverto RMT will occur when RWST level transmitters reach 13.5%.

2) In accordance with 1-ES-i .3, Transfer to Cold Leg Recirculation, step 5; IF RMT fails to automatically actuate the RO manually initiates RMT by depressing pushbuttons for each train.

A. i) 2of4

2) 2of2 B. 1) 3of4
2) 2of2 C. 1) 3of4
2) lof2 D. i) 2of4
2) 1 of2

Question: 75 Initial Conditions:

  • Both Units are operating at 100% power.

Current Conditions:

  • The STA reports that Containment Sump Level is 7.8 feet and rising.

Which ONE of the following identifies:

1) The Abnormal Procedure initiated by 1-E-0 Immediate Actions.
2) The PATH COLOR in effect on the Containment Status Tree.

A. 1) 0-AP-37.00, Seismic Event.

2) Red.

B. 1) 0-AP-37.00, Seismic Event.

2) Orange.

C. 1) 1-AP-10.07, Loss of Unit 1 Power.

2) Red.

D. 1) 1-AP-10.07, Loss of Unit 1 Power.

2) Orange.

RO EXAM LIST OF ATTACHMENTS Attachment # Attachment Description 1 Containment Ventilation 2 E-3 Table

2015 NRC ANSWER KEY Question # Answer Question Answer

RO 1 B 41 C 2 A 42 C 3 A 43 A 4 A 44 B 5 B 45 D 6 D 46 B 7 A 47 C 8 B 48 B 9 B 49 C 10 D 50 A 11 B 51 B 12 C 52 C 13 D 53 C 14 C 54 D 15 A 55 A 16 B 56 A 17 A 57 D 18 C 58 B 19 A 59 D 20 D 60 B 21 A 61 D 22 A 62 B 23 D 63 A 24 A 64 D 25 B 65 C 26 C 66 C 27 D 67 A 28 B 68 C 29 A 69 A 30 C 70 B 31 C 71 A 32 C 72 B 33 C 73 A 34 D 74 A 35 A 75 D 36 D 37 C 38 B 39 D 40 C NRC Validation Page 1

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