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{{#Wiki_filter:ES-401, Rev. 9              Site-Specific SRO Written Examination                  Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
Date: August 28, 2012                            Facility/Unit: Surry Nuclear Power Plant Region:        I/jj/lIl/IV                        ReactorType:W/CE/BW/GE Start Time:                                      Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours to complete the combined examination, and 3 hours if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicants Signature Results RO/SRO-Only/Total_Examination Values Applicants Scores                                                      /      /          Points Applicants Grade                                                    /      /          Percent
: 1. Initial conditions:
* Unit 1 is at 90% power.
* Reactor protection testing is in progress on Train A.
* Reactor Trip Breaker B is closed.
* Reactor Trip Breaker A is open.
* Reactor Trip Bypass Breaker A is closed.
Current Conditions:
* No other breaker manipulations have been performed.
Which ONE of the following describes the immediate response to the reactor trip breaker B and the reactor trip bypass breakers if the Reactor Trip Bypass Breaker B is closed?
A. Reactor Trip Bypass Breakers A and B will trip open.
Reactor Trip Breaker B will trip open.
B. Reactor Trip Bypass Breakers A and B will trip open.
Reactor Trip Breaker B will remain closed.
C. Reactor Trip Bypass Breaker B will trip open. Reactor Trip Bypass Breaker A will remain closed.
Reactor Trip Breaker B will remain closed.
D. Reactor Trip Bypass Breakers A and B will remain closed.
Reactor Trip Breaker B will remain closed.
: 2. Initial Conditions                      *            -__________________
* Unit 1 is at 100% and 2250 psig.
* The PRT is at 3 psig.
Current Conditions
* Annunciator 1 D-H4, PRZR SFTY VV I PWR RELIEF VV OPEN is alarming.
* The PRT is 10 psig and increasing.
* Reactor Pressure is 2210 psig and decreasing.
* There is a report that the local safety valve acoustic monitor indicates a valve partially open.
Which ONE of the following describes the appropriate actions lAW ARP 1 D-H4?
The leaking valve is confirmed by the associated downstream temperature reading approximately          (1)      ,and the crew is required to    (2).
A. (1) the saturation pressure of the Pressurizer (2) initiate 1 -E-0, Reactor Trip or Safety Injection B. (1) the saturation pressure of the Pressurizer (2) close the associated PORV block valve C. (1) the saturation pressure of the PRT (2) initiate 1 -E-0, Reactor Trip or Safety Injection D. (1) the saturation pressure of the PRT (2) close the associated PORV block valve
: 3. The following conditions exist:
* Unit 1 has tripped from 100% power due to a Large Break Loss of Coolant Accident (LBLOCA).
* The operating crew has transitioned to 1 -E-1, LOSS OF REACTOR OR SECONDARY COOLANT, step 22, Check if SI accumulators should be isolated.
* RCS hot leg temperatures are:
* Loop A Th = 394 F.
* Loop B Th = 393 F.
* Loop C Th = 396 F.
* Power is available to all Accumulator discharge isolation valves.
* Both trains of SI have been reset.
Which ONE of the following completes the statement:
1 -E-1 directs isolation of    (1)  , and the MOVs for the accumulators to be isolated can be closed with the ACC Interlock in      (2)
A. (1) A, B and C Accumulators (2) NORMAL B. (1) A and B Accumulators, but not C Accumulator (2) NORMAL C. (1) A, B and C Accumulators (2) DEFEAT D. (1) A and B Accumulators, but not C Accumulator (2) DEFEAT
: 4. Initial conditions:
* Unit 1 is at 100% power.
* Pressurizer (PRZR) is at program level.
* Charging Pump A is running.
* Charging Pumps B and C normal breakers are racked in, and their switches in the Control Room are in AUTO.
Current conditions:
* Charging flow and discharge pressure are erratic.
* Charging pump amps are erratic on all three running pumps.
* Seal injection is oscillating between 4 and 5 gpm.
* PRZR level is at 19% and lowering. Charging flow has not been restored.
* 1-AP-8.00, Loss of Normal Charging Flow has been entered.
* Letdown flow and pressure indications are oscillating.
Which ONE of the following describes the correct sequence of actions lAW 1 -AP-8.00 to secure charging and letdown, and restore pressurizer make-up?
A. Trip Unit 1 ONLY. THEN isolate letdown and place all Unit One charging pumps in PTL. Dispatch personnel to vent and restart a charging pump.
B. Trip BOTH Units. THEN isolate letdown and place all Unit One charging pumps in PTL.
Dispatch personnel to establish charging cross-tie from Unit Two.
C. Isolate letdown and place all Unit One charging pumps in PTL. THEN Trip Unit 1 ONLY.
Dispatch personnel to vent and restart a charging pump.
D. Isolate letdown and place all Unit One charging pumps in PTL. THEN Trip BOTH Units.
Dispatch personnel to establish charging cross-tie from Unit Two.
: 5. Initial Conditions:
            -  Unit 1 has been shutdown for 35 days
            -  The RHR System aligned for normal operation.
            -  RCS level is at mid-loop 12.4 feet and stable as read on 1-RC-Ll-100A.
            -  The A RHR pump is running.
            -  1 -RH-FC-1 605C (RHR HXS BYP FLOW) controller fails to 100% full open demand in AUTO Current Conditions:
            -  RHR flow is oscillating from 1500 to 3000 gpm.
            -  A RHR pump amps are oscillating
            -  RHR HX LO FLOW annunciator, 1B-G6 alarming Based on the above conditions, which ONE of the following identifies the correct action to mitigate the event as directed by 1-AP-27.00 (LOSS OF DECAY HEAT REMOVAL CAPABILITY)?
A. Raise RCS level by opening 1-SI-MO V-i 869A (Th HHSI Isolation MOV).
B. Reduce RHR flow by placing 1-RH-FC-1605C in MAN and lowering demand.
C. Stop the A RHR pump.
D. Start the B RHR pump.
: 6. Unit 1 Initial Conditions:
* 75% Power at Middle-of-Life (MOL) conditions.
* Excess Letdown is in service in preparation for removing Normal Letdown from service.
Current conditions:
* Component Cooling (CC) surge tank level is slowly DECREASING at 1% every 5 minutes.
* VCT level is slowly increasing.
* No operator actions have been taken.
Which ONE of the following completes the statement below?
The above conditions are consistent with a tube leak in the  (1)  , which will cause reactor power to      (2)
A. (1) RCP Seal Return Heat Exchanger (2) increase B. (1) RCP Seal Return Heat Exchanger (2) decrease C. (1) Excess Letdown Heat Exchanger (2) increase D. (1) Excess Letdown Heat Exchanger (2) decrease
: 7. Unit 1 plant conditions:
* Rx heatup is in progress
* RCS pressure is 1900 psig Which ONE of the following is the response of the pressurizer PORVs if pressurizer pressure transmitter 1-RC-PT-1444 fails high?
A. Only 1-RC-PCV-1455C will open.
B. Only 1-RC-PCV-1 456 wiN open.
C. Both 1-RC-PCV-1 4550 and 1-RC-PCV.-1456 will open.
D. Neither 1-RC-PCV-1 4550 nor 1-RC-PCV-1456 will open.
: 8. Unit 1  has experienced an Anticipated Transient Without Trip (ATWT).
* Operators have transitioned out of 1 -E-0 to 1 -FR-S.1
* SI has NOT been initiated.
* Charging Flow is 80 gpm.
* The BATP has been placed in FAST
* 1-CH-MOV-1 350 (Emergency Borate Valve) will not open from the Control Room.
Based on the above conditions, which ONE of the following choices identifies the required procedure actions for getting boron into the reactor per 1-FR-S.1?
A. Start a second Charging pump and fully open 1 -CH-FCV-1 122 (Charging Flow Control Valve).
B. Locally open 1-CH-MOV-1350, after 21 minutes close 1-CH-MOV-1350.
C. Open 1-CH-MOV-1115B and D (CHG pump suction from RWST) and Close 1 -CH-MOV-1 11 SC and E (CHG PUMP SUCTION FROM VCT).
D. Manually open 1-CH-FCV-1113A (BORON TO BLENDER FLOW CONTROL), then dispatch an operator to establish Manual Emergency Boration by opening 1 -CH-228 (MANUAL EMERGENCY BORATE STOP)
: 9. The following plant conditions exist:
* Tube Rupture on A SG.
* The operating team has cooled the RCS to 485 °F and completed the RCS depressurization.
* The ruptured SG pressure is 935 psig.
* Pressurizer level is 65%.
* Ruptured SG level is 45% NR and decreasing.
The operating team is currently performing step 35, Control RCS Pressure and CHG Flow to Minimize RCS to Secondary Leakage.
Which ONE of the following (1) describes the actions required by E-3, and (2) the basis for this action?
A. (1) Turn ON pressurizer heaters to raise RCS pressure.
(2) This will minimize RCS volume loss.
B. (1) Turn ON pressurizer heaters to raise RCS pressure.
(2) This will lead to a reduction in pressurizer level.
C. (1) Use main or auxiliary spray to lower RCS pressure.
(2) This will minimize RCS volume loss.
D. (1) Use main or auxiliary spray to lower RCS pressure.
(2) This will lead to a reduction in pressurizer level.
 
flO. Reactor power was noted to be 101% and rapidly rising. The crewtripped the reactor and entered E-0, Reactor Trip or Safety Injection.
There is a report of a significant break on the supply to the TDAFW. All personnel have been evacuated from the area due to the unsafe conditions.
The crew has transitioned to ECA-2.1, Uncontrolled Depressurization of All Steam Generators.
Given the following:
* All Narrow Range Cold leg Temperature indications have lowered 18 °F in the last 5 minutes.
* Feedf low to each Steam Generator has been adjusted to 60 gpm.
* A Steam Generatorlevel isll%NR o  B Steam Generator level is 8% NR
* C Steam Generator level is 10% NR
* All Steam Dumps are closed.
Which ONE of the following describes the required actions lAW ECA-2.1?
A. Lower feeding each steam generator to 25 gpm.
B. Stop feeding all Steam Generators.
C. Stop feeding only the A and C Steam Generators.
D. Continue feeding all Steam generators at the current flow rates.
: 11. The AAC Diesel Generator is removed from service for scheduled maintenance. A sustained loss of offsite power has led to a reactor and turbine trip. The #1 and #3 EDG fail to start.
Five (5) minutes after the trip, the following conditions exist:
* RCS Pressure is 2107 psia and slowly lowering.
* Highest CETC is 575 °F and slowly rising.
TC is 509 °F and slowly lowering.
* Delta T is 64 °F and slowly rising.
* SG pressure is 720 psig and stable.
Which ONE of the following describes the status of RCS heat removal?
A. Reflux Cooling has developed.
B. A pending loss of natural circulation is indicated.
C. Single phase natural circulation is fully developed.
D. Natural circulation is developing.
: 12. A loss of Vital Bus ll has just occurred.
Which ONE of the following describes the reason that AP-1 0.03, Loss of Vital Bus lii, requires the operators to trip the reactor?
Losing the vital bus causes a loss of A. CC to the RCP thermal barriers.
B. Pressurizer pressure control.
C. CC to the A RCP lube oil cooler.
D. Main and bypass Feed Regulating Valve Control.
: 13. With the unit initially at 100% power, a fault developed in the 1A battery bank (failed cell) that resulted in a loss of the 1A DC bus. Electricans have verified that the DC distribution system is unaffected.
Which ONE of the following states the recovery method for the 1A DC bus in accordance with 1-AP-1 0.06 (Loss of DC power)?
A. Direct electricians to lift battery leads, open all breakers in the DC distribution panels, and align at least one battery charger to the DC bus.
B. Direct electricians to lift battery leads and align at least one battery charger to the DC bus.
C. Direct electricians to lift battery leads and close the A DC bus crosstie breaker.
D. Direct electricians to lift battery leads, open all breakers in the DC distribution panels, and close the A DC bus crosstie breaker.
 
r 14. Unit 1 initial conditions:
* 100% power.
* A Charging Pump is in service.
* The following alarms received in the Main Control Room:
* 1 D-G5, SW or CC Pps Disch to Chg Pps Lo Press
* 0-VSP-M4, Flood Cont Pnl Trbl
* Flood Panel light LS-.DA-1 1 5A-1, Unit #1 ESGR is illuminated.
Which ONE of the following completes the statement below?
The above conditions are consistent with a rupture of the supply piping from the Charging Pump        (1)    system. If left uncorrected, A Charging Pump    (2) could be damaged.
A. (1) Component Cooling (2) seals
: 8. (1) Component Cooling (2) bearings C. (1) Service Water (2) seals D. (1) Service Water (2) bearings
: 15. Unit 1 initial conditions:
* A SBLOCA has occurred.
* Containment pressure reached a maximum of 18.3 psia Current conditions:
* Containment pressure has stabilized at 16.5 psia.
Which ONE of the following completes the description of control room indications on the Containment Instrument Air system?
1-IA-PT-i 06, Containment Instrument Air pressure, indicates    (1), and 1 -lA-TV-i 01 A/B, Normal Compressor Suction Valves, are      2).
A. (1) pressurized (2) OPEN B. (1) pressurized (2) CLOSED C. (1) depressurized (2) OPEN D. (1) depressurized (2) CLOSED
: 16. A transient is in progress and the following alarms have been received:
* 1 B-F3, SFGDS AREA SUMP HI LEVEL is in ALARM.
* 1C-B8, PRZR LO PRESS.
* 1C-D8, PRZR LO LVL.
* 1F-A7 (B7), STM GEN A LO LVL CHN 1 (CHN 2)
* 1F-A8 (B8), STM GEN B LO LVLCHN 1 (CHN 2)
* 1 F-A9, (B9), STM GEN C LO LVL CHN 1 (CHN 2)
* 1 H-B8, AFW Pump 3A LOCKOUT OR OL TRIP is in ALARM.
* 1-RM-D4, 1-RM-RI-154 (AUX BLDG CONT) HIGH is in ALARM.
Which ONE of the foIIowng casualties is in progress?
A. Steam Generator Tube Rupture B. LOCA Outside Containment C. LOCA Inside Containment D. LossofSecondaryHeatSink
 
17.Whkth one of the following correcy comçetes the statements listed below in accordance with the requirements of 1 -ECA-1 .1 (LOSS OF EMERGENCY COOLANT RECIRCULATION)?
The RMT MODE TRANSFER SWITCH will be placed in the            (1) mode.
And If containment sump blockage exists when 1-ECA-1 .1 is entered, A. 1) REFUEL
: 2) FR procedures apply throughout the procedure B. 1) REFUEL
: 2) FR procedures are suspended until directed C. 1)RMT
: 2) FR procedures apply throughout the procedure D. 1)RMT
: 2) FR procedures are suspended until directed
: 18. Unit 1 Initial Conditions:
* Unit 1 has experienced a LOCA from 100% power.
Unit 1 Current Conditions:
* PRZR pressure is 2200 psig.
* CETC temperatures are increasing.
* Containment Pressure is 21 psia.
* RCS Hot Leg temperatures are 552 degrees F and increasing.
* AFW flow has been lost to all Steam Generators.
* WIDE RANGE level in 1A Steam Generator is 21 %.
* WIDE RANGE level in 18 Steam Generator is 20%.
* WIDE RANGE level in 1C Steam Generator is 20 %.
* The Unit Supervisor has directed entry into 1-FR-.H.1 (RESPONSE TO LOSS OF SECONDARY HEAT SINK).
Based on Current Conditions, which ONE of the following correctly completes the statements listed below in accordance with 1-FR-H.1 (RESPONSE TO LOSS OF SECONDARY HEAT SINK)?
When the ability to supply feedwater is restored, feed flow should initially be A. limited to 60 gpm per SG B. limited to 100 gpm per SG C. minimum of 350 gpm total D. established to ONE SG at the maximum available rate
 
1 9. Unit 1 Current Conditions:
* One Control Rod has dropped (Rod Bottom Light lit).
* The Rod Control System is in Manual.
* Tave is 532 degrees F and decreasing.
Based on the Current Conditions, which one of the following correctly completes the statements listed below?
The earliest a Reactor trip will be required is if Tave decreases below  jJ degrees F.
And That Reactor trip will be required by      (2)
A. (1)522 (2) the Technical Specification Minimum Temperature for Criticality B. (1)530 (2) the Technical Specification Minimum Temperature for Criticality C. (1)530 (2) 0-AP-1 .00 (ROD CONTROL SYSTEM MALFUNCTION)
D. (1)522 (2) 0-AP-1 .00 (ROD CONTROL SYSTEM MALFUNCTION)
: 20. Which ONE of the following correctly completes the statements listed below?
When performing an emergency boration per 1-AP-3.00 (EMERGENCY BORATION), the in-service BATP      (1)    automatically be shifted to FAST.
1 -CH-MOV-1 350 (emergency borate valve) can be electrically operated at the jj A. (1) will NOT (2) Main Control room and Aux Shutdown Panel B. (1)will NOT (2) Main Control Room Only C. (1) will (2) Main Control Room and Aux Shutdown Panel D. (1) will (2) Main Control Room Only
: 21. Initial conditions:
* Unit 1 is at 100% steady state power
* All systems are in Automatic
* The Pressurizer Level Control Selector Switch is in position I/Ill.
Current conditions:
* The bellows inside the differential pressure cell for pressurizer level transmitter 1-RC-LT-1461 (Channel III Pressurizer Level) completely ruptures.
* No operator action occurs.
Which ONE of the following describes the immediate initial response of the pressurizer level control system?
A. Charging flow decreases.
Annunciator 1C-C8, PRZR HI LVL HTRS ON alarms.
B. Charging flow increases.
Annunciators 1C-E8, PRZR LO LVL HTRS OFF & LETDOWN ISOL and 1C-D8, PRZR LO LVL alarm.
C. Charging flow remains constant.
Annunciator 1C-E8, PRZR LO LVL HTRS OFF & LETDOWN ISOL alarms.
D. Charging flow remains constant.
Annunciator 1 E-H3, RX TRIP CH 3 PRZR HI LVL alarms.
: 22. Initial Conditions
* A Unit 1 Reactor Trip occurs from 60% power.
Conditions 25 minutes jost-trir
* N-35 indicates 4x10
                          ° amps, SUR of 0 DPM.
1
* N-36 indicates lxi Q-11 amps, SUR of 0 DPM.
Which ONE of the following describes the current conditions?
A. N-35 is undercompensated.
N-31 and N-32 must be manually energized.
B. N-35 is undercompensated.
N-31 and N-32 energized automatically.
C. N-35 is overcompensated.
N-31 and N-32 must be manually energized.
D. N-35 is overcompensated.
N-31 and N-32 energized automatically.
: 23. Unit 1  Initial Conditions:
* LOCA inside containment.
* 1-E-1 Loss Of Reactor Or Secondary Coolanf in progress
* Both Train A and Train B of cold leg recirculation are NOT available.
Current Conditions:
* Unit Supervisor directs transition to 1 -ECA-1 .1, Loss of Emergency Coolant Recirculation
* A RED path exists for Containment
* RWST level is 5%
Which ONE of the following correctly states which procedure should be used for operation of the Containment Spray Pumps, AND whether or not CS Pumps are required to be placed in Pull to Lock (PTL) based on the Current Conditions?
CS Pumps operation is directed by        (1)    , AND CS Pumps        (2)  required to be placed in PTL in accordance to the selected procedure.
A. (1)ECA-1.1 (2) are B. (1)ECA-1.1 (2) are NOT C. (1) FR-Z.1 (2) are D. (1)FR-Z.1 (2) are NOT
: 24. Given the following plant conditions:
* A S/G Pressure is 1250 psig.
* A SIG Narrow range level is 82%
* RCS hot leg temperatures are 574 degrees F.
* 1-FR-H.2, Response to Steam Generator Overpressure has been entered.
* The condenser is not available.
* The A S/G PORV is stuck closed.
* Turbine Driven AFW pump is out of service for bearing replacement.
Which ONE of the following describes the preferred method to reduce A S/G pressure in accordance with 1-FR-H.2?
A. Feed A S/G with AFW and commence an RCS cooldown to less than 540 degrees F.
B. Feed A S/G with AFW and establish Blowdown from the A steam generator.
C. Isolate AFW to the A S/G and commence RCS cooldown to less than 540 degrees F.
D. Isolate AFW to the A S/G and establish Blowdown from the A Steam Generator.
: 25. the Unit is in HotShutdown with the following conditions:
* Tavg is 547 °F.
* Pressurizer pressure is 2235 psig.
* RCS boron is at the CSD value of 1120 ppm.
* Initial Source Range counts are 45 cps.
* All Control Rods are inserted.
* Shutdown 7 days ago The shutdown banks are withdrawn in accordance with procedure GOP-i .4 Unit Startup, HSD To 2% Reactor Power.
When the shutdown banks are fully withdrawn, the following Source Range data is recorded:
N-31 counts are 82 cps N-32 counts are 202 cps Based on the above indications, which ONE of the following BEST describes the Source Range data that was collected and required actions (if any)?
A. N31 is indicating an abnormally low count rate, initiate 1-AP-4.00 (NI Malfunction).
B. N32 is indicating an abnormally high count rate, initiate 1-AP-4.00 (NI Malfunction).
C. Source range response is as expected, no abnormalities exist.
D. Current RCS boron is not as expected, initiate 1-AP-3.00 (Emergency Boration).
: 26. Initial Conditions:
* LOCA occurred on Unit 1.
* SI has been RESET.
* Operators are implementing 1-ES-i .2, POST LOCA COOLDOWN AND DEPRESSURIZATION.
* 90 F/hr cooldown is in progress.
* RCP C is the ONLY running RCP.
Current Conditions:
* Operators are at the step in i-ES-i .2 to CHECK SI FLOW NOT REQUIRED.
* RCS subcooling requirement is NOT met.
* One charging pump is in service.
Based on the current conditions, which ONE of the following is the NEXT action required by i-ES-i .2 to regain subcooling?
A. Energize all available pressurizer heaters and maintain current RCS pressure.
B. Increase the cooldown rate to <100 &deg;F/hr and ensure PRZR level can be maintained >22%.
C. Reinitiate SI by operation of the SI pushbuttons and verify HHSI flow path to RCS cold legs.
D. Manually start CHG pumps and align HHSI flow path to RCS cold legs.
: 27. Unit 1  Conditions
* A reactor trip has occurred on Unit 1.
* 1-E-O, Reactor Trip or Safety Injection, has been entered.
* Step 5, Initiate Attachment 1, System Alignment Verification, is in progress.
Which ONE of the following statements describes the basis for checking FW isolation in 1-E-O, Attachment 1, System Alignment Verification?
A. To minimize feed flow to reduce the likelihood of thermal shock to SG components.
B. To preclude any excessive FW addition to intact SGs that would cause negative MTC to add positive reactivity insertion and return to criticality.
C. To ensure that excessive FW flow does not cause an overpressure condition of the SGs.
D. To prevent excessive RCS cooldown that could aggravate the initiating transient, especially if it were a steam line break.
: 28. The seal leakoff valve is inadvertently isolated for 1-RC-P-1B(1-CH-HCV-1303B).
Which ONE of the following states the seal package response?
A. The #1 seal assumes full RCS delta-P.
B. The #2 seal assumes full RCS delta-P.
C. The #3 seal assumes full RCS delta-P.
D. The #2 and #3 seals share the RCS delta-P.
: 29. Which one of the following provides indications of #2 seal failure on 1 B RCP (1 -RC-P-1 B)?
REFERENCE PROVIDED A. P1 (1-RC-PI-1402)  = 1200 psig, P2 (1-CH-P!-1155)  =  800 psig, Seal Leakoff  =  1.75 gpm B. P1 (1-RC-Pl-1402)  = 2200 psig, P2 (1-CH-Pl-1155)  =  1100 psig, Seal Leakoff  = 3.00 gpm C. P1 (1-RC-PI-1402)  = 2200 psig, P2 (1-CH-PI-1155)  =  1100 psig, Seal Leakoff  = 0.00 gpm D. P1 (1-RC-PI-1402)  = 1200 psig, P2 (1-CH-PI-1155)  =  1200 psig, Seal Leakoff  = 2.20 gpm
: 30. Unit 1 Initial Conditions at 0100:
* A Large Break LOCA has occurred from 100% power.
* 1-E-1 (LOSS OF REACTOR OR SECONDARY COOLANT) is in progress.
Unit 1 Current Conditions at 0500:
* Annunciator 1A-A7 (RWST LO LVL) is in alarm.
Which ONE of the following correctly completes the statements listed below?
High Head Safety Injection Pump suctions should automatically shift from the RWST to the discharge of the Low Head Safety Injection Pumps at an RWST level of _(1)
And Transfer to      2) leg recirculation is required at this time.
A. (1)20%
(2) cold B. (1)20%
(2) hot C. (1) 13.5%
(2) hot D. (1) 13.5%
(2) cold
: 31. Initial Conditions (0910):
* Unit 1 is at 90%.
* Charging Pump A is RUNNING in AUTO on its NORMAL bus.
* Charging Pump B is OFF in AUTO on its NORMAL bus.
* Charging Pump C is OFF in AUTO on its NORMAL bus.
* 1-CC-FT-i 40A, Flow Transmitter for 1-CC-TV-i 40A (RCP Thermal Barrier CC Outlet Flow Outside Trip Valve) has failed high.
* Annunciator 1 C-D2, RCP Thermal Barrier Return Header HI Flow is alarming.
Current Conditions (0912):
* Charging Pump B is locked out.
* 41 60v bus 1 H is deenergized.
* 4160v bus 1J is energized.
* Unit 1 remains at 90% power.
* No operator actions have occurred.
Which ONE of the following describes the operational implications of the current conditions and the correct action to take?
RCP Seal cooling            (1)    been lost.
An IMMEDIATE Reactor Trip            (2)        required.
A. (1)has (2) is B. (1)has (2) is NOT C. (1) has NOT (2) is D. (1) has NOT (2) is NOT
: 32. The following Unit 1 conditions exist:
* A loss of decay heat removal has occurred and 1-AP-27.00, Loss of Decay Heat Removal Capability, has been entered.
* The RHR system has just been made available.
* Inadequate time to completely vent the RHR system exists prior to boiling in the core.
Which ONE of the following correctly states guidance in 1-AP-27.00 with respect to sweeping air from the RHR lines?
If adequate time to completely vent the RHR system is not available, air can be swept out of the RHR lines by filling the RCS to a MINIMUM of    (1)____ feet on 1-RC-LI-100A (RCS Standpipe), checking a minimum subcooling of 1OF, and running an RHR pump at a flow rate of      2)    gpm.
REFERENCE PROVIDED (1)                          (2)
A.                      12.4                      >2950gpm B.                      12.4                      <2600 gpm C.                      13.5                      >2950gpm D.                      13.5                      <2600 gpm
: 33. Current Conditions
* Unit 1 is in REFUELING OPERATIONS.
* 1-RH-P-lA is in service to 1-RH-E-1A.
* Cavity level is 26 feet above the top of the reactor pressure vessel flange.
* Core alterations are in progress.
Which ONE of the following 1) requires entry into a LCO condition, and 2) whether fuel movement can continue?
A. 1) 1 -RH-E-1 B is isolated and drained for tube leak testing
: 2) Fuel movement MAY continue B. 1) 1 -RH-E-1 B is isolated and drained for tube leak testing
: 2) Fuel movement may NOTcontinue C. 1) 1 -RH-P-i A trips on ground overcurrent
: 2) Fuel movement may NOT continue D. 1)1-RH-P-lA trips on ground overcurrent
: 2) Fuel movement MAY continue
: 34. Unit 1  Conditions:
* A Medium-Break LOCA has occurred.
* The crew is performing the actions of 1 -E-1, Loss of Reactor or Secondary Coolant.
* All RCPs are running.
* 5 minutes ago, Charging Pump A was placed in PTL lAW Step 1 9.b of 1 -E-1 (ESTABLISH CHG PUMP REDUNDANT FLOW PATHS). No valve manipulations have occurred.
* The following information was displayed on the SPDS at the times indicated:
Parameter                      10 minutes ago 5 minutes ago  Current CONTAINMENT CONDITIONS PAGE CONTAINMENT PRESSU REIR                    19.6          19.5        19.4    PSIA 5
RCS INTEGRITY PAGE HIGH HEAD SAFETY INJECTION FLOW 176.2        119.2        120.7    GPM LOOP A HIGH HEAD SAFETY INJECTION FLOW 176.5        119.2        121.1    GPM 100 P B HIGH HEAD SAFETY INJECTION FLOW 176.3        119.1        120.9    GPM LOOP C RCS PRESSURE                        1900          1887        1875    PSIG PRESSURIZER LEVEL                      22.9          21.5        19.1    PCT CORE HEAT REMOVAL PAGE PEAK CORE EXITTEMPERATURE                  595.5        595.7        594.9    DEGF Which ONE of the following describes appropriate actions lAW 1 -E-1?
A. SI is required to be reinitiated by starting A Charging Pump.
B. SI is required to be reinitiated by placing A Charging Pump in AUTO and depressing the SI pushbuttons.
C. SI is not required to be reinitiated. Establish charging pump redundant flow paths with B Charging Pump supplying the normal SI HDR and C Charging Pump supplying the alternate SI HDR.
D. Slis not required to be reinitiated. Establish charging pump redundant flow paths with C Charging Pump supplying the normal SI HDR and B Charging Pump supplying the alternate SI HDR.
: 35. Current Conditions
* Unit 1 is at 100% power when annunciator C-E-7, PRZR RELIEF TK HI TEMP, is received.
* The OATC confirms the alarm is valid, and notes that PRT level, pressure, and temperature have been slowly increasing since assuming the watch.
* The OATC is directed to lower tank temperature lAW 1 -OP-RC-01 1.
Which ONE of the following describes how temperature will be lowered lAW 1 -OP-RC-01 1, Pressurizer Relief Tank Operations?
The PRT is filled by opening 1-RC-TV-1519A and 1-RC-TV-1519B to discharge Primary Grade Water      (1)    the water level in the PRT, and the PRT is subsequently drained to maintain the PRT in the normal level band of        (2).
A. (1) above (2)6080%
B. (1) above (2) 59 83 %
C. (1) below (2) 60 80 %
D. (1) below (2) 59 83 %
: 36. Unit 1 is operating in Mode lat 100% power.
* A review of parameters shows the following:
Time                        1300            1400 PRT Level                    73%            84%
PRTTemperature              108F            185F PRT Pressure                3 psig          4 psig Which ONE of the following relief valves has failed (leaking by)?
A. Regenerative Heat Exchanger Letdown Line Relief Valve, 1-CH-RV-1 203 B. RCP Seal Water Return Line Relief Valve, 1-CH-RV-1382A C. RHR Heat Exchanger Relief, 1-RH-RV-1 721 D. SI Accumulator Relief Valve, 1-SI-RV-1 859
: 37. Unit 1  plant conditions:
* Reactor power = 100%
* Charging flow = 100 gpm increasing
* 1-CC-RI-i 05 (CC Heat Exchanger A/B Outlet Radiation Monitor) alarms HIGH
* CC surge tank level = 64% increasing
* 1-AP-16.00 (EXCESSIVE RCS LEAKAGE) is initiated Based on the above conditions, which ONE of the following describes where the excess volume in the CC system will go and (2) what action is directed first by i-AP-1 6.00 to attempt to isolate the leak?
A. (1) The process vent system (2) Isolate letdown B. (1) The process vent system (2) Isolate thermal barrier on suspected RCP C. (1) The auxiliary building sump (2) Isolate letdown D. (1) The auxiliary building sump (2) Isolate thermal barrier on suspected RCP
 
38.Un1t1ant conditions:                    -__________
* 1C-Bi, RCP lB CC RETURN LO FLOW alarm annunciator lit
* Pressurizer Pressure Master Controller is in AUTO-HOLD
* Pressurizer Level Controller is in AUTO-HOLD
* Both Pressurizer Spray Valve Controllers are in AUTO-LOW Based on the above conditions, which ONE of the following identifies the Vital Bus that has been lost?
A. Vital Bus I B. Vital Bus II C. Vital Bus Ill D. Vital Bus IV
: 39. Initial Unit One Conditions:
* Cold Shutdown
* 1-RH-P-i A is in service to 1-RH-E-1 B
* RCS temperature is 140&deg;F and stable.
* PRZR is solid.
* RCP C is running.
Current Conditions:
* Testing on 1-CC-E-1A has resulted in CC system temperature increasing 15&deg;F Which ONE of the following describes the expected plant response to this increase in CC temperature? Assume no operator actions have occurred.
A. Letdown flow will increase B. RHR flow will increase C. Pressurizer spray flow will increase D. Charging flow will increase
: 40. Unit 1 Initial Conditions:
* Time= 1400.
* Power=100%.
* No equipment out of service.
* Steam Generator A (S/G A) Level channel 1-FW-LT-474 (S/G A Level Transmitter CH 1) unexpectedly fails low.
Current conditions:
* Time = 1430 (same day). All required bistables for 1-FW-LT-474 failure have been placed in the TRIP condition.
Based on the current conditions, which ONE of the following identifies the Reactor Protection System actuation logic coincidence required from the remaining in-service Low Low S/G protection channels and Steam Flow Feed Flow Mismatch Coincidence With Low S/G Level protection channels for S/G A only, to initiate an automatic Reactor Trip at time 1431?
Low Low S/G          Feed Flow    Steam Flow Mismatch With Low S/G Level Reactor Trip                          Reactor Trip A.          1/1                      1/2 level with 1/2 flow mismatch B.          1/2                      1/2 level with 1/2 flow mismatch C.          1/1                      1/2 flow mismatch only D.          1/2                      1/2 flow mismatch only
: 41. Initial Conditions:
* Unit 2 is at 100% power.
        * #2 EDG is out of service.
* Safety Injection actuated on Unit 1 five (5) minutes ago.
* Unit 1 emergency buses remain powered from off-site sources.
Current conditions:
* All power is lost to the Unit 2 H AND J buses.
* Unit One Safety Injection has NOT been reset.
Based on the current conditions, which ONE of the following is correct concerning the #3 EDG, in accordance with 2-ECA-0.0?
A. #3 EDG will automatically energize the Unit 2 J bus.
B. operator action is required to manually close the #3 EDG output breaker for the Unit 2 J bus. No operator actions are required for the #3 EDG bypass switch on Unit 1.
C. #3 EDG will automatically parallel on to the Unit 1 J bus. Operator actions are required to realign the #3 EDG to the Unit 2 J bus.
D. operator action is required to place the #3 EDG bypass switch on Unit 1 in Bypass and then the #3 EDG output breaker for the Unit 2 J bus will automatically close.
: 42. Given the following plant conditions:
* A complete loss of vital bus 1-Ill occurred with the unit at 100% power.
* Repairs will require at least one hour before the bus can be re-energized.
* CC flow to the A RCP could not be restored and the team tripped the unit.
* Five minutes after the trip, RCS average temperature decreased to 538&deg;F in the idle RCS loop.
Based on the given conditions, which ONE of the following automatic actuations will occur (if any)?
HiQh Steam Flow Safety Iniection            Steam Line Isolation A.              NOT Actuated                          Actuated B.                Actuated                            Actuated C.                Actuated                          NOT Actuated D.              NOT Actuated                        NOT Actuated
: 43. Unit 2 was operating at 100% power when a LOCA occurred. Containment pressure has ris    1 to 8.4 psig.
Which ONE of the following accurately describes the current containment air recirculation fan configuration?
A. A, B, and C recirculation fans are in service.
B. A and B recirculation fans are in service. C recirculation fan is secured.
C. C recirculation fan is in service. A and B recirculation fans are secured.
D. A, B, and C recirculation fans are all secured.
: 44. A large break LOCA has occurred on Unit 1. Containment pressure has reached the HI-HI CLS setpoint. The 1A Containment Spray Pump failed to start and cannot be started manually.
RWST level is 40% and lowering.
Which ONE of the following describes the direction provided by 1 -FR-Z.1, Response to Containment High Pressure?
A. Monitor the 2A Outside Recirc Pump for cavitation. Throttle pump discharge valve if cavitation observed.
B. Monitor the 2A Outside Recirc Pump for cavitation. Place in PTL if cavitation observed.
C. Monitor the 1A Inside Recirc Pump for cavitation. Throttle pump discharge valve if cavitation observed.
D. Monitor the 1A Inside Recirc Pump for cavitation. Place in PTL if cavitation observed.
: 45. AFW was automatically actuated from a valid AMSAC signal. SG levels are now all greater than 50% NR.
Which ONE of the following describes the minimum actions that the Operator must take to secure the TDAFW Pump?
A. i)RESETAMSAC.
: 2) Close i-MS-PCV-i 02A and B by taking their switches to CLOSED.
B. i)RESETAMSAC.
: 2) Close i-MS-PCV-iO2A and B by taking their switches to OPEN then CLOSED.
C. i) RESET AMSAC AND place AMSAC BYPASS switch in BYPASS.
: 2) Close i -MS-PCV-i 02A and B by taking their switches to CLOSED.
D. i) RESET AMSAC AND place AMSAC BYPASS switch in BYPASS.
: 2) Close 1 -MS-PCV-i 02A and B by taking their switches to OPEN then CLOSED.
: 46. Unit 1 conditions at 0800:
* Reactor power = 50%
* The operating Main Feedwater Pump discharge valve inadvertently closes
* The operating Main Feedwater Pump Recirc valve fails to open Unit 1 conditions at 0805:
* A SIG NR level = 23% decreasing
* B SIG NR level = 19% decreasing
* C S/G NR level = 15% decreasing Based on the above plant conditions, at 0800  (1) wiN start and at 0805        (2) will be operating.
A. (1) 1-FW-P-2 ONLY (2) 1-FW-P-2 ONLY B. (1) 1-FW-P-2 ONLY (2) 1-FW-P-2, 1-FW-P-.3A AND 1-FW-P-3B C. (1) 1-FW-P-3A AND 1-FW-P-3B ONLY (2) 1-FW-P-3A AND 1-FW-P-3B ONLY D. (1) 1-FW-P-3A AND 1-FW-P-3B ONLY (2) 1-FW-P-.2, 1-FW-P-3A AND 1-FW-P-3B
: 47. Given the following plant conditions:
* Unit 1 tripped from 100% power with all systems functioning in automatic.
* 480 Volt Bus 1 Hi source breaker tripped open.
Based on the above conditions, which ONE of the following AFW pumps will be able to feed the steam generators (if any)?
A. i-FW-P-2 ONLY B. i-FW-P-3A ONLY C. i-FW-P-3B ONLY D. All
: 48. Unit 1 Conditions:
* Unit 1 has been shutdown for 30 days.
* The crew is performing 1 -AP-27.O0, Loss of Decay Heat Removal Capability.
* Attachment 5, Reflux Boiling Heat Removal, of 1-AP-27.00 has been initiated.
Which ONE of the following describes the appropriate control of SG narrow range level lAW Step 5 of Attachment 5 of 1 -AP-27.0O?
Control SG narrow range level in a minimum of      (1) SG(s) by utilizing _(2)__.
A. (1)2 (2) 1-.FW-FCV-1478, 1488, 1498.
B. (1)2 (2) 1-FW-MOV-151A through F.
C. (1)1 (2) 1-FW-FCV-1478, 1488, 1498.
D. (1)1 (2) 1-FW-MOV-151A throughF.
: 49. The Unit is in Refueling Shutdown. Refueling operations are in progress. Annunciator 1 B-E IA LO HDR PRESS/IA COMPR 1 TRBL, alarms. 1-IA-PS-100, Instrument Air Header Pressure, indicates 0 psig.
Which ONE of the following is an expected plant change without operator actions?
A. Charging flow has isolated.
B. RHR cooling is no longer occurring.
C. Fuel Transfer Canal Door seal will be deflating.
Containment Instrument Air Compressor has staed.
 
5O.Un1is at full power. The UPS 1A1 Battery Charger fails.
Which ONE of the following sources will AUTOMATICALLY supply power to the loads on the 1A DC bus?
A. 1A1 regulating line conditioner B. 1A2 battery charger.
C. 1B1 battery charger.
D. lBDCbus.
: 51. Unit 1 Initial Conditions:
* 1 A and 1 B 125 VDC Station Batteries are carrying equal loads at the same state of discharge and all related parameters are identical
* There are no battery chargers supplying power to either Station Battery Unit 1 Current Conditions:
* Discharge rate is increased on 1A 125 VDC Station Battery Which ONE of the following correctly completes the statements listed below?
The total amount of ampere-hours that the 1A 125 VDC Station Battery will be able to supply will be (1) the 1 B 125 VDC Station Baffery.
And The voltage indicated on vertical board 2 for the 1 A 125 VDC Station Battery will be (2  that for the 1 B 125 VDC Station Battery.
A. (1) less than (2) equal to B. (1)lessthan (2) less than C. (1)equalto (2) equal to D. (1)equalto (2) less than
: 52. Un1    Current Conditions:
* Annunciator 1C-F6 (EDG 1 TRBL) is in alarm
* EDG 1 Left Air Bank Pressure is 100 psig.
* EDG 1 Right Air Bank Pressure is 98 psig.
* There is no electrical power available to EDG 1 Air Compressor #1 (South compressor)
* There is no electrical power available to EDG 1 Air Compressor #2 (North compressor)
Based on the current conditions, which ONE of the following correctly completes the statements listed below?
The EDG 1 Air Start System        (1)  capable of providing three start attempts.
And If necessary, EDG 1 Right and Left Air Bank pressures may be increased using the EDG 1 (2) Air Compressor.
A. (1)is (2) #2 B. (1)isNOT (2) #2 C. (1)is (2) #1 D. (1)IsNOT (2)#1
: 53. Current Conditions:
* PROCESS VENT RAD MON TRBL (O-RMA-C5) alarms.
* The Green Operate light on the Remote Display Unit (RDU) for 1-GW-RM-130A (Rad Monitor Process Vent Particulate Detector) is off.
Which ONE of the following correctly completes the statements listed below?
Per the O-RMA-C5 Annunciator Response Procedure, manual operator action is required to (1)
And Following a loss and restoration of power, 1 -GW-RM-1 30A will restart in the (2) mode.
A. (1) place the CTMT Vacuum Pumps in OFF (2) accident B. (1) place the CTMT Vacuum Pumps in OFF (2) normal C. (1) close the CTMT Vacuum Pump Discharge Isolation Valves (1-GW-FCV-160/260)
(2) accident D. (1) close the CTMT Vacuum Pump Discharge Isolation Valves (1-GW-FCV-1601260)
(2) normal
: 54. Unit 1 Initial Conditions:
A Stop Log is installed in the 1A Screenwell.
Unit 1 Current Conditions:
A Stop Log is inadvertently installed in the 1 C Screenwell.
Based on current conditions, which ONE of the following will indicate an increase in temperature?
A. Main Control Room Chillers B. Charging Pump Lubricating Oil C. Bearing Cooling Water cooled components D. Component Cooling Water cooled components
: 55. Unit 1 Initial Conditions:
* 100% Power Current Conditions:
* Unit 1 has experienced a LOCA.
* 1-LM-PT-100A (Containment Pressure)    = 22  psia.
* 1-LM-PT-100B (Containment Pressure)    = 24  psia.
* 1-LM-PT-100C (Containment Pressure)    = 24  psia.
* 1-LM-PT-100D (Containment Pressure)    = 22  psia.
Based on the current conditions, which ONE of the following correctly completes the statements listed below?
1CC-TV-140A (CCW from RCP Thermal Barrier) should be _(1).
And 1-CS-MOV-1O1A (A CS Pump Discharge to Spray Ring) should be _(2)_.
A. (1) open (2) open B. (1)open (2) closed C. (1) closed (2) open D. (1) closed (2) closed
: 56. Which ONE of the following states the normal and alternate sources of CONTROL POWER to the Unit 1 Rod Contro logic cabinets?
A. Normal Directly from the output of the rod drive MG sets Alternate MCC 1 Cl -2 via a step-down transformer B. Normal From the output of the rod drive MG sets via a step-down transformer Alternate MCC 1 Cl -2 via a step-down transformer C. Normal MCC 1C1-2 via a step-down transformer Alternate Directly from the output of the rod drive MG sets D. Normal MCC 101-2 via a step-down transformer Alternate From the output of the rod drive MG sets via a step-down transformer
: 57. Initial conditions:
* Unit 1 is at 100% power.
* All systems are in automatic.
Current conditions:
* The lower control channel for Pressurizer Level Control has failed off-scale low.
Which ONE of the following describes the immediate effect of this malfunction on the CVCS?
A. 1-CH-LCV-1460A closes. There is no change in charging flow.
B. 1-CH-LCV-1460B closes. There is no change in charging flow.
C. 1-CH-LCV-1460A closes. 1-CH-FCV-1 122 throttles open to establish approximately 115 gpm charging flow.
D. 1-CH-LCV-1460B closes. 1-CH-FCV-1 122 throttles open to establish approximately 115 gpm charging flow.
: 58. A LOCA has occurred on Unit 1.
The operators are performing actions of E-1, Loss of Reactor or Secondary Coolant.
The following plant conditions exist:
* Core Exit Thermocouples (CET) are all reading between 750 and 950&deg;F, except for three that are reading 1207&deg;F, 1223&deg;F, and 1205&deg;F.
* No RCPs are running.
* RVLIS is reading 55% full range.
The STA declares a RED PATH on the CORE COOLING and states that FR-C.1, Response to Inadequate Core Cooling, must be implemented.
Based on the above conditions, which ONE of the following describes your response to the STAs declaration and why?
A. Agree with the STA; three CETs indicating above 1200&deg;F warrants the RED PATH.
B. Disagree with the STA; at least five CETs must average greater than 1200&deg;F to warrant a RED PATH.
C. Agree with the STA; with no RCPs running and CETs indicating greater than 700&deg;F warrants the RED PATH.
D. Disagree with the STA; RVLIS level indicates that sufficient subcooling exists for the core conditions.
: 59. Which ONE of the following descrIbes (1) how NAOH solution is added to the Reactor Building during a design based accident, and (2) why?
A. (1) Gravity-fed to the suction of the Outside Recirculation Spray pumps.
(2) To aid in the prevention of hydrogen formation.
B. (1) Gravity-fed to the suction of the Outside Recirculation Spray pumps.
(2) To aid in the removal of radioactive iodine.
C. (1) Gravity-fed to the suction of the Containment Spray pumps.
(2) To aid in the prevention of hydrogen formation.
D. (1) Gravity-fed to the suction of the Containment Spray pumps.
(2) To aid in the removal of radioactive iodine.
: 60. Which ONE of the following describes (1)    How the containment hydrogen recombiner reduces containment H2 concentration AND (2)    The band given in 1-E-1 (Loss of Reactor or Secondary Coolant) of hydrogen concentration that the recombiner is placed in service?
A. (1) Flow is heated to 1150-1400&deg;F causing recombination of H  2 and 02 to occur.
(2) 0.4% to 5.0%
B. (1) Hydrogen is directed over electronic device that dissipates hydrogen via small combustions (2) 0.4% to 5.0%
C. (1) Flow is heated to 1150-1400&deg;F causing recombination of H  2 and 02 to occur.
(2) 0.5% to 4.0%
D. (1) Hydrogen is directed over electronic device that dissipates hydrogen via small combustions (2) 0.5% to 4.0%
: 61. With the unit initially at 100%, the steam dumps are pced in STEAM PRESSURE mode to allow for l&C testing.
Which ONE of the following describes how the STEAM PRESSURE arming signal is cleared following completion of the test?
The operator must A. shift the Steam Header Pressure Controller to manual and decreasing signal demand to zero.
B. take the Steam Dump Mode Selector Switch to the Tavg Mode.
C. take the Steam Dump Control Switch to Off/Reset and return the switch to the ON position.
D. take the Steam Dump Control Switch to the By-pass Interlock position.
: 62. Unit 1 Conditions The plant is at 50% rated thermal power.
* 1-MS-PT-447, the selected pimp channel, fails low.
Assuming no operator action, which ONE of the following represents the correct response of SG water level?
A. SG water level control will be maintained at program level for 50% power.
B. SG water level will increase to 44%.
C. SG water level will increase to 75%, resulting in FW isolation at SG Hi-Hi level.
D. SG water level will decrease to 33%.
: 63. Both units are being fed by the Reserve Station Service Transformers Which ONE of the following pairs of condensate pumps will be automatically tripped by the actuation of a load shed?
A. 2AandlC B. lBand2C C. lAand2C D. 2BandlC
: 64. Unit 1 Current Conditions:
* WGDT 1 B release is in progress.
When 1-GW-FCV-1O1 (PROCESS VENT WGDT EFFLUENT FLOW CONTROL) is throttled closed to terminate the release, steady state Process Vent flow will A. Decrease to zero B. Increase slightly C. Decrease slightly D. Remain the same
: 65. Which ONE of the following correctly completes the statements listed bow?
A    (1)  scintillation detector is used in the Containment Gas Monitor (1 -RM-RI-1 60).
And The units indicated on the Containment Gas Monitor (1 -RM-Rl-1 60) meter are      (2)_.
A. (1) beta (2) cpm B. (1) beta (2) mR/hr C. (1) gamma (2)cpm D. (1) gamma (2) mR/hr
: 66. Current Conditions:
* Unit 1 is in INTERMEDIATE SHUTDOWN.
* 1-CH-MOV-1 381 (RCP Seal Return) is required to be locally shut in preparation for a clearance.
* The local shutting of 1-CH-MOV-1381 is NOT directed by a procedure.
* An emergency does NOT exist.
Which ONE of the following describes the necessary approval for local operation and the impact of manual MOV operation on operability, lAW OP-AA-100, Conduct of Operations?
Local operation of 1 -CH-MOV-1 381 must be authorized by .(1 ) and following manual operation, the valve will be considered  (2).
A. (1) Shift Manager (2) inoperable B. (1) Shift Manager (2) operable C. (1) Manager Nuclear Operations (2) inoperable D. (1) Manager Nuclear Operations (2) operable
: 67. Current Conditions:
* 1-FW-P-2, TURB DRVN AFW PUMP is being run for the monthy PT
* 1-MS-SOV-i 02A, TURB DRVN AFW PUMP is OPEN.
* 1-MS-SOV-102B, TURB DRVN AFW PUMP is CLOSED.
* The service building operator identifies turbine speed is 4630 rpm.
Based on the above conditions, which ONE of the following describes the action to take lAW 1 -OPT-FW-003, Turbine Driven Auxiliary Feedwater Pump 1 -FW-P-2?
A. In the MCR, take i-MS-SOV-lO2Ato CLOSE.
B. In the MCR, verify 1-MS-SO V-i 02A in OPEN/RESET and take 1-MS-SOV-102B to OPEN/RESET. THEN take 1-MS-SOV-102A and 1-MS-SOV-102B to CLOSE.
C. Locally at the pump, trip the pump by cycling i-MS-TV-120, AFW Pump 2 Turb Trip Valve, at least one time and leave it in the LATCH position.
D. Locally at the pump, trip the pump by pushing the Manual Push Trip Lever.
: 68. You are in work control onaraiy day when an operator comes to you and states he has been assigned to 34.5 KV switching and tagging tasks. The operator was checking his PPE and noticed that the test date for a pair of electrical rubber insulating gloves was 9 months old.
In accordance with SA-AA-125 Electrical Safety, which ONE of the following describes (1) if electrical rubber insulating gloves are required to be used when performing 34.5 KV switching and tagging tasks in the rain, and (2) If this pair of gloves needs to be retested before use?
A. (1)yes (2) yes B. (1)yes (2)no C. (1)no (2) yes D. (1)no (2) no
: 69. Unit 1  Current Conditions:
* Tavgisl6OF.
* The reactor is subcritical by 3% delta-k/k.
* Reactor defueling is scheduled to begin in 48 hours.
Based on the current conditions, which one of the following correctly completes the statements listed below in accordance with the Surry Power Station Technical Specifications?
Unit us currently in    (1)    ?
And Following completion of refueling, the reactor must be subcritical by at least (2)  %
delta-k/k in order to be in INTERMEDIATE SHUTDOWN.
A. (1) COLD SHUTDOWN (2) 1 B. (1) COLD SHUTDOWN (2)1.77 C. (1) REFUELING SHUTDOWN (2) 1 D. (1) REFUELING SHUTDOWN (2) 1.77
: 70. Unit 1 Conditions:
* Unit 1 was at 100% power.
* A SGTR occurred, resulting in an automatic SI.
* All systems responded as designed.
* The ruptured steam generator has been isolated.
* RCS cooldown has been completed.
* The operating crew has commenced RCS depressurization.
* The ruptured steam generator level is 100% WR.
* The other two steam generators are at 40% NR and rising.
* Pressurizer level is 20% and rising.
* Subcooling is 100 &deg;F and rising.
Based on the above conditions, which ONE of the following describes the required actions of the operating crew?
The operating crew shall A. immediately stop all high head safety injection pumps.
B. go to 1-ES-0.0, REDIAGNOSIS.
C. continue with the procedure in effect.
D. immediately go to 1-FR-H.3, Response to Steam Generator High Level.
: 71.
* The unit was shutdown and placed on RHR Cooling for a refueling outage. All fuel has been offloaded and the A train of RHR secured for maintenance.
* In the A Loop room, the area around the letdown isolation valves has been surveyed and is reading 175 mr/hr. This is the maximum dose observed in the loop room. The dose rate is 35 mr/hr at the loop room entrance.
* The entrance gate to the loop room is being maintained UNLOCKED.
* An Operator has been assigned the task to hang a tagout in the room, It is expected that this task will take 10 to 15 minutes to complete.
Which ONE of the following describes:
(1) In accordance with 10 CFR 20 requirements, how should HP post the room?
AND (2) In accordance with VPAP-21 01, Radiation Protection Program, can the Operator pertorm the task on the general Operator Clearance RWP, or must a specific RWP be obtained?
A. (1) Radiation Area (2) General RWP is sufficient B. (1) Radiation Area (2) Specific RWP is required C. (1) High Radiation Area (2) General RWP is sufficient D. (1) High Radiation Area (2) Specific RWP is required
: 72. Initial Conditions:
* Unit Two is currently commencing the spring 2011 refueling outage..
Current Conditions:
* The refueling team is preparing to load the first Fuel Assembly into the reactor vessel.
Based on the current conditions, which ONE of the following completes both of the below statements in accordance with 2-OP-FH-001, CONTROLLING PROCEDURE FOR REFUELING?
The MINIMUM allowable reactor cavity boron concentration for Refueling Shutdown is        (1)
AND The LATEST point in time when base neutron count rates for SRNI N-31 and SRNI N-32 is allowed to be obtained is          (2)
A. (1)2250 ppm (2) after the fourth (
th) Fuel Assembly is loaded into the core and before the fifth (
4                                                              th) 5 Fuel Assembly is loaded into the core.
B. (1)2350ppm (2) after the fourth (
th) Fuel Assembly is loaded into the core and before the fifth (Sth) 4 Fuel Assembly is loaded into the core.
C. (1)2250 ppm (2) after the eighth (
th) Fuel Assembly is loaded into the core and before the ninth (gth) 8 Fuel Assembly is loaded into the core.
D. (1)2350 ppm (2) after the eighth (ath) Fuel Assembly is loaded into the core and before the ninth (
th) 9 Fuel Assembly is loaded into the core.
: 73. Initial Conditions:
* Unit 1 experienced an automatic SI coincident with a total loss of offsite power Current Conditions:
* All Power Range Nl=4% and increasing
* All Intermediate Range SUR=+O.1 DPM and stable
* All CETs=71 5 &deg;F and lowering slowly
* RVLIS Full Range=26% and increasing slowly
* RCS Subcooling based on CETssuperheated
* Total AFW Flow=200 GPM and stable
* All SIG NR levels=O% (downscale low)
* RWST Level=1O% and lowering
* Recirculation has been established in accordance with 1-ES-i .3, TRANSFER TO COLD LEG RECIRCULATION
* Containment sump levels are oscillating erratically
* Amps, flows, and discharge pressures on the running ECCS pumps aligned for recirculation are all oscillating erratically
* A transition to Attachment 1, CONTAINMENT SUMP SCREEN BLOCKAGE CONTINGENCY ACTIONS, of i-ES-i .3 has just been announced by the SRO Based on the current conditions, which ONE of the following is a correct evaluation of critical safety function procedural implementation?
A. Implementation of i-FR-S.i, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, takes precedence over implementation of i-FR-H.i, RESPONSE TO LOSS OF SECONDARY HEAT SINK B. Implementation of i-FR-H.i, RESPONSE TO LOSS OF SECONDARY HEAT SINK, takes precedence over implementation of Affachment 1 of 1-ES-i .3 C. Implementation of Attachment 1 of 1-ES-i .3 takes precedence over implementation of i-FR-C.1, RESPONSE TO INADEQUATE CORE COOLING D. Implementation of i-FR-H.i, RESPONSE TO LOSS OF SECONDARY HEAT SINK, takes precedence over implementation of i-FR-C.2, RESPONSE TO DEGRADED CORE COOLING
: 74. Unit 1 Conditions:
*          . The unit has experienced a Steam Generator Tube Rupture.
* 1-E-3 (STEAM GENERATOR TUBE RUPTURE) is in effect.
* An RCS Cooldown using the Steam Dumps has been initiated.
* One Charging Pump is running and flowing to the RCS.
* RCS subcooling is 29&deg;F.
* Based on the conditions listed above, which one of the following correctly completes the statements listed below?
Flow on each Main Steamline should be kept less than 1.0 X 1 6 PPH to prevent      (1)
And RCP trip criteria _(2)_ apply.
A. (1) Main Steamline isolation (2) do B. (1) Main Steamline isolation (2) do NOT C. (1) exceeding the Technicat Specification cooldown rate limit (2)do D. (1) exceeding the Technical Specification cooldown rate limit (2) do NOT
: 75. Which ONE of the following descrthes the lowest position on the Station Emerge 1
Organization chart that may authorize the use of Emergency Exposure Limits?
A. Unit Supervisor B. Station Emergency Manager C. Radiation Protection Supervisor D. Radiological Assessment Director
: 76. Due to RCS pressure and level decreasing excessivel a team entered AP-16.OO, transitioned to 1-E-O, and initiated SI on step 4 of 1-E-O.
The team identified the leakage as a LOCA outside of containment on the Tc LHSI piping and just closed 1-SI-MOV-1890C (LHSI to Tc).
Using the supplied PCS drawing, which ONE of the following states 1) whether the RCS leakage has been isolated, and 2) the appropriate procedure for the team to transition to upon exit from 1 -ECA-1 .2 (LOCA Outside Containment)?
REFERENCE PROVIDED A. (1) RCS leakage IS isolated (2) 1 -ECA-1 .1 (Loss of Emergency Coolant Recirculation)
B. (1) RCS leakage is NOT isolated (2) 1 -ECA-1 .1 (Loss of Emergency Coolant Recirculation)
C. (1) RCS leakage is NOT isolated (2) 1-E-1 (Loss of Reactor or Secondary Coolant)
D. (1) RCS leakage IS isolated (2) 1-El (Loss of Reactor or Secondary Coolant)
: 77. 0800: Unit 1 is at 100% steady-state power. PCS is out of service.
0810: The following annunciator is received:
* 1C-F2 RCP BRG HI TEMP 0812: The plant operator reports RCP 10 Upper Radial Bearing Temperature is 199 degrees F and 10 RCP Lower Radial Bearing Temperature is 192 degrees F.
Based on the above conditions, at 0812 which ONE of the following (1) are the actions required by procedure, AND (2) is the Technical Specification basis for prohibiting power operation with less than 3 RCPs in service?
A. (1) The Reactor must be shutdown and 10 RCP stopped.
(2) The design limit for departure from nucleate boiling ratio (DNBR).
B. (1) Continued operation is allowed, increase monitoring of 10 RCP.
(2) The design limit for fuel peak centerline temperature (POT).
C. (1) Continued operation is allowed, increase monitoring of 10 RCP.
(2) The design limit for departure from nucleate boiling ratio (DNBR).
D. (1) The Reactor must be shutdown and 10 RCP stopped.
(2) The design limit for fuel peak centerline temperature (POT).
: 78. A plant shutdown is in progress. RCS temperature is 358 F and slowly being lowered per GOP-2.4, Unit Cooldown, HSD to 351 F. Both Pressurizer PORVs have failed their setpoint adjustment post maintenance tests and have been declared inoperable. l&C states that it will take 8 hours to repair the instruments and restore the valves to operable.
The cooldown can continue if pressurizer level is maintained less than      (1). The Technical Specification basis for this allowance is that the pressurizer  (2).
A. (1) 33%
(2) steam bubble wili mitigate any pressure transients for at least 5 minutes to allow for operator action B. (1) 33%
(2) level allows approximately 10 minutes for operator action to mitigate any pressure transient events C. (1) 50%
(2) level allows approximately 10 minutes for operator action to mitigate any pressure transient events D. (1) 50%
(2) steam bubble will mitigate any pressure transients for at least 5 minutes to allow for operator action
: 79. At 09:50, a steam line fault in safeguards occurred on Unit 1 with the following plant parameter timeline:
At 10:00
* All SG NR levels at 5%, stable
* All SG pressures 650 psig, lowering uncontrollably
* Containment Pressure 10.8 psia, stable
* Pressurizer level 10%
* Steam Safety Rad Monitors:
* MS-RM-1 24 reading 2 mr/hr, stable
* MS-RM-125 reading 4 mr/hr, stable
* MS-RM-126 reading 2 mr/hr, stable 10:15
* All SG NR levels at 7%, rising slowly
* SG A and SG B pressures 500 psig, lowering uncontrollably
* SG C pressure 700 psig, rising
* Containment Pressure 10.8 psia, stable
* RCS Pressure 1900 psig; cool down rate >100 &deg;FIhr
* Pressurizerlevell5%
* Steam Safety Rad Monitors:
* MS-RM-124 reading 2 mr/hr, stable
* MS-RM-125 reading 4 mr/hr, stable
* MS-RM-126 reading 2 mr/hr, stable
* Both motor driven AFW pumps have tripped on overcurrent AT 10:15, which ONE of the following identifies (1) the required procedure, and (2) whether an emergency classification is REQUIRED in accordance with Emergency Action Level Matrix?
(Exclude SEM judgment classifications)
REFERENCE PROVIDED A. (1) Remain in ECA-2.1 (2) NOUE B. (1) Exit ECA-2.1 and transition to E-2 (2) NOUE C. (1) Remain in ECA-2.1, (2) ALERT D. (1) Exit ECA-2.1 and transition to E-2 (2) ALERT
: 80. Unit 1 Initial Conditions:
* Lowest indicated Tc is 250&deg; F.
* Wide Range RCS Pressure is 320 psig.
* Cooldown is in progress per 1 -GOP-2.5 (UNIT COOLDOWN, 351&deg;F TO LESS THAN 205&deg; F).
* RHR is in service.
* Pressurizer level is decreasing at a rate that cannot be accounted for due to the cooldown.
* Makeup flow is maximized and with pressurizer level still decreasing.
Unit 1 Current Conditions:
* A Station Blackout has occurred.
* Both AC Emergency Buses are DEENERGIZED.
Based on the current conditions, which ONE of the following will correctly complete the statements listed below?
_(1)_ must be initiated to address the loss of both Emergency Buses.
And
_(2)_ must be initiated to mitigate the loss of reactor coolant.
A. (1) 1-AP-1 0.07 (LOSS OF UNIT 1 POWER)
(2) 1AP-16.01 (SHUTDOWN LOCA)
B. (1) 1-AP-1 0.07 (LOSS OF UNIT 1 POWER)
(2) 1-AP-1 6.00 (EXCESSIVE RCS LEAKAGE)
C. (1) 1-ECA-0.0 (LOSS OF ALL AC POWER)
(2) 1-AP-1 6.01 (SHUTDOWN LOCA)
D. (1) 1 -ECA-0.0 (LOSS OF ALL AC POWER)
(2) 1-AP-1 6.00 (EXCESSIVE RCS LEAKAGE)
: 81. Unit 1  conditions at 0900:
* 100% Power
* 230 KV system voltage is 225 Ky.
* The Generator Voltage Regulator is in AUTO.
Unit 1 conditions at 1000:
* 230 KV system voltage is 218 KV
* The crew is attempting to increase voltage lAW 1-OP-26.5, 230 KV Switchyard Voltage, Section 5.1, Corrective Actions to be Taken in the Event 230 KV Voltage is Sagging Below the Scheduled Voltage.
* The crew has entered 0-AP-1 0.18, Response to Grid Instability.
Which ONE of the following states (A) how the crew is attempting to increase voltage lAW 1-OP-26.5 section 5.1, and (B) based on the current conditions, the status of the 230kv distribution system operability (in accordance with 0-AP-10.18 and Tech Specs)?
The Voltage Regulator          (1)    when operating the EXCITATION LEVEL control switch in the RAISE direction. lAW TS 3.16 and 0-AP-10.18, the 230kv distribution system is (2)
A. (1) must be placed in MANUAL (2) INOPERABLE B. (1) must be placed in MANUAL (2) OPERABLE C. (1) mayremain in AUTO (2) INOPERABLE D. (1) may remain in AUTO (2) OPERABLE
: 82. Initial plant condWons:
      -  Reactor Power = 60%
      -  Power increase to 100% is in progress
      -  Control Rod Bank D is at 165 steps Current plant conditions:
      -  Reactor Power = 70%
      -  Control Bank D positions are as follows:
              -  Group position = 175 steps
              -  Rod B8 drops to 0 steps
              -  Rod K10 drops to 155 steps
      -  Annunciator 1 G-H2, RPI ROD BOTTOM < 20 STEPS LIT  -
      -  0-AP-1 .00 ROD CONTROL SYSTEM MALFUNCTION is entered Based on the above plant conditions, Rod Ki 0 is considered        and 0-AP-1 .00 directs the operator to:        2 A. 1)      Operable
: 2)    GO TO 0-AP-1 .01, CONTROL ROD MISALIGNMENT B. 1)      Inoperable
: 2)    Trip the Reactor and GO TO 1-E-0, REACTOR TRIP OR SAFETY INJECTION C. 1)      Inoperable
: 2)    GO TO 0-AP-1 .01, CONTROL ROD MISALIGNMENT D. 1)      Operable
: 2)    Trip the Reactor and GO TO 1-E-0, REACTOR TRIP OR SAFETY INJECTION
: 83. Initital Conditions (2210):
            - Unit 1 is operating at full power
            - In preparations for an upcoming refueling outage, the 1 H stub bus is tagged out
            - A fire is reported in the Emergency switchgear room and the fire brigade is dispatched Current Conditions (2230):
            - The brigade leader reports that there are flames and smoke billowing from the 1J stub bus feeder breaker.
            - The Control Room has completed the applicable portions of AP-48.00, Fire Protection Operations Response.
Which ONE of the following describes:
(1) The procedure the crew should transition to lAW AP-48.00, Attachment 3, Appendix R Safe Shutdown Functions, and (2) The correct Emergency Classification?
Reference Provided A. (1) 1-FS-FP-107, Unit 1 Emergency Switchgear Room Elevation 9 FT, 6 IN (2) Alert B. (1) 1-FCA-4.00, Limiting ESGR Number 1 Fire (2) Unusual Event C. (1) 1-FS-FP-107, Unit 1 Emergency Switchgear Room Elevation 9 FT, 6 IN (2) Unusual Event D. (1) 1-FCA-4.00, Limiting ESGR Number 1 Fire (2) Alert
: 84. Which ONE of the following describes the assumed sources of water used to determine the setpoint for entry into FR-Z.2, Containment Flooding, and when FR-Z.2 is applicable?
A. RCS, RWST, and SI accumulators only: FR-Z.2 is applicable between in Model through Mode 3 only.
B. RCS, RWST, and SI accumulators only: FR-Z.2 is applicable between in Model through Mode 4.
C. RCS, RWST, Chemical Addition Tank, and SI accumulators: FR-Z.2 is applicable between Modes 1 through Mode 3 only.
D. RCS, RWST, Chemical Addition Tank, and SI accumulators: FR-Z.2 is applicable between Model through Mode 4.
: 85. Unit 1 Initial Conditions:
* Unit 1 has experienced a Loss of All AC Power.
* 1-ECA-0.1 (LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED) is complete.
Unit 1 Current Conditions:
* Tave is 547 F.
* 1 D-B5 (ICCM System Failure) is in alarm due to failed power supplies on Channels A &
B.
* All Reactor Coolant Pumps are unavailable due to a prolonged loss of seal cooling.
* The Shift Manager has directed a cooldown to less than 2000 F within 10 hours due to impending weather conditions.
Based on the current conditions, which ONE of the following correctly completes the statements listed below?
(1)    will be used to complete the cooldown.
And (2)    if Pressurizer level increases to 90% during RCS depressurization.
A. (1) 1-ES-0.2 (NATURAL CIRCULATION COOLDOWN)
(2) Increase RCS Pressure by 100 psi using Pressurizer Heaters B. (1) 1-ES-0.2 (NATURAL CIRCULATION 000LDOWN)
(2) Adjust charging and letdown flows to restore Pressurizer level to required band C. (1) 1-ES-0.4 (NATURAL CIRCULATION 000LDOWN WITH STEAM VOID IN RX VESSEL) (W/O RVLIS)
(2) Increase RCS Pressure by 100 psi using Pressurizer Heaters D. (1) 1-ES-0.4 (NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN RX VESSEL) (W/O RVLIS)
(2) Adjust charging and letdown flows to restore Pressurizer level to required band
: 86. Initial Conditions
* 1-GOP-2.5, Unit Cooldown 351&deg;F to Less Than 205&deg;F is complete.
* All safety systems are aligned lAW 1 -OSP-ZZ-004, Unit 1 Safety Systems Status List for Cold Shutdown/Refueling Conditions.
* 1-CH-PCV-1145, LTDN LINE PRESS CNTRL is in AUTO and set to 300 psig.
* 1-RC-Pl-1458, RCS PRESS NAR RANGE, indicates 305 psig.
* 1-RC-LI-1462, PRZR LEVEL START UP indicates 83%.
* Charging flow has been adjusted to increase PRZR level to SOLID lAW step 5.2.19.e.3 of 1-GOP-2.6.
Current Conditions
* The PRZR is solid.
* 1-RC-PCV-1456 and 1-RC-PCV-1455C, PRZR PORVs, have cycled.
* Annunicator 1 D-B6, PRZR NDTT HI PRESS is alarming.
Which ONE of the following describes the required actions?
Per ARP 1 D-B6, the most effective method to lower RCS pressure is by        (1)    . In accordance with Technical Specification 6.6.C, Special Reports, this event 2) required to be reported to the NRC.
A. (1) lowering charging flow (2) is B. (1) lowering charging flow (2) is not C. (1) securing PRZR heaters while maintaining spray flow (2) is D. (1) securing PRZR heaters while maintaining spray flow (2) is not
: 87. kiWal Conditions
* Unit 1 is operating at 100% power.
Current Conditions:
* Rx Trip due to load rejection.
* 1-E-0 is in progress.
* AC Emergency Bus H has no power.
* SI has initiated.
* RCS temperature trending to 547&deg; F.
* PRZR PORV 1-RCPCV-1455C stuck open.
* PRZR PORV Block valve 1 -RC-MOV-1 536 will not close.
* 1-CH-P-1B Charging pump red lights lit, green light off.
* 1 -CH-P-1 B Charging pump indicating 5 amps on the control panel.
* RCS subcooling 17&deg;F decreasing.
Based on the current conditions, which ONE of the following describes (1) the procedure that FIRST gives guidance for RCP operation and (2) what direction it gives?
A. (1) 1-E-1 (2) Stop all RCPs B. (1) 1-E-0 (2) Stop all RCPs C. (1) 1-E-1 (2) Do NOT stop RCPs D. (1) 1-E-0 (2) Do NOT stop RCPs
: 88. A reactor startup sin progress. Power is currently at 9% and holding for turbine issues. An Intermediate Range Instrument fails low.
Which ONE of the following is acceptable by Technical Specification 3.7 (Instrumentation Systems)?
A. Reduce power to below P-6 within 48 hours.
B. Raise power to greater than 11% within 24 hours.
C. Power operation may continue without restriction.
D. Current power can be maintained indefinitely. Return the instrument to OPERABLE status prior to raising power.
: 89. Current Conditions:
* Unit 1 is operating at 100% power.
* 1 -CC-RM-1 05 radiation levels have remained stable over the last 3 hours.
* 1 -CC-RM-1 06 radiation levels have shown a lowering trend over the last 3 hours.
* An instrumentation technician reports that the cause of the lowering trend on 1 -CC-RM-1 06 is calibration drift in the detector.
* HCV-CC-100, CC Surge Tank Vent Valve is OPEN.
Based on the current conditions, which ONE of the following describes (A) the effect of the calibration drift on the CC system (if any), and (B) the requirements of Technical Specification (TS) 3.13, Component Cooling System?
HCV-CC-100, CC Surge Tank Vent Valve, 1) have the ability to close automatically and      (2)____
A. (1) does (2) may remain OPEN.
B. (1) does (2) must be SHUT.
C. (1)does not (2) may remain OPEN.
D. (1)doesnot (2) must be SHUT.
: 90. Initial Condition:
            -  Both Units at 100% power
            -  While moving equipment in the turbine building in preparation for an upcoming refueling outage, a forklift strikes an instrument air pipe and separates the line in two.
Current Conditions:
            - Feed flow is decreasing to all Unit One Steam Generators
            - Current S/G Narrow Range levels are:
                      - A S/G 19%
                      - B S/G 22%
                      - C S/G 20%
            - 1F-C7 (STM GEN 1A CH 3 FW < STM FLOW) is LIT
            - 1 F-D7 (STM GEN 1A CH 4 FW <STM FLOW) is LIT
            - 1 F-C8 (STM GEN 1 B CH 3 FW <STM FLOW) is LIT
            - 1 F-D8 (STM GEN 1 B CH 4 FW <STM FLOW) is LIT
            - 1F-C9 (STM GEN 1C CH 3 FW <STM FLOW) is LIT
            - 1F-D9 (STM GEN 1C CH 4 FW <STM FLOW) is LIT
            - Demand on all main feedwater regulating valves is 72% and increasing Which ONE of the following states 1) the appropriate team response to these indications, and
: 2) the first procedure to be initiated by the SRO?
A. 1)      Direct the BOP operator to manually increase demand on the feed reg valves.
: 2)    0-AP-40.00 B. 1)      Direct the reactor operator to perform immediate actions of 1 -E-0.
: 2)    1-E-O C. 1)      Direct the operator to perform the immediate actions of 1-FR-S.1
: 2)    1-FR-S.1 D. 1)      Direct the BOP operator to start the r  3d condensate pump and reduce turbine load using the limiter.
: 2)  1-AP-21.00
: 91. WhkDh ONE of the followig completes the statement regarding the Manulator Crane Lifting Hoist Overload Interlock?
The OVERLOAD interlock          (1)      be bypassed, and the reason for this interlock, in accordance with the basis for Technical Specification 3.10 (REFUELING), is      (2)
A. (1)can (2) to prevent movement of a disengaged fuel assembly that is hung up on the gripper B. (1) can NOT (2) to prevent movement of a disengaged fuel assembly that is hung up on the gripper C. (1)can (2) to prevent movement of more than one fuel assembly at a time D. (1)canNOT (2) to prevent movement of more than one fuel assembly at a time
: 92. Unit One Reactor Startup is in progress and a bance shot has just been completed on the main turbine. The team is preparing to assign admin control of the main steam trip valve bypass valves in accordance with 1 -OP-TM-001, attachment 2 (Adminstrative Control Requirements for Main Steam Trip Valve Bypass Valves).
The briefing for the admin control states: The valve shall be immediately closed upon notification from the Control Room of a SI initiation.
Which ONE of the following states 1) the specific time requirement to satisfy immediate in accordance with SUADM-O-26 (Administrative Control of Operational Components), and 2) whether the operator assigned admin controls can perfrom the pre-start checks of 1 -FW-P-2 (to support upcoming start-up activities) while assigned admin control?
A. 1) 60 seconds
: 2) Yes B. 1)40 seconds
: 2) Yes C. 1) 60 seconds
: 2) No D. 1) 40 seconds
: 2) No
 
r 93. Current Conditions
* Unit 2 is stable at the POAH with physics testing in progress.
* PR Channel N-44 is still in trip because the reactivity recorder is installed.
* The National Hurricane Center just issued a Hurricane Warning for Surry County.
* Unit Two has just been directed to shut down due to hurricane force winds expected onsite within the next 12 hours.
* Unit One is currently shutdown and maintaining 300&deg;F in the RCS.
* A fault occurs in the 2B1 UPS that causes the loss of Vital Bus II and llA.
* The reactor is tripped as required by 2-AP-10.02, Loss of Vital Bus II.
Which ONE of the following describes:
(1) How many SR indications are available on Unit 2 after tripping the unit?
AND (2) What RCS temperature should be maintained?
A. (1)0 (2) 200&deg;F to 345&deg;F per 0-AP-37.01, Abnormal Environmental Conditions.
B. (1)1 (2) 200&deg;F to 345&deg;F per 0-AP-37.01, Abnormal Environmental Conditions C. (1)0 (2) > 530&deg; F per 1 -AP-4.0, Nuclear Instrumentation Malfunction.
D. (1)1 (2) > 530&deg;F per 1-AP-4.0, Nuclear Instrumentation Malfunction.
: 94. Initial Conditions:
* At time 0930, unexpected grid fluctuations caused an automatic turbine trip from 100%
power.
* Chemistry personnel drew a post-trip RCS sample at time 1005.
* Control room operators have stabilized the unit at 547 &deg;F and normal operating pressure.
Current conditions:
* At time 1045, chemistry reports the following:
* E-bar is 10 Mev/disintegration.
* Dose Equivalent 1-131 is 0.5 microcuries/cc.
* RCS specific activity 15 microcuries/cc.
Based on the current conditions, which ONE of the following describes (1) the appropriate actions in accordance with Technical Specification (TS) 3.1 .D, Maximum Reactor Coolant Activity, and (2) the reporting requirements lAW TS 6.6.A.2, if any?
LCO 3.1.D for Dose Equivalent 1-131        (1)  met, and the current chemistry results
: 2)          reportable to the Commission pursuant to TS 6.6.A.2.
REFERENCE PROVIDED A. (1)is (2) are B. (1)is (2) are NOT C. (1)isNOT (2) are D. (1)isNOT (2) are NOT
: 95. Which ONE of the following correctly completes the statements listed below?
Per SY-AA-1O1 (Security Access and Control),    (1)  escort(s) is\are required for escorting ten personnel into the Control Room area.
And Per OP-AA-100 (Conduct of Operations), the    (2)  shall give prior approval for Control Room tours.
A. (1)one (2) Unit Supervisor B. (1)one (2) Shift Manager C. (1)two (2) Unit Supervisor D. (1)two (2) Shift Manager
 
E 9 6 A temporary level indkator is to be installed for the VCT using the Temporary Modif ication process detailed in CM-AA-TDC-204, Temporary Modifications.
Which ONE of the following describes the Temporary Modification process lAW CM-AA-TDC-204?
The Manager Radiological Protection (or alternate)      (1)    required to be a member of the Facility Safety Review Committee (FSRC) for this modification, and the MINIMUM level of Station Management approval required for Extension of Temporary Modification Duration, assuming no unresolved conditions, is the        (2)
A. (1)is (2) FSRC B. (1)is (2) Site Vice President C. (1) is not (2) FSRC D. (1)isnot (2) Site Vice President
: 97. The 1A RHR Pump surveHlance has just been completed. The following data has been recorded on the Data Sheet from Attachment 4 of 1-OPT-RH-003, RHR System Operability Test:
Note: Recorded data is in the shaded region.
Record                  ReFerence      Satisfactory              Alert      Unsatisfactory Adjusted                    = 375  psid 81 4 to 90.1 psid 73.3 to  81,4 psid LP    78.8 pd P      892 psid                                                              or From Substep                                                                      >  90.1 pd 6 .513c Vh  =0i052      in/sec \Th = 0 0837    1<  0 2092 insec 0 2092  Vh =      Vim>  0.5022    n sac in.sec                            05fl22  in.c I, =  0 0972  in/sec    = U 323          1 2u35 in ec fl2Li35                Ii  4.E3 ii  sec nsec                            01956 n.c Va      0i288    in/sec Vs = 0 0502    Va< 0.1255 insec  01255 Va            Va> 0 3 012 insec insec                            0.3012 n.sec Which ONE of the following completes the statement:
The 1A RHR pump is __(1)_; __(2)__ required.
A. (1) operable (2) no further action is B. (1) operable (2) a Condition Report is C. (1) inoperable (2) an immediate retest is D. (1) inoperable (2) a Condition Report is
: 98. Initial conditions:
    - Unit One experiencing a LOCA with fuel failure Present conditions:
      -  1-RM-Rl-157, Main Control Room Radiation Monitor, alarms. It currently reads 2.6 mr/hr and is rising.
      -  Main control room supply and exhaust has been isolated, and 1 -VS-F-41, Emergency Supply Fan has been started.
      -  The following data is noted:
* PDI-VS-100, D.P.-U1CR/U1TB -0.2 water
* PDI-VS-101, D.P.-U1RR/U1TB +O.1water
* PDI-VS-200, D.P.-U2CR/U2TB -0.1 water
* PDI-VS-201, D.P.-U2RR/U2TB &#xf7;0.1 water
* All pressure indications are degrading Based on the above conditions, which ONE of the following describes (1) what action(s) is (are) required by 1 -E-0 (Reactor Trip or Safety Injection), and (2) what the status of the Control Room Envelope is, per TS 3.21?
A. (1) Secure MCR Boundary Fans.
(2) Operable B. (1) Secure MCR Boundary Fans.
(2) Inoperable C. (1) Start an additional emergency supply fan.
(2) Operable D. (1) Start an additional emergency supply fan.
(2) Inoperable
: 99. Initial Conditions:
* Unit 1 is experiencing a sustained Loss of All AC Power condition.
* The TDAFW pump shaft sheared on startup, and all efforts to cross-connect AFW with Unit 2 have failed.
Current Conditions:
* All emergency buses remain de-energized.
* Operators have just completed the step in ECA-0.0 to Check DC Bus Loads, and have placed both the DC emergency oil pump and the Air Side seal oil backup pump in PTL.
* Core Exit Thermocouples (CETC5) are 1202 F and rising.
* STA reports the following Critical Safety Function Status Trees:
* Core Cooling: RED
* Heat Sink: RED
* Containment: ORANGE
* Inventory: YELLOW
* Subcriticality: GREEN
* Integrity: GREEN Based on the current conditions, which ONE of the following describes the appropriate procedure to be used NEXT to mitigate the casualty?
A. Transition to 1 -SACRG-1, SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL RESPONSE.
B. Continue in 1-ECA-0.0, LOSS OF ALL AC POWER.
C. Transition to 1-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.
D. Transition to 1-FR-C.1, RESPONSE TO INADEQUATE CORE COOLING.
 
1 00. Unit 1 Initial Conditions:
* 100% power Current conditions:
* A maintenance worker inadvertently tripped the Unit 1 Main Turbine while working at the turbine front end.
* The Reactor Protective System automatically initiated a Reactor Trip.
Based on the current conditions, which ONE of the following correctly describes (1) whether the Reactor Trip should be considered a VALID or INVALID actuation, as defined by VPAP-2802, Notifications and Reports, AND (2) the shortest time requirement to report this event to the NRC, as specified by VPAP-2802?
REFERENCE PROVIDED A. (1) VALID actuation (2) 4 hour notification B. (1) INVALID actuation (2) 8 hour notification C. (1) VALID actuation (2) 8 hour notification D. (1) INVALID actuation (2) 4 hour notification
 
ANSWER KEY REPORT for Surry RO-SRO Combined 2012 Test Form: 0 Answers W      ID                                      Points  Type    0 1      007 EK2.02 1                              1.00  MCS      B 2    008 AKI.01 1                                1.00  MCS      C 3    011 EAI.09 1                                1.00  MCS      C 4      022 AA2.02 1                                1.00  MCS      D 5    025 G2.4.31 1                              1.00  MCS      B 6      026 AA2.01 1                                1.00  MCS      A 7      027 AK2.03 1                                1.00  MCS      D 8      029 EA 1.03 1                              1.00  MCS    C 9      038 EK3.01 1                                1.00  MCS    B 10    040 WEI2 EK2.1 1                            1.00  MCS    D 11    055 EKI.02 1                                1.00  MCS    B 12    057 AK3.01 1                                1.00  MCS    C 13    058 AAI.01 1                                1.00  MCS    A 14    062 AA2.01 1                              1.00  MCS    ID 15    065 G2.1.31 1                              1.00  MCS    B 16    WIEO4 G2.4.45 1                            1.00  MCS    B 17    W/E11 EK1.2 1                              1.00  MCS    B 18    WIEO5 EK3.2 1                              1.00  MCS    ID 19    003 AK3.07 1                              1.00  MCS    C 20    024 AK2.03 1                              1.00  MCS    A 21    028 AK2.02 1                              1.00  MCS    ID 22    033 AKI.01 1                              1.00  MCS    A 23    069 WE14 EK3.4 1                          1.00  MCS    B 24    W/E13 EAI.1 1                              1.00  MCS    C 25    032 AA2.02 1                                1.00  MCS    B 26    W/E03 G2.1.20 1                            1.00  MCS    D 27    WIEO8 EA2.2 1                              1.00  MCS    D 28    003 K6.02 1                                1.00  MCS    C 29    003 A3.03 1                                1.00  MCS    B 30    004 A2.13 1                                1.00  MCS    D 31    004 G2.4.2 1                                1.00  MCS    A 32    005 K5.02 1                                1.00  MCS    C 33    005 G2.2.42 1                              1.00  MCS    C 34    006A4.101                                  1.00  MCS    ID 35    007 K4.01 1                                1.00  MCS  A 36    007 A3.01 1                                1.00  MCS  A 37    008 A2.04 1                                1.00  MCS  C 38    010 K2.02 1                                1.00  MCS  B 39    010 A1.04 1                                1.00  MCS  A 40    012 K6.03 1                                1.00  MCS  ID 41    013K1.121                                  1.00  MCS  D 42    013 K5.02 1                                1.00  MCS  B 43    022 K4.05 1                                1.00  MCS  C 44    026 K3.02 1                                1.00  MCS  B 45    039 A4.04 1                                1.00  MCS  B 46    059 K1.02 1                                1.00  MCS  C Tuesday, September 25, 2012 7:49:33 AM
 
ANSWER KEY REPORT for Surry RO-SRO Combined 2012 Test Form: 0 Answers
  #      ID                                      Points  Type  0 47    061 K2.01 1                                1.00  MCS    D 48    061 K5.02 1                                1.00  MCS    D 49    078 K3.02 1                                1.00  MCS    B 50    063 K4.02 1                                1.00  MCS    B 51    063 A1.01 1                                1.00  MCS    B 52    064 K6.07 1                                1.00  MCS    B 53    073 A2.01 1                                1.00  MCS    A 54    076 A1.02 1                                1.00  MCS    C 55      103 A3.01 1                                1.00  MCS    B 56    001 K2.03 1                                1.00  MCS    B 57    011 K3.01 1                                1.00  MCS  B 58    017 K6.01 1                                1.00  MCS    B 59    027 K1.01 1                                1.00  MCS  D 60    028 02.1.28 1                              1.00  MCS  C 61    041 A4.02 1                                1.00  MCS  B 62    035 A3.01 1                                1.00  MCS  D 63    056 A2.04 1                                1.00  MCS  C 64    071 A1.06 1                                1.00  MCS  D 65    072 KS .01 1                              1.00  MCS    A 66    02.1.1 1                                  1.00  MCS  C    z.ss 67    02.1.8 1                                  1.00  MCS    D 68    02.1.26 1                                  1.00  MCS    A 69    02.2.35 1                                  1.00  MCS    B 70    02.2.44 1                                  1.00  MCS    C 71    02.3.71                                    1.00  MCS    e  D      i/L//_
72    02.3.12 1                                  1.00  MCS    D 73    02.4.5 1                                  1.00  MCS    C 74      02.4.20 1                                  1.00  MCS  B 75      02.4.37 1                                  1.00  MCS  B 76    00902.1.191                                1.00  MCS  D 77    015 AA2.08 1                                1.00  MCS  A 78    027 02.1.23 1                              1.00  MCS  B 79    O4OWEI2EA2.22                              1.00  MCS  D 80    055 02.4.9 1                                1.00  MCS  C 81    077 AA2.05 2                              1.00  MCS  C 82    005.AA2.03 1                              1.00  MCS  B 83    067 02.4.11 1                              1.00  MCS  D 84    W/E1S G2.4.18 1                            1.00  MCS  D 85    WIEIO EA2.1 1                              1.00  MCS  C 86    004 A2.01 1                                1.00  MCS  A 87    006 A2.05 1                                1.00  MCS  D 88    012 02.2.38 1                              1.00  MCS  B 89    073 A2.03 1                                1.00  MCS  B 90    078 02.1.7 2                              1.00  MCS  B 91    034 K4.03 1                                1.00  MCS  C 92    045 02.1.23 1                              1.00  MCS  D Tuesday, September 25, 2012 7:49:33 AM 2
 
ANSWER KEY REPORT for Surry RO-SRO Combined 2012 Test Form: 0 Answers
#      ID                                      Points Type 0 93    015 A2.04 1                                1.00 MCS  A 94    02.1.34 1                                  1.00 MCS  A 95    G2.1.13 1                                  1.00 MCS  D 96    02.2.11 1                                  1.00 MCS  A 97    02.2.12 1                                  1.00 MCS  B 98    G2.3.13 1                                  1.00 MCS  B 99    G2.4.16 1                                  1.00 MCS  A 100    02.4.30 1                                  1.00 MCS  A SECTION 1 (100 ftems)                          100.00 Tuesday, September 25, 2012 7:49:33 AM 3
 
NRC Exam Reference Materials Table of Contents Page 1&#xe1;
 
RO Exam References Page Reference 4    1-AP-9.OO  Attachment 4 (Determining No. 3 Seal Cavity Pressure (P3) Using RCP Seal Leakoff) 5    1-AP-27.OO  Attachment 2 (Minimum RCS Level Versus RHR Flow (1-RC-Ll-100A)
Page 2
 
SRO Exam References Page  Reference 4      1-AP-9.OO  Attachment 4 (Determining No. 3 Seal Cavi ty Pressure (P3) Using RCP Seal Leakoff) 5    1-AP-27.OO    Attachment 2 (Minimum RCS Level Vers us RHR Flow (1-RC-Ll-100A) 6    PCS Drawing    Unit 1 Low Head Safety Injection 7    Surry Power Station EAL Matrix    Revision 2 8,9  Technical Specifications 3.1.D (Pages 3.1-1 5a & 3.1-15b) 10    VPAP- 2802    Notifications and Reports Page 3}}

Latest revision as of 12:03, 6 February 2020

Initial Exam 2012-301 Final SRO Written Exam
ML12269A248
Person / Time
Site: Surry  Dominion icon.png
Issue date: 09/25/2012
From:
NRC/RGN-II
To:
References
50-280/12-301, 50-281/12-301
Download: ML12269A248 (107)
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Text

ES-401, Rev. 9 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: August 28, 2012 Facility/Unit: Surry Nuclear Power Plant Region: I/jj/lIl/IV ReactorType:W/CE/BW/GE Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicants Signature Results RO/SRO-Only/Total_Examination Values Applicants Scores / / Points Applicants Grade / / Percent

1. Initial conditions:
  • Unit 1 is at 90% power.
  • Reactor protection testing is in progress on Train A.

Current Conditions:

  • No other breaker manipulations have been performed.

Which ONE of the following describes the immediate response to the reactor trip breaker B and the reactor trip bypass breakers if the Reactor Trip Bypass Breaker B is closed?

A. Reactor Trip Bypass Breakers A and B will trip open.

Reactor Trip Breaker B will trip open.

B. Reactor Trip Bypass Breakers A and B will trip open.

Reactor Trip Breaker B will remain closed.

C. Reactor Trip Bypass Breaker B will trip open. Reactor Trip Bypass Breaker A will remain closed.

Reactor Trip Breaker B will remain closed.

D. Reactor Trip Bypass Breakers A and B will remain closed.

Reactor Trip Breaker B will remain closed.

2. Initial Conditions * -__________________
  • Unit 1 is at 100% and 2250 psig.
  • The PRT is at 3 psig.

Current Conditions

  • The PRT is 10 psig and increasing.
  • Reactor Pressure is 2210 psig and decreasing.
  • There is a report that the local safety valve acoustic monitor indicates a valve partially open.

Which ONE of the following describes the appropriate actions lAW ARP 1 D-H4?

The leaking valve is confirmed by the associated downstream temperature reading approximately (1) ,and the crew is required to (2).

A. (1) the saturation pressure of the Pressurizer (2) initiate 1 -E-0, Reactor Trip or Safety Injection B. (1) the saturation pressure of the Pressurizer (2) close the associated PORV block valve C. (1) the saturation pressure of the PRT (2) initiate 1 -E-0, Reactor Trip or Safety Injection D. (1) the saturation pressure of the PRT (2) close the associated PORV block valve

3. The following conditions exist:
  • Unit 1 has tripped from 100% power due to a Large Break Loss of Coolant Accident (LBLOCA).
  • The operating crew has transitioned to 1 -E-1, LOSS OF REACTOR OR SECONDARY COOLANT, step 22, Check if SI accumulators should be isolated.
  • RCS hot leg temperatures are:
  • Loop A Th = 394 F.
  • Loop B Th = 393 F.
  • Loop C Th = 396 F.
  • Power is available to all Accumulator discharge isolation valves.
  • Both trains of SI have been reset.

Which ONE of the following completes the statement:

1 -E-1 directs isolation of (1) , and the MOVs for the accumulators to be isolated can be closed with the ACC Interlock in (2)

A. (1) A, B and C Accumulators (2) NORMAL B. (1) A and B Accumulators, but not C Accumulator (2) NORMAL C. (1) A, B and C Accumulators (2) DEFEAT D. (1) A and B Accumulators, but not C Accumulator (2) DEFEAT

4. Initial conditions:
  • Unit 1 is at 100% power.
  • Pressurizer (PRZR) is at program level.
  • Charging Pump A is running.
  • Charging Pumps B and C normal breakers are racked in, and their switches in the Control Room are in AUTO.

Current conditions:

  • Charging flow and discharge pressure are erratic.
  • Charging pump amps are erratic on all three running pumps.
  • Seal injection is oscillating between 4 and 5 gpm.
  • PRZR level is at 19% and lowering. Charging flow has not been restored.
  • 1-AP-8.00, Loss of Normal Charging Flow has been entered.
  • Letdown flow and pressure indications are oscillating.

Which ONE of the following describes the correct sequence of actions lAW 1 -AP-8.00 to secure charging and letdown, and restore pressurizer make-up?

A. Trip Unit 1 ONLY. THEN isolate letdown and place all Unit One charging pumps in PTL. Dispatch personnel to vent and restart a charging pump.

B. Trip BOTH Units. THEN isolate letdown and place all Unit One charging pumps in PTL.

Dispatch personnel to establish charging cross-tie from Unit Two.

C. Isolate letdown and place all Unit One charging pumps in PTL. THEN Trip Unit 1 ONLY.

Dispatch personnel to vent and restart a charging pump.

D. Isolate letdown and place all Unit One charging pumps in PTL. THEN Trip BOTH Units.

Dispatch personnel to establish charging cross-tie from Unit Two.

5. Initial Conditions:

- Unit 1 has been shutdown for 35 days

- The RHR System aligned for normal operation.

- RCS level is at mid-loop 12.4 feet and stable as read on 1-RC-Ll-100A.

- The A RHR pump is running.

- 1 -RH-FC-1 605C (RHR HXS BYP FLOW) controller fails to 100% full open demand in AUTO Current Conditions:

- RHR flow is oscillating from 1500 to 3000 gpm.

- A RHR pump amps are oscillating

- RHR HX LO FLOW annunciator, 1B-G6 alarming Based on the above conditions, which ONE of the following identifies the correct action to mitigate the event as directed by 1-AP-27.00 (LOSS OF DECAY HEAT REMOVAL CAPABILITY)?

A. Raise RCS level by opening 1-SI-MO V-i 869A (Th HHSI Isolation MOV).

B. Reduce RHR flow by placing 1-RH-FC-1605C in MAN and lowering demand.

C. Stop the A RHR pump.

D. Start the B RHR pump.

6. Unit 1 Initial Conditions:
  • 75% Power at Middle-of-Life (MOL) conditions.
  • Excess Letdown is in service in preparation for removing Normal Letdown from service.

Current conditions:

  • Component Cooling (CC) surge tank level is slowly DECREASING at 1% every 5 minutes.
  • VCT level is slowly increasing.
  • No operator actions have been taken.

Which ONE of the following completes the statement below?

The above conditions are consistent with a tube leak in the (1) , which will cause reactor power to (2)

A. (1) RCP Seal Return Heat Exchanger (2) increase B. (1) RCP Seal Return Heat Exchanger (2) decrease C. (1) Excess Letdown Heat Exchanger (2) increase D. (1) Excess Letdown Heat Exchanger (2) decrease

7. Unit 1 plant conditions:
  • Rx heatup is in progress
  • RCS pressure is 1900 psig Which ONE of the following is the response of the pressurizer PORVs if pressurizer pressure transmitter 1-RC-PT-1444 fails high?

A. Only 1-RC-PCV-1455C will open.

B. Only 1-RC-PCV-1 456 wiN open.

C. Both 1-RC-PCV-1 4550 and 1-RC-PCV.-1456 will open.

D. Neither 1-RC-PCV-1 4550 nor 1-RC-PCV-1456 will open.

8. Unit 1 has experienced an Anticipated Transient Without Trip (ATWT).
  • Operators have transitioned out of 1 -E-0 to 1 -FR-S.1
  • SI has NOT been initiated.
  • Charging Flow is 80 gpm.
  • The BATP has been placed in FAST
  • 1-CH-MOV-1 350 (Emergency Borate Valve) will not open from the Control Room.

Based on the above conditions, which ONE of the following choices identifies the required procedure actions for getting boron into the reactor per 1-FR-S.1?

A. Start a second Charging pump and fully open 1 -CH-FCV-1 122 (Charging Flow Control Valve).

B. Locally open 1-CH-MOV-1350, after 21 minutes close 1-CH-MOV-1350.

C. Open 1-CH-MOV-1115B and D (CHG pump suction from RWST) and Close 1 -CH-MOV-1 11 SC and E (CHG PUMP SUCTION FROM VCT).

D. Manually open 1-CH-FCV-1113A (BORON TO BLENDER FLOW CONTROL), then dispatch an operator to establish Manual Emergency Boration by opening 1 -CH-228 (MANUAL EMERGENCY BORATE STOP)

9. The following plant conditions exist:
  • Tube Rupture on A SG.
  • The operating team has cooled the RCS to 485 °F and completed the RCS depressurization.
  • The ruptured SG pressure is 935 psig.
  • Pressurizer level is 65%.
  • Ruptured SG level is 45% NR and decreasing.

The operating team is currently performing step 35, Control RCS Pressure and CHG Flow to Minimize RCS to Secondary Leakage.

Which ONE of the following (1) describes the actions required by E-3, and (2) the basis for this action?

A. (1) Turn ON pressurizer heaters to raise RCS pressure.

(2) This will minimize RCS volume loss.

B. (1) Turn ON pressurizer heaters to raise RCS pressure.

(2) This will lead to a reduction in pressurizer level.

C. (1) Use main or auxiliary spray to lower RCS pressure.

(2) This will minimize RCS volume loss.

D. (1) Use main or auxiliary spray to lower RCS pressure.

(2) This will lead to a reduction in pressurizer level.

flO. Reactor power was noted to be 101% and rapidly rising. The crewtripped the reactor and entered E-0, Reactor Trip or Safety Injection.

There is a report of a significant break on the supply to the TDAFW. All personnel have been evacuated from the area due to the unsafe conditions.

The crew has transitioned to ECA-2.1, Uncontrolled Depressurization of All Steam Generators.

Given the following:

  • All Narrow Range Cold leg Temperature indications have lowered 18 °F in the last 5 minutes.
  • All Steam Dumps are closed.

Which ONE of the following describes the required actions lAW ECA-2.1?

A. Lower feeding each steam generator to 25 gpm.

B. Stop feeding all Steam Generators.

C. Stop feeding only the A and C Steam Generators.

D. Continue feeding all Steam generators at the current flow rates.

11. The AAC Diesel Generator is removed from service for scheduled maintenance. A sustained loss of offsite power has led to a reactor and turbine trip. The #1 and #3 EDG fail to start.

Five (5) minutes after the trip, the following conditions exist:

  • RCS Pressure is 2107 psia and slowly lowering.
  • Highest CETC is 575 °F and slowly rising.

TC is 509 °F and slowly lowering.

  • Delta T is 64 °F and slowly rising.
  • SG pressure is 720 psig and stable.

Which ONE of the following describes the status of RCS heat removal?

A. Reflux Cooling has developed.

B. A pending loss of natural circulation is indicated.

C. Single phase natural circulation is fully developed.

D. Natural circulation is developing.

12. A loss of Vital Bus ll has just occurred.

Which ONE of the following describes the reason that AP-1 0.03, Loss of Vital Bus lii, requires the operators to trip the reactor?

Losing the vital bus causes a loss of A. CC to the RCP thermal barriers.

B. Pressurizer pressure control.

C. CC to the A RCP lube oil cooler.

D. Main and bypass Feed Regulating Valve Control.

13. With the unit initially at 100% power, a fault developed in the 1A battery bank (failed cell) that resulted in a loss of the 1A DC bus. Electricans have verified that the DC distribution system is unaffected.

Which ONE of the following states the recovery method for the 1A DC bus in accordance with 1-AP-1 0.06 (Loss of DC power)?

A. Direct electricians to lift battery leads, open all breakers in the DC distribution panels, and align at least one battery charger to the DC bus.

B. Direct electricians to lift battery leads and align at least one battery charger to the DC bus.

C. Direct electricians to lift battery leads and close the A DC bus crosstie breaker.

D. Direct electricians to lift battery leads, open all breakers in the DC distribution panels, and close the A DC bus crosstie breaker.

r 14. Unit 1 initial conditions:

  • 100% power.
  • A Charging Pump is in service.
  • The following alarms received in the Main Control Room:
  • 1 D-G5, SW or CC Pps Disch to Chg Pps Lo Press
  • 0-VSP-M4, Flood Cont Pnl Trbl
  • Flood Panel light LS-.DA-1 1 5A-1, Unit #1 ESGR is illuminated.

Which ONE of the following completes the statement below?

The above conditions are consistent with a rupture of the supply piping from the Charging Pump (1) system. If left uncorrected, A Charging Pump (2) could be damaged.

A. (1) Component Cooling (2) seals

8. (1) Component Cooling (2) bearings C. (1) Service Water (2) seals D. (1) Service Water (2) bearings
15. Unit 1 initial conditions:
  • Containment pressure reached a maximum of 18.3 psia Current conditions:
  • Containment pressure has stabilized at 16.5 psia.

Which ONE of the following completes the description of control room indications on the Containment Instrument Air system?

1-IA-PT-i 06, Containment Instrument Air pressure, indicates (1), and 1 -lA-TV-i 01 A/B, Normal Compressor Suction Valves, are 2).

A. (1) pressurized (2) OPEN B. (1) pressurized (2) CLOSED C. (1) depressurized (2) OPEN D. (1) depressurized (2) CLOSED

16. A transient is in progress and the following alarms have been received:
  • 1 B-F3, SFGDS AREA SUMP HI LEVEL is in ALARM.
  • 1 F-A9, (B9), STM GEN C LO LVL CHN 1 (CHN 2)
  • 1 H-B8, AFW Pump 3A LOCKOUT OR OL TRIP is in ALARM.
  • 1-RM-D4, 1-RM-RI-154 (AUX BLDG CONT) HIGH is in ALARM.

Which ONE of the foIIowng casualties is in progress?

A. Steam Generator Tube Rupture B. LOCA Outside Containment C. LOCA Inside Containment D. LossofSecondaryHeatSink

17.Whkth one of the following correcy comçetes the statements listed below in accordance with the requirements of 1 -ECA-1 .1 (LOSS OF EMERGENCY COOLANT RECIRCULATION)?

The RMT MODE TRANSFER SWITCH will be placed in the (1) mode.

And If containment sump blockage exists when 1-ECA-1 .1 is entered, A. 1) REFUEL

2) FR procedures apply throughout the procedure B. 1) REFUEL
2) FR procedures are suspended until directed C. 1)RMT
2) FR procedures apply throughout the procedure D. 1)RMT
2) FR procedures are suspended until directed
18. Unit 1 Initial Conditions:
  • Unit 1 has experienced a LOCA from 100% power.

Unit 1 Current Conditions:

  • PRZR pressure is 2200 psig.
  • CETC temperatures are increasing.
  • Containment Pressure is 21 psia.
  • RCS Hot Leg temperatures are 552 degrees F and increasing.
  • The Unit Supervisor has directed entry into 1-FR-.H.1 (RESPONSE TO LOSS OF SECONDARY HEAT SINK).

Based on Current Conditions, which ONE of the following correctly completes the statements listed below in accordance with 1-FR-H.1 (RESPONSE TO LOSS OF SECONDARY HEAT SINK)?

When the ability to supply feedwater is restored, feed flow should initially be A. limited to 60 gpm per SG B. limited to 100 gpm per SG C. minimum of 350 gpm total D. established to ONE SG at the maximum available rate

1 9. Unit 1 Current Conditions:

  • The Rod Control System is in Manual.
  • Tave is 532 degrees F and decreasing.

Based on the Current Conditions, which one of the following correctly completes the statements listed below?

The earliest a Reactor trip will be required is if Tave decreases below jJ degrees F.

And That Reactor trip will be required by (2)

A. (1)522 (2) the Technical Specification Minimum Temperature for Criticality B. (1)530 (2) the Technical Specification Minimum Temperature for Criticality C. (1)530 (2) 0-AP-1 .00 (ROD CONTROL SYSTEM MALFUNCTION)

D. (1)522 (2) 0-AP-1 .00 (ROD CONTROL SYSTEM MALFUNCTION)

20. Which ONE of the following correctly completes the statements listed below?

When performing an emergency boration per 1-AP-3.00 (EMERGENCY BORATION), the in-service BATP (1) automatically be shifted to FAST.

1 -CH-MOV-1 350 (emergency borate valve) can be electrically operated at the jj A. (1) will NOT (2) Main Control room and Aux Shutdown Panel B. (1)will NOT (2) Main Control Room Only C. (1) will (2) Main Control Room and Aux Shutdown Panel D. (1) will (2) Main Control Room Only

21. Initial conditions:
  • Unit 1 is at 100% steady state power
  • All systems are in Automatic
  • The Pressurizer Level Control Selector Switch is in position I/Ill.

Current conditions:

  • The bellows inside the differential pressure cell for pressurizer level transmitter 1-RC-LT-1461 (Channel III Pressurizer Level) completely ruptures.
  • No operator action occurs.

Which ONE of the following describes the immediate initial response of the pressurizer level control system?

A. Charging flow decreases.

Annunciator 1C-C8, PRZR HI LVL HTRS ON alarms.

B. Charging flow increases.

Annunciators 1C-E8, PRZR LO LVL HTRS OFF & LETDOWN ISOL and 1C-D8, PRZR LO LVL alarm.

C. Charging flow remains constant.

Annunciator 1C-E8, PRZR LO LVL HTRS OFF & LETDOWN ISOL alarms.

D. Charging flow remains constant.

Annunciator 1 E-H3, RX TRIP CH 3 PRZR HI LVL alarms.

22. Initial Conditions

Conditions 25 minutes jost-trir

  • N-35 indicates 4x10

° amps, SUR of 0 DPM.

1

  • N-36 indicates lxi Q-11 amps, SUR of 0 DPM.

Which ONE of the following describes the current conditions?

A. N-35 is undercompensated.

N-31 and N-32 must be manually energized.

B. N-35 is undercompensated.

N-31 and N-32 energized automatically.

C. N-35 is overcompensated.

N-31 and N-32 must be manually energized.

D. N-35 is overcompensated.

N-31 and N-32 energized automatically.

23. Unit 1 Initial Conditions:
  • LOCA inside containment.
  • 1-E-1 Loss Of Reactor Or Secondary Coolanf in progress
  • Both Train A and Train B of cold leg recirculation are NOT available.

Current Conditions:

  • Unit Supervisor directs transition to 1 -ECA-1 .1, Loss of Emergency Coolant Recirculation
  • A RED path exists for Containment

Which ONE of the following correctly states which procedure should be used for operation of the Containment Spray Pumps, AND whether or not CS Pumps are required to be placed in Pull to Lock (PTL) based on the Current Conditions?

CS Pumps operation is directed by (1) , AND CS Pumps (2) required to be placed in PTL in accordance to the selected procedure.

A. (1)ECA-1.1 (2) are B. (1)ECA-1.1 (2) are NOT C. (1) FR-Z.1 (2) are D. (1)FR-Z.1 (2) are NOT

24. Given the following plant conditions:
  • A S/G Pressure is 1250 psig.
  • A SIG Narrow range level is 82%
  • RCS hot leg temperatures are 574 degrees F.
  • The condenser is not available.
  • The A S/G PORV is stuck closed.
  • Turbine Driven AFW pump is out of service for bearing replacement.

Which ONE of the following describes the preferred method to reduce A S/G pressure in accordance with 1-FR-H.2?

A. Feed A S/G with AFW and commence an RCS cooldown to less than 540 degrees F.

B. Feed A S/G with AFW and establish Blowdown from the A steam generator.

C. Isolate AFW to the A S/G and commence RCS cooldown to less than 540 degrees F.

D. Isolate AFW to the A S/G and establish Blowdown from the A Steam Generator.

25. the Unit is in HotShutdown with the following conditions:
  • Tavg is 547 °F.
  • Pressurizer pressure is 2235 psig.
  • RCS boron is at the CSD value of 1120 ppm.
  • Initial Source Range counts are 45 cps.
  • Shutdown 7 days ago The shutdown banks are withdrawn in accordance with procedure GOP-i .4 Unit Startup, HSD To 2% Reactor Power.

When the shutdown banks are fully withdrawn, the following Source Range data is recorded:

N-31 counts are 82 cps N-32 counts are 202 cps Based on the above indications, which ONE of the following BEST describes the Source Range data that was collected and required actions (if any)?

A. N31 is indicating an abnormally low count rate, initiate 1-AP-4.00 (NI Malfunction).

B. N32 is indicating an abnormally high count rate, initiate 1-AP-4.00 (NI Malfunction).

C. Source range response is as expected, no abnormalities exist.

D. Current RCS boron is not as expected, initiate 1-AP-3.00 (Emergency Boration).

26. Initial Conditions:
  • LOCA occurred on Unit 1.
  • SI has been RESET.
  • Operators are implementing 1-ES-i .2, POST LOCA COOLDOWN AND DEPRESSURIZATION.
  • 90 F/hr cooldown is in progress.
  • RCP C is the ONLY running RCP.

Current Conditions:

  • Operators are at the step in i-ES-i .2 to CHECK SI FLOW NOT REQUIRED.
  • RCS subcooling requirement is NOT met.
  • One charging pump is in service.

Based on the current conditions, which ONE of the following is the NEXT action required by i-ES-i .2 to regain subcooling?

A. Energize all available pressurizer heaters and maintain current RCS pressure.

B. Increase the cooldown rate to <100 °F/hr and ensure PRZR level can be maintained >22%.

C. Reinitiate SI by operation of the SI pushbuttons and verify HHSI flow path to RCS cold legs.

D. Manually start CHG pumps and align HHSI flow path to RCS cold legs.

27. Unit 1 Conditions
  • Step 5, Initiate Attachment 1, System Alignment Verification, is in progress.

Which ONE of the following statements describes the basis for checking FW isolation in 1-E-O, Attachment 1, System Alignment Verification?

A. To minimize feed flow to reduce the likelihood of thermal shock to SG components.

B. To preclude any excessive FW addition to intact SGs that would cause negative MTC to add positive reactivity insertion and return to criticality.

C. To ensure that excessive FW flow does not cause an overpressure condition of the SGs.

D. To prevent excessive RCS cooldown that could aggravate the initiating transient, especially if it were a steam line break.

28. The seal leakoff valve is inadvertently isolated for 1-RC-P-1B(1-CH-HCV-1303B).

Which ONE of the following states the seal package response?

A. The #1 seal assumes full RCS delta-P.

B. The #2 seal assumes full RCS delta-P.

C. The #3 seal assumes full RCS delta-P.

D. The #2 and #3 seals share the RCS delta-P.

29. Which one of the following provides indications of #2 seal failure on 1 B RCP (1 -RC-P-1 B)?

REFERENCE PROVIDED A. P1 (1-RC-PI-1402) = 1200 psig, P2 (1-CH-P!-1155) = 800 psig, Seal Leakoff = 1.75 gpm B. P1 (1-RC-Pl-1402) = 2200 psig, P2 (1-CH-Pl-1155) = 1100 psig, Seal Leakoff = 3.00 gpm C. P1 (1-RC-PI-1402) = 2200 psig, P2 (1-CH-PI-1155) = 1100 psig, Seal Leakoff = 0.00 gpm D. P1 (1-RC-PI-1402) = 1200 psig, P2 (1-CH-PI-1155) = 1200 psig, Seal Leakoff = 2.20 gpm

30. Unit 1 Initial Conditions at 0100:
  • A Large Break LOCA has occurred from 100% power.
  • 1-E-1 (LOSS OF REACTOR OR SECONDARY COOLANT) is in progress.

Unit 1 Current Conditions at 0500:

Which ONE of the following correctly completes the statements listed below?

High Head Safety Injection Pump suctions should automatically shift from the RWST to the discharge of the Low Head Safety Injection Pumps at an RWST level of _(1)

And Transfer to 2) leg recirculation is required at this time.

A. (1)20%

(2) cold B. (1)20%

(2) hot C. (1) 13.5%

(2) hot D. (1) 13.5%

(2) cold

31. Initial Conditions (0910):
  • Unit 1 is at 90%.
  • Charging Pump A is RUNNING in AUTO on its NORMAL bus.
  • Charging Pump B is OFF in AUTO on its NORMAL bus.
  • Charging Pump C is OFF in AUTO on its NORMAL bus.
  • 1-CC-FT-i 40A, Flow Transmitter for 1-CC-TV-i 40A (RCP Thermal Barrier CC Outlet Flow Outside Trip Valve) has failed high.

Current Conditions (0912):

  • Charging Pump B is locked out.
  • 41 60v bus 1 H is deenergized.
  • 4160v bus 1J is energized.
  • Unit 1 remains at 90% power.
  • No operator actions have occurred.

Which ONE of the following describes the operational implications of the current conditions and the correct action to take?

RCP Seal cooling (1) been lost.

An IMMEDIATE Reactor Trip (2) required.

A. (1)has (2) is B. (1)has (2) is NOT C. (1) has NOT (2) is D. (1) has NOT (2) is NOT

32. The following Unit 1 conditions exist:
  • The RHR system has just been made available.
  • Inadequate time to completely vent the RHR system exists prior to boiling in the core.

Which ONE of the following correctly states guidance in 1-AP-27.00 with respect to sweeping air from the RHR lines?

If adequate time to completely vent the RHR system is not available, air can be swept out of the RHR lines by filling the RCS to a MINIMUM of (1)____ feet on 1-RC-LI-100A (RCS Standpipe), checking a minimum subcooling of 1OF, and running an RHR pump at a flow rate of 2) gpm.

REFERENCE PROVIDED (1) (2)

A. 12.4 >2950gpm B. 12.4 <2600 gpm C. 13.5 >2950gpm D. 13.5 <2600 gpm

33. Current Conditions
  • Unit 1 is in REFUELING OPERATIONS.
  • 1-RH-P-lA is in service to 1-RH-E-1A.
  • Core alterations are in progress.

Which ONE of the following 1) requires entry into a LCO condition, and 2) whether fuel movement can continue?

A. 1) 1 -RH-E-1 B is isolated and drained for tube leak testing

2) Fuel movement MAY continue B. 1) 1 -RH-E-1 B is isolated and drained for tube leak testing
2) Fuel movement may NOTcontinue C. 1) 1 -RH-P-i A trips on ground overcurrent
2) Fuel movement may NOT continue D. 1)1-RH-P-lA trips on ground overcurrent
2) Fuel movement MAY continue
34. Unit 1 Conditions:
  • A Medium-Break LOCA has occurred.
  • The crew is performing the actions of 1 -E-1, Loss of Reactor or Secondary Coolant.
  • All RCPs are running.
  • 5 minutes ago, Charging Pump A was placed in PTL lAW Step 1 9.b of 1 -E-1 (ESTABLISH CHG PUMP REDUNDANT FLOW PATHS). No valve manipulations have occurred.
  • The following information was displayed on the SPDS at the times indicated:

Parameter 10 minutes ago 5 minutes ago Current CONTAINMENT CONDITIONS PAGE CONTAINMENT PRESSU REIR 19.6 19.5 19.4 PSIA 5

RCS INTEGRITY PAGE HIGH HEAD SAFETY INJECTION FLOW 176.2 119.2 120.7 GPM LOOP A HIGH HEAD SAFETY INJECTION FLOW 176.5 119.2 121.1 GPM 100 P B HIGH HEAD SAFETY INJECTION FLOW 176.3 119.1 120.9 GPM LOOP C RCS PRESSURE 1900 1887 1875 PSIG PRESSURIZER LEVEL 22.9 21.5 19.1 PCT CORE HEAT REMOVAL PAGE PEAK CORE EXITTEMPERATURE 595.5 595.7 594.9 DEGF Which ONE of the following describes appropriate actions lAW 1 -E-1?

A. SI is required to be reinitiated by starting A Charging Pump.

B. SI is required to be reinitiated by placing A Charging Pump in AUTO and depressing the SI pushbuttons.

C. SI is not required to be reinitiated. Establish charging pump redundant flow paths with B Charging Pump supplying the normal SI HDR and C Charging Pump supplying the alternate SI HDR.

D. Slis not required to be reinitiated. Establish charging pump redundant flow paths with C Charging Pump supplying the normal SI HDR and B Charging Pump supplying the alternate SI HDR.

35. Current Conditions
  • The OATC confirms the alarm is valid, and notes that PRT level, pressure, and temperature have been slowly increasing since assuming the watch.
  • The OATC is directed to lower tank temperature lAW 1 -OP-RC-01 1.

Which ONE of the following describes how temperature will be lowered lAW 1 -OP-RC-01 1, Pressurizer Relief Tank Operations?

The PRT is filled by opening 1-RC-TV-1519A and 1-RC-TV-1519B to discharge Primary Grade Water (1) the water level in the PRT, and the PRT is subsequently drained to maintain the PRT in the normal level band of (2).

A. (1) above (2)6080%

B. (1) above (2) 59 83 %

C. (1) below (2) 60 80 %

D. (1) below (2) 59 83 %

36. Unit 1 is operating in Mode lat 100% power.
  • A review of parameters shows the following:

Time 1300 1400 PRT Level 73% 84%

PRTTemperature 108F 185F PRT Pressure 3 psig 4 psig Which ONE of the following relief valves has failed (leaking by)?

A. Regenerative Heat Exchanger Letdown Line Relief Valve, 1-CH-RV-1 203 B. RCP Seal Water Return Line Relief Valve, 1-CH-RV-1382A C. RHR Heat Exchanger Relief, 1-RH-RV-1 721 D. SI Accumulator Relief Valve, 1-SI-RV-1 859

37. Unit 1 plant conditions:
  • Reactor power = 100%
  • Charging flow = 100 gpm increasing
  • 1-CC-RI-i 05 (CC Heat Exchanger A/B Outlet Radiation Monitor) alarms HIGH
  • CC surge tank level = 64% increasing
  • 1-AP-16.00 (EXCESSIVE RCS LEAKAGE) is initiated Based on the above conditions, which ONE of the following describes where the excess volume in the CC system will go and (2) what action is directed first by i-AP-1 6.00 to attempt to isolate the leak?

A. (1) The process vent system (2) Isolate letdown B. (1) The process vent system (2) Isolate thermal barrier on suspected RCP C. (1) The auxiliary building sump (2) Isolate letdown D. (1) The auxiliary building sump (2) Isolate thermal barrier on suspected RCP

38.Un1t1ant conditions: -__________

  • Pressurizer Pressure Master Controller is in AUTO-HOLD
  • Pressurizer Level Controller is in AUTO-HOLD
  • Both Pressurizer Spray Valve Controllers are in AUTO-LOW Based on the above conditions, which ONE of the following identifies the Vital Bus that has been lost?

A. Vital Bus I B. Vital Bus II C. Vital Bus Ill D. Vital Bus IV

39. Initial Unit One Conditions:
  • Cold Shutdown
  • 1-RH-P-i A is in service to 1-RH-E-1 B
  • RCS temperature is 140°F and stable.
  • PRZR is solid.
  • RCP C is running.

Current Conditions:

  • Testing on 1-CC-E-1A has resulted in CC system temperature increasing 15°F Which ONE of the following describes the expected plant response to this increase in CC temperature? Assume no operator actions have occurred.

A. Letdown flow will increase B. RHR flow will increase C. Pressurizer spray flow will increase D. Charging flow will increase

40. Unit 1 Initial Conditions:
  • Time= 1400.
  • Power=100%.
  • No equipment out of service.
  • Steam Generator A (S/G A) Level channel 1-FW-LT-474 (S/G A Level Transmitter CH 1) unexpectedly fails low.

Current conditions:

  • Time = 1430 (same day). All required bistables for 1-FW-LT-474 failure have been placed in the TRIP condition.

Based on the current conditions, which ONE of the following identifies the Reactor Protection System actuation logic coincidence required from the remaining in-service Low Low S/G protection channels and Steam Flow Feed Flow Mismatch Coincidence With Low S/G Level protection channels for S/G A only, to initiate an automatic Reactor Trip at time 1431?

Low Low S/G Feed Flow Steam Flow Mismatch With Low S/G Level Reactor Trip Reactor Trip A. 1/1 1/2 level with 1/2 flow mismatch B. 1/2 1/2 level with 1/2 flow mismatch C. 1/1 1/2 flow mismatch only D. 1/2 1/2 flow mismatch only

41. Initial Conditions:
  • Unit 2 is at 100% power.
  • #2 EDG is out of service.
  • Safety Injection actuated on Unit 1 five (5) minutes ago.
  • Unit 1 emergency buses remain powered from off-site sources.

Current conditions:

  • All power is lost to the Unit 2 H AND J buses.
  • Unit One Safety Injection has NOT been reset.

Based on the current conditions, which ONE of the following is correct concerning the #3 EDG, in accordance with 2-ECA-0.0?

A. #3 EDG will automatically energize the Unit 2 J bus.

B. operator action is required to manually close the #3 EDG output breaker for the Unit 2 J bus. No operator actions are required for the #3 EDG bypass switch on Unit 1.

C. #3 EDG will automatically parallel on to the Unit 1 J bus. Operator actions are required to realign the #3 EDG to the Unit 2 J bus.

D. operator action is required to place the #3 EDG bypass switch on Unit 1 in Bypass and then the #3 EDG output breaker for the Unit 2 J bus will automatically close.

42. Given the following plant conditions:
  • A complete loss of vital bus 1-Ill occurred with the unit at 100% power.
  • Repairs will require at least one hour before the bus can be re-energized.
  • CC flow to the A RCP could not be restored and the team tripped the unit.
  • Five minutes after the trip, RCS average temperature decreased to 538°F in the idle RCS loop.

Based on the given conditions, which ONE of the following automatic actuations will occur (if any)?

HiQh Steam Flow Safety Iniection Steam Line Isolation A. NOT Actuated Actuated B. Actuated Actuated C. Actuated NOT Actuated D. NOT Actuated NOT Actuated

43. Unit 2 was operating at 100% power when a LOCA occurred. Containment pressure has ris 1 to 8.4 psig.

Which ONE of the following accurately describes the current containment air recirculation fan configuration?

A. A, B, and C recirculation fans are in service.

B. A and B recirculation fans are in service. C recirculation fan is secured.

C. C recirculation fan is in service. A and B recirculation fans are secured.

D. A, B, and C recirculation fans are all secured.

44. A large break LOCA has occurred on Unit 1. Containment pressure has reached the HI-HI CLS setpoint. The 1A Containment Spray Pump failed to start and cannot be started manually.

RWST level is 40% and lowering.

Which ONE of the following describes the direction provided by 1 -FR-Z.1, Response to Containment High Pressure?

A. Monitor the 2A Outside Recirc Pump for cavitation. Throttle pump discharge valve if cavitation observed.

B. Monitor the 2A Outside Recirc Pump for cavitation. Place in PTL if cavitation observed.

C. Monitor the 1A Inside Recirc Pump for cavitation. Throttle pump discharge valve if cavitation observed.

D. Monitor the 1A Inside Recirc Pump for cavitation. Place in PTL if cavitation observed.

45. AFW was automatically actuated from a valid AMSAC signal. SG levels are now all greater than 50% NR.

Which ONE of the following describes the minimum actions that the Operator must take to secure the TDAFW Pump?

A. i)RESETAMSAC.

2) Close i-MS-PCV-i 02A and B by taking their switches to CLOSED.

B. i)RESETAMSAC.

2) Close i-MS-PCV-iO2A and B by taking their switches to OPEN then CLOSED.

C. i) RESET AMSAC AND place AMSAC BYPASS switch in BYPASS.

2) Close i -MS-PCV-i 02A and B by taking their switches to CLOSED.

D. i) RESET AMSAC AND place AMSAC BYPASS switch in BYPASS.

2) Close 1 -MS-PCV-i 02A and B by taking their switches to OPEN then CLOSED.
46. Unit 1 conditions at 0800:
  • Reactor power = 50%
  • The operating Main Feedwater Pump discharge valve inadvertently closes
  • The operating Main Feedwater Pump Recirc valve fails to open Unit 1 conditions at 0805:
  • A SIG NR level = 23% decreasing
  • B SIG NR level = 19% decreasing
  • C S/G NR level = 15% decreasing Based on the above plant conditions, at 0800 (1) wiN start and at 0805 (2) will be operating.

A. (1) 1-FW-P-2 ONLY (2) 1-FW-P-2 ONLY B. (1) 1-FW-P-2 ONLY (2) 1-FW-P-2, 1-FW-P-.3A AND 1-FW-P-3B C. (1) 1-FW-P-3A AND 1-FW-P-3B ONLY (2) 1-FW-P-3A AND 1-FW-P-3B ONLY D. (1) 1-FW-P-3A AND 1-FW-P-3B ONLY (2) 1-FW-P-.2, 1-FW-P-3A AND 1-FW-P-3B

47. Given the following plant conditions:
  • Unit 1 tripped from 100% power with all systems functioning in automatic.
  • 480 Volt Bus 1 Hi source breaker tripped open.

Based on the above conditions, which ONE of the following AFW pumps will be able to feed the steam generators (if any)?

A. i-FW-P-2 ONLY B. i-FW-P-3A ONLY C. i-FW-P-3B ONLY D. All

48. Unit 1 Conditions:
  • Unit 1 has been shutdown for 30 days.
  • Attachment 5, Reflux Boiling Heat Removal, of 1-AP-27.00 has been initiated.

Which ONE of the following describes the appropriate control of SG narrow range level lAW Step 5 of Attachment 5 of 1 -AP-27.0O?

Control SG narrow range level in a minimum of (1) SG(s) by utilizing _(2)__.

A. (1)2 (2) 1-.FW-FCV-1478, 1488, 1498.

B. (1)2 (2) 1-FW-MOV-151A through F.

C. (1)1 (2) 1-FW-FCV-1478, 1488, 1498.

D. (1)1 (2) 1-FW-MOV-151A throughF.

49. The Unit is in Refueling Shutdown. Refueling operations are in progress. Annunciator 1 B-E IA LO HDR PRESS/IA COMPR 1 TRBL, alarms. 1-IA-PS-100, Instrument Air Header Pressure, indicates 0 psig.

Which ONE of the following is an expected plant change without operator actions?

A. Charging flow has isolated.

B. RHR cooling is no longer occurring.

C. Fuel Transfer Canal Door seal will be deflating.

Containment Instrument Air Compressor has staed.

5O.Un1is at full power. The UPS 1A1 Battery Charger fails.

Which ONE of the following sources will AUTOMATICALLY supply power to the loads on the 1A DC bus?

A. 1A1 regulating line conditioner B. 1A2 battery charger.

C. 1B1 battery charger.

D. lBDCbus.

51. Unit 1 Initial Conditions:
  • 1 A and 1 B 125 VDC Station Batteries are carrying equal loads at the same state of discharge and all related parameters are identical
  • There are no battery chargers supplying power to either Station Battery Unit 1 Current Conditions:
  • Discharge rate is increased on 1A 125 VDC Station Battery Which ONE of the following correctly completes the statements listed below?

The total amount of ampere-hours that the 1A 125 VDC Station Battery will be able to supply will be (1) the 1 B 125 VDC Station Baffery.

And The voltage indicated on vertical board 2 for the 1 A 125 VDC Station Battery will be (2 that for the 1 B 125 VDC Station Battery.

A. (1) less than (2) equal to B. (1)lessthan (2) less than C. (1)equalto (2) equal to D. (1)equalto (2) less than

52. Un1 Current Conditions:
  • EDG 1 Left Air Bank Pressure is 100 psig.
  • EDG 1 Right Air Bank Pressure is 98 psig.
  • There is no electrical power available to EDG 1 Air Compressor #1 (South compressor)
  • There is no electrical power available to EDG 1 Air Compressor #2 (North compressor)

Based on the current conditions, which ONE of the following correctly completes the statements listed below?

The EDG 1 Air Start System (1) capable of providing three start attempts.

And If necessary, EDG 1 Right and Left Air Bank pressures may be increased using the EDG 1 (2) Air Compressor.

A. (1)is (2) #2 B. (1)isNOT (2) #2 C. (1)is (2) #1 D. (1)IsNOT (2)#1

53. Current Conditions:
  • PROCESS VENT RAD MON TRBL (O-RMA-C5) alarms.
  • The Green Operate light on the Remote Display Unit (RDU) for 1-GW-RM-130A (Rad Monitor Process Vent Particulate Detector) is off.

Which ONE of the following correctly completes the statements listed below?

Per the O-RMA-C5 Annunciator Response Procedure, manual operator action is required to (1)

And Following a loss and restoration of power, 1 -GW-RM-1 30A will restart in the (2) mode.

A. (1) place the CTMT Vacuum Pumps in OFF (2) accident B. (1) place the CTMT Vacuum Pumps in OFF (2) normal C. (1) close the CTMT Vacuum Pump Discharge Isolation Valves (1-GW-FCV-160/260)

(2) accident D. (1) close the CTMT Vacuum Pump Discharge Isolation Valves (1-GW-FCV-1601260)

(2) normal

54. Unit 1 Initial Conditions:

A Stop Log is installed in the 1A Screenwell.

Unit 1 Current Conditions:

A Stop Log is inadvertently installed in the 1 C Screenwell.

Based on current conditions, which ONE of the following will indicate an increase in temperature?

A. Main Control Room Chillers B. Charging Pump Lubricating Oil C. Bearing Cooling Water cooled components D. Component Cooling Water cooled components

55. Unit 1 Initial Conditions:
  • 100% Power Current Conditions:
  • Unit 1 has experienced a LOCA.
  • 1-LM-PT-100A (Containment Pressure) = 22 psia.
  • 1-LM-PT-100B (Containment Pressure) = 24 psia.
  • 1-LM-PT-100C (Containment Pressure) = 24 psia.
  • 1-LM-PT-100D (Containment Pressure) = 22 psia.

Based on the current conditions, which ONE of the following correctly completes the statements listed below?

1CC-TV-140A (CCW from RCP Thermal Barrier) should be _(1).

And 1-CS-MOV-1O1A (A CS Pump Discharge to Spray Ring) should be _(2)_.

A. (1) open (2) open B. (1)open (2) closed C. (1) closed (2) open D. (1) closed (2) closed

56. Which ONE of the following states the normal and alternate sources of CONTROL POWER to the Unit 1 Rod Contro logic cabinets?

A. Normal Directly from the output of the rod drive MG sets Alternate MCC 1 Cl -2 via a step-down transformer B. Normal From the output of the rod drive MG sets via a step-down transformer Alternate MCC 1 Cl -2 via a step-down transformer C. Normal MCC 1C1-2 via a step-down transformer Alternate Directly from the output of the rod drive MG sets D. Normal MCC 101-2 via a step-down transformer Alternate From the output of the rod drive MG sets via a step-down transformer

57. Initial conditions:
  • Unit 1 is at 100% power.
  • All systems are in automatic.

Current conditions:

  • The lower control channel for Pressurizer Level Control has failed off-scale low.

Which ONE of the following describes the immediate effect of this malfunction on the CVCS?

A. 1-CH-LCV-1460A closes. There is no change in charging flow.

B. 1-CH-LCV-1460B closes. There is no change in charging flow.

C. 1-CH-LCV-1460A closes. 1-CH-FCV-1 122 throttles open to establish approximately 115 gpm charging flow.

D. 1-CH-LCV-1460B closes. 1-CH-FCV-1 122 throttles open to establish approximately 115 gpm charging flow.

58. A LOCA has occurred on Unit 1.

The operators are performing actions of E-1, Loss of Reactor or Secondary Coolant.

The following plant conditions exist:

  • Core Exit Thermocouples (CET) are all reading between 750 and 950°F, except for three that are reading 1207°F, 1223°F, and 1205°F.
  • No RCPs are running.
  • RVLIS is reading 55% full range.

The STA declares a RED PATH on the CORE COOLING and states that FR-C.1, Response to Inadequate Core Cooling, must be implemented.

Based on the above conditions, which ONE of the following describes your response to the STAs declaration and why?

A. Agree with the STA; three CETs indicating above 1200°F warrants the RED PATH.

B. Disagree with the STA; at least five CETs must average greater than 1200°F to warrant a RED PATH.

C. Agree with the STA; with no RCPs running and CETs indicating greater than 700°F warrants the RED PATH.

D. Disagree with the STA; RVLIS level indicates that sufficient subcooling exists for the core conditions.

59. Which ONE of the following descrIbes (1) how NAOH solution is added to the Reactor Building during a design based accident, and (2) why?

A. (1) Gravity-fed to the suction of the Outside Recirculation Spray pumps.

(2) To aid in the prevention of hydrogen formation.

B. (1) Gravity-fed to the suction of the Outside Recirculation Spray pumps.

(2) To aid in the removal of radioactive iodine.

C. (1) Gravity-fed to the suction of the Containment Spray pumps.

(2) To aid in the prevention of hydrogen formation.

D. (1) Gravity-fed to the suction of the Containment Spray pumps.

(2) To aid in the removal of radioactive iodine.

60. Which ONE of the following describes (1) How the containment hydrogen recombiner reduces containment H2 concentration AND (2) The band given in 1-E-1 (Loss of Reactor or Secondary Coolant) of hydrogen concentration that the recombiner is placed in service?

A. (1) Flow is heated to 1150-1400°F causing recombination of H 2 and 02 to occur.

(2) 0.4% to 5.0%

B. (1) Hydrogen is directed over electronic device that dissipates hydrogen via small combustions (2) 0.4% to 5.0%

C. (1) Flow is heated to 1150-1400°F causing recombination of H 2 and 02 to occur.

(2) 0.5% to 4.0%

D. (1) Hydrogen is directed over electronic device that dissipates hydrogen via small combustions (2) 0.5% to 4.0%

61. With the unit initially at 100%, the steam dumps are pced in STEAM PRESSURE mode to allow for l&C testing.

Which ONE of the following describes how the STEAM PRESSURE arming signal is cleared following completion of the test?

The operator must A. shift the Steam Header Pressure Controller to manual and decreasing signal demand to zero.

B. take the Steam Dump Mode Selector Switch to the Tavg Mode.

C. take the Steam Dump Control Switch to Off/Reset and return the switch to the ON position.

D. take the Steam Dump Control Switch to the By-pass Interlock position.

62. Unit 1 Conditions The plant is at 50% rated thermal power.
  • 1-MS-PT-447, the selected pimp channel, fails low.

Assuming no operator action, which ONE of the following represents the correct response of SG water level?

A. SG water level control will be maintained at program level for 50% power.

B. SG water level will increase to 44%.

C. SG water level will increase to 75%, resulting in FW isolation at SG Hi-Hi level.

D. SG water level will decrease to 33%.

63. Both units are being fed by the Reserve Station Service Transformers Which ONE of the following pairs of condensate pumps will be automatically tripped by the actuation of a load shed?

A. 2AandlC B. lBand2C C. lAand2C D. 2BandlC

64. Unit 1 Current Conditions:
  • WGDT 1 B release is in progress.

When 1-GW-FCV-1O1 (PROCESS VENT WGDT EFFLUENT FLOW CONTROL) is throttled closed to terminate the release, steady state Process Vent flow will A. Decrease to zero B. Increase slightly C. Decrease slightly D. Remain the same

65. Which ONE of the following correctly completes the statements listed bow?

A (1) scintillation detector is used in the Containment Gas Monitor (1 -RM-RI-1 60).

And The units indicated on the Containment Gas Monitor (1 -RM-Rl-1 60) meter are (2)_.

A. (1) beta (2) cpm B. (1) beta (2) mR/hr C. (1) gamma (2)cpm D. (1) gamma (2) mR/hr

66. Current Conditions:
  • Unit 1 is in INTERMEDIATE SHUTDOWN.
  • 1-CH-MOV-1 381 (RCP Seal Return) is required to be locally shut in preparation for a clearance.
  • The local shutting of 1-CH-MOV-1381 is NOT directed by a procedure.
  • An emergency does NOT exist.

Which ONE of the following describes the necessary approval for local operation and the impact of manual MOV operation on operability, lAW OP-AA-100, Conduct of Operations?

Local operation of 1 -CH-MOV-1 381 must be authorized by .(1 ) and following manual operation, the valve will be considered (2).

A. (1) Shift Manager (2) inoperable B. (1) Shift Manager (2) operable C. (1) Manager Nuclear Operations (2) inoperable D. (1) Manager Nuclear Operations (2) operable

67. Current Conditions:
  • 1-FW-P-2, TURB DRVN AFW PUMP is being run for the monthy PT
  • 1-MS-SOV-i 02A, TURB DRVN AFW PUMP is OPEN.
  • 1-MS-SOV-102B, TURB DRVN AFW PUMP is CLOSED.
  • The service building operator identifies turbine speed is 4630 rpm.

Based on the above conditions, which ONE of the following describes the action to take lAW 1 -OPT-FW-003, Turbine Driven Auxiliary Feedwater Pump 1 -FW-P-2?

A. In the MCR, take i-MS-SOV-lO2Ato CLOSE.

B. In the MCR, verify 1-MS-SO V-i 02A in OPEN/RESET and take 1-MS-SOV-102B to OPEN/RESET. THEN take 1-MS-SOV-102A and 1-MS-SOV-102B to CLOSE.

C. Locally at the pump, trip the pump by cycling i-MS-TV-120, AFW Pump 2 Turb Trip Valve, at least one time and leave it in the LATCH position.

D. Locally at the pump, trip the pump by pushing the Manual Push Trip Lever.

68. You are in work control onaraiy day when an operator comes to you and states he has been assigned to 34.5 KV switching and tagging tasks. The operator was checking his PPE and noticed that the test date for a pair of electrical rubber insulating gloves was 9 months old.

In accordance with SA-AA-125 Electrical Safety, which ONE of the following describes (1) if electrical rubber insulating gloves are required to be used when performing 34.5 KV switching and tagging tasks in the rain, and (2) If this pair of gloves needs to be retested before use?

A. (1)yes (2) yes B. (1)yes (2)no C. (1)no (2) yes D. (1)no (2) no

69. Unit 1 Current Conditions:
  • Tavgisl6OF.
  • The reactor is subcritical by 3% delta-k/k.
  • Reactor defueling is scheduled to begin in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Based on the current conditions, which one of the following correctly completes the statements listed below in accordance with the Surry Power Station Technical Specifications?

Unit us currently in (1)  ?

And Following completion of refueling, the reactor must be subcritical by at least (2)  %

delta-k/k in order to be in INTERMEDIATE SHUTDOWN.

A. (1) COLD SHUTDOWN (2) 1 B. (1) COLD SHUTDOWN (2)1.77 C. (1) REFUELING SHUTDOWN (2) 1 D. (1) REFUELING SHUTDOWN (2) 1.77

70. Unit 1 Conditions:
  • Unit 1 was at 100% power.
  • A SGTR occurred, resulting in an automatic SI.
  • All systems responded as designed.
  • RCS cooldown has been completed.
  • The operating crew has commenced RCS depressurization.
  • Pressurizer level is 20% and rising.
  • Subcooling is 100 °F and rising.

Based on the above conditions, which ONE of the following describes the required actions of the operating crew?

The operating crew shall A. immediately stop all high head safety injection pumps.

B. go to 1-ES-0.0, REDIAGNOSIS.

C. continue with the procedure in effect.

D. immediately go to 1-FR-H.3, Response to Steam Generator High Level.

71.
  • The unit was shutdown and placed on RHR Cooling for a refueling outage. All fuel has been offloaded and the A train of RHR secured for maintenance.
  • In the A Loop room, the area around the letdown isolation valves has been surveyed and is reading 175 mr/hr. This is the maximum dose observed in the loop room. The dose rate is 35 mr/hr at the loop room entrance.
  • The entrance gate to the loop room is being maintained UNLOCKED.
  • An Operator has been assigned the task to hang a tagout in the room, It is expected that this task will take 10 to 15 minutes to complete.

Which ONE of the following describes:

(1) In accordance with 10 CFR 20 requirements, how should HP post the room?

AND (2) In accordance with VPAP-21 01, Radiation Protection Program, can the Operator pertorm the task on the general Operator Clearance RWP, or must a specific RWP be obtained?

A. (1) Radiation Area (2) General RWP is sufficient B. (1) Radiation Area (2) Specific RWP is required C. (1) High Radiation Area (2) General RWP is sufficient D. (1) High Radiation Area (2) Specific RWP is required

72. Initial Conditions:
  • Unit Two is currently commencing the spring 2011 refueling outage..

Current Conditions:

  • The refueling team is preparing to load the first Fuel Assembly into the reactor vessel.

Based on the current conditions, which ONE of the following completes both of the below statements in accordance with 2-OP-FH-001, CONTROLLING PROCEDURE FOR REFUELING?

The MINIMUM allowable reactor cavity boron concentration for Refueling Shutdown is (1)

AND The LATEST point in time when base neutron count rates for SRNI N-31 and SRNI N-32 is allowed to be obtained is (2)

A. (1)2250 ppm (2) after the fourth (

th) Fuel Assembly is loaded into the core and before the fifth (

4 th) 5 Fuel Assembly is loaded into the core.

B. (1)2350ppm (2) after the fourth (

th) Fuel Assembly is loaded into the core and before the fifth (Sth) 4 Fuel Assembly is loaded into the core.

C. (1)2250 ppm (2) after the eighth (

th) Fuel Assembly is loaded into the core and before the ninth (gth) 8 Fuel Assembly is loaded into the core.

D. (1)2350 ppm (2) after the eighth (ath) Fuel Assembly is loaded into the core and before the ninth (

th) 9 Fuel Assembly is loaded into the core.

73. Initial Conditions:
  • Unit 1 experienced an automatic SI coincident with a total loss of offsite power Current Conditions:
  • All Power Range Nl=4% and increasing
  • All Intermediate Range SUR=+O.1 DPM and stable
  • All CETs=71 5 °F and lowering slowly
  • RVLIS Full Range=26% and increasing slowly
  • Total AFW Flow=200 GPM and stable
  • All SIG NR levels=O% (downscale low)
  • RWST Level=1O% and lowering
  • Recirculation has been established in accordance with 1-ES-i .3, TRANSFER TO COLD LEG RECIRCULATION
  • Containment sump levels are oscillating erratically
  • Amps, flows, and discharge pressures on the running ECCS pumps aligned for recirculation are all oscillating erratically
  • A transition to Attachment 1, CONTAINMENT SUMP SCREEN BLOCKAGE CONTINGENCY ACTIONS, of i-ES-i .3 has just been announced by the SRO Based on the current conditions, which ONE of the following is a correct evaluation of critical safety function procedural implementation?

A. Implementation of i-FR-S.i, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, takes precedence over implementation of i-FR-H.i, RESPONSE TO LOSS OF SECONDARY HEAT SINK B. Implementation of i-FR-H.i, RESPONSE TO LOSS OF SECONDARY HEAT SINK, takes precedence over implementation of Affachment 1 of 1-ES-i .3 C. Implementation of Attachment 1 of 1-ES-i .3 takes precedence over implementation of i-FR-C.1, RESPONSE TO INADEQUATE CORE COOLING D. Implementation of i-FR-H.i, RESPONSE TO LOSS OF SECONDARY HEAT SINK, takes precedence over implementation of i-FR-C.2, RESPONSE TO DEGRADED CORE COOLING

74. Unit 1 Conditions:
  • An RCS Cooldown using the Steam Dumps has been initiated.
  • One Charging Pump is running and flowing to the RCS.
  • RCS subcooling is 29°F.
  • Based on the conditions listed above, which one of the following correctly completes the statements listed below?

Flow on each Main Steamline should be kept less than 1.0 X 1 6 PPH to prevent (1)

And RCP trip criteria _(2)_ apply.

A. (1) Main Steamline isolation (2) do B. (1) Main Steamline isolation (2) do NOT C. (1) exceeding the Technicat Specification cooldown rate limit (2)do D. (1) exceeding the Technical Specification cooldown rate limit (2) do NOT

75. Which ONE of the following descrthes the lowest position on the Station Emerge 1

Organization chart that may authorize the use of Emergency Exposure Limits?

A. Unit Supervisor B. Station Emergency Manager C. Radiation Protection Supervisor D. Radiological Assessment Director

76. Due to RCS pressure and level decreasing excessivel a team entered AP-16.OO, transitioned to 1-E-O, and initiated SI on step 4 of 1-E-O.

The team identified the leakage as a LOCA outside of containment on the Tc LHSI piping and just closed 1-SI-MOV-1890C (LHSI to Tc).

Using the supplied PCS drawing, which ONE of the following states 1) whether the RCS leakage has been isolated, and 2) the appropriate procedure for the team to transition to upon exit from 1 -ECA-1 .2 (LOCA Outside Containment)?

REFERENCE PROVIDED A. (1) RCS leakage IS isolated (2) 1 -ECA-1 .1 (Loss of Emergency Coolant Recirculation)

B. (1) RCS leakage is NOT isolated (2) 1 -ECA-1 .1 (Loss of Emergency Coolant Recirculation)

C. (1) RCS leakage is NOT isolated (2) 1-E-1 (Loss of Reactor or Secondary Coolant)

D. (1) RCS leakage IS isolated (2) 1-El (Loss of Reactor or Secondary Coolant)

77. 0800: Unit 1 is at 100% steady-state power. PCS is out of service.

0810: The following annunciator is received:

  • 1C-F2 RCP BRG HI TEMP 0812: The plant operator reports RCP 10 Upper Radial Bearing Temperature is 199 degrees F and 10 RCP Lower Radial Bearing Temperature is 192 degrees F.

Based on the above conditions, at 0812 which ONE of the following (1) are the actions required by procedure, AND (2) is the Technical Specification basis for prohibiting power operation with less than 3 RCPs in service?

A. (1) The Reactor must be shutdown and 10 RCP stopped.

(2) The design limit for departure from nucleate boiling ratio (DNBR).

B. (1) Continued operation is allowed, increase monitoring of 10 RCP.

(2) The design limit for fuel peak centerline temperature (POT).

C. (1) Continued operation is allowed, increase monitoring of 10 RCP.

(2) The design limit for departure from nucleate boiling ratio (DNBR).

D. (1) The Reactor must be shutdown and 10 RCP stopped.

(2) The design limit for fuel peak centerline temperature (POT).

78. A plant shutdown is in progress. RCS temperature is 358 F and slowly being lowered per GOP-2.4, Unit Cooldown, HSD to 351 F. Both Pressurizer PORVs have failed their setpoint adjustment post maintenance tests and have been declared inoperable. l&C states that it will take 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to repair the instruments and restore the valves to operable.

The cooldown can continue if pressurizer level is maintained less than (1). The Technical Specification basis for this allowance is that the pressurizer (2).

A. (1) 33%

(2) steam bubble wili mitigate any pressure transients for at least 5 minutes to allow for operator action B. (1) 33%

(2) level allows approximately 10 minutes for operator action to mitigate any pressure transient events C. (1) 50%

(2) level allows approximately 10 minutes for operator action to mitigate any pressure transient events D. (1) 50%

(2) steam bubble will mitigate any pressure transients for at least 5 minutes to allow for operator action

79. At 09:50, a steam line fault in safeguards occurred on Unit 1 with the following plant parameter timeline:

At 10:00

  • All SG NR levels at 5%, stable
  • All SG pressures 650 psig, lowering uncontrollably
  • Containment Pressure 10.8 psia, stable
  • Pressurizer level 10%
  • Steam Safety Rad Monitors:
  • MS-RM-1 24 reading 2 mr/hr, stable
  • MS-RM-125 reading 4 mr/hr, stable
  • MS-RM-126 reading 2 mr/hr, stable 10:15
  • All SG NR levels at 7%, rising slowly
  • SG A and SG B pressures 500 psig, lowering uncontrollably
  • SG C pressure 700 psig, rising
  • Containment Pressure 10.8 psia, stable
  • RCS Pressure 1900 psig; cool down rate >100 °FIhr
  • Pressurizerlevell5%
  • Steam Safety Rad Monitors:
  • MS-RM-124 reading 2 mr/hr, stable
  • MS-RM-125 reading 4 mr/hr, stable
  • MS-RM-126 reading 2 mr/hr, stable
  • Both motor driven AFW pumps have tripped on overcurrent AT 10:15, which ONE of the following identifies (1) the required procedure, and (2) whether an emergency classification is REQUIRED in accordance with Emergency Action Level Matrix?

(Exclude SEM judgment classifications)

REFERENCE PROVIDED A. (1) Remain in ECA-2.1 (2) NOUE B. (1) Exit ECA-2.1 and transition to E-2 (2) NOUE C. (1) Remain in ECA-2.1, (2) ALERT D. (1) Exit ECA-2.1 and transition to E-2 (2) ALERT

80. Unit 1 Initial Conditions:
  • Lowest indicated Tc is 250° F.
  • Wide Range RCS Pressure is 320 psig.
  • Cooldown is in progress per 1 -GOP-2.5 (UNIT COOLDOWN, 351°F TO LESS THAN 205° F).
  • RHR is in service.
  • Pressurizer level is decreasing at a rate that cannot be accounted for due to the cooldown.
  • Makeup flow is maximized and with pressurizer level still decreasing.

Unit 1 Current Conditions:

  • A Station Blackout has occurred.
  • Both AC Emergency Buses are DEENERGIZED.

Based on the current conditions, which ONE of the following will correctly complete the statements listed below?

_(1)_ must be initiated to address the loss of both Emergency Buses.

And

_(2)_ must be initiated to mitigate the loss of reactor coolant.

A. (1) 1-AP-1 0.07 (LOSS OF UNIT 1 POWER)

(2) 1AP-16.01 (SHUTDOWN LOCA)

B. (1) 1-AP-1 0.07 (LOSS OF UNIT 1 POWER)

(2) 1-AP-1 6.00 (EXCESSIVE RCS LEAKAGE)

C. (1) 1-ECA-0.0 (LOSS OF ALL AC POWER)

(2) 1-AP-1 6.01 (SHUTDOWN LOCA)

D. (1) 1 -ECA-0.0 (LOSS OF ALL AC POWER)

(2) 1-AP-1 6.00 (EXCESSIVE RCS LEAKAGE)

81. Unit 1 conditions at 0900:
  • 100% Power
  • 230 KV system voltage is 225 Ky.
  • The Generator Voltage Regulator is in AUTO.

Unit 1 conditions at 1000:

  • 230 KV system voltage is 218 KV
  • The crew is attempting to increase voltage lAW 1-OP-26.5, 230 KV Switchyard Voltage, Section 5.1, Corrective Actions to be Taken in the Event 230 KV Voltage is Sagging Below the Scheduled Voltage.
  • The crew has entered 0-AP-1 0.18, Response to Grid Instability.

Which ONE of the following states (A) how the crew is attempting to increase voltage lAW 1-OP-26.5 section 5.1, and (B) based on the current conditions, the status of the 230kv distribution system operability (in accordance with 0-AP-10.18 and Tech Specs)?

The Voltage Regulator (1) when operating the EXCITATION LEVEL control switch in the RAISE direction. lAW TS 3.16 and 0-AP-10.18, the 230kv distribution system is (2)

A. (1) must be placed in MANUAL (2) INOPERABLE B. (1) must be placed in MANUAL (2) OPERABLE C. (1) mayremain in AUTO (2) INOPERABLE D. (1) may remain in AUTO (2) OPERABLE

82. Initial plant condWons:

- Reactor Power = 60%

- Power increase to 100% is in progress

- Control Rod Bank D is at 165 steps Current plant conditions:

- Reactor Power = 70%

- Control Bank D positions are as follows:

- Group position = 175 steps

- Rod B8 drops to 0 steps

- Rod K10 drops to 155 steps

- Annunciator 1 G-H2, RPI ROD BOTTOM < 20 STEPS LIT -

- 0-AP-1 .00 ROD CONTROL SYSTEM MALFUNCTION is entered Based on the above plant conditions, Rod Ki 0 is considered and 0-AP-1 .00 directs the operator to: 2 A. 1) Operable

2) GO TO 0-AP-1 .01, CONTROL ROD MISALIGNMENT B. 1) Inoperable
2) Trip the Reactor and GO TO 1-E-0, REACTOR TRIP OR SAFETY INJECTION C. 1) Inoperable
2) GO TO 0-AP-1 .01, CONTROL ROD MISALIGNMENT D. 1) Operable
2) Trip the Reactor and GO TO 1-E-0, REACTOR TRIP OR SAFETY INJECTION
83. Initital Conditions (2210):

- Unit 1 is operating at full power

- In preparations for an upcoming refueling outage, the 1 H stub bus is tagged out

- A fire is reported in the Emergency switchgear room and the fire brigade is dispatched Current Conditions (2230):

- The brigade leader reports that there are flames and smoke billowing from the 1J stub bus feeder breaker.

- The Control Room has completed the applicable portions of AP-48.00, Fire Protection Operations Response.

Which ONE of the following describes:

(1) The procedure the crew should transition to lAW AP-48.00, Attachment 3, Appendix R Safe Shutdown Functions, and (2) The correct Emergency Classification?

Reference Provided A. (1) 1-FS-FP-107, Unit 1 Emergency Switchgear Room Elevation 9 FT, 6 IN (2) Alert B. (1) 1-FCA-4.00, Limiting ESGR Number 1 Fire (2) Unusual Event C. (1) 1-FS-FP-107, Unit 1 Emergency Switchgear Room Elevation 9 FT, 6 IN (2) Unusual Event D. (1) 1-FCA-4.00, Limiting ESGR Number 1 Fire (2) Alert

84. Which ONE of the following describes the assumed sources of water used to determine the setpoint for entry into FR-Z.2, Containment Flooding, and when FR-Z.2 is applicable?

A. RCS, RWST, and SI accumulators only: FR-Z.2 is applicable between in Model through Mode 3 only.

B. RCS, RWST, and SI accumulators only: FR-Z.2 is applicable between in Model through Mode 4.

C. RCS, RWST, Chemical Addition Tank, and SI accumulators: FR-Z.2 is applicable between Modes 1 through Mode 3 only.

D. RCS, RWST, Chemical Addition Tank, and SI accumulators: FR-Z.2 is applicable between Model through Mode 4.

85. Unit 1 Initial Conditions:
  • Unit 1 has experienced a Loss of All AC Power.
  • 1-ECA-0.1 (LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED) is complete.

Unit 1 Current Conditions:

  • Tave is 547 F.
  • 1 D-B5 (ICCM System Failure) is in alarm due to failed power supplies on Channels A &

B.

  • All Reactor Coolant Pumps are unavailable due to a prolonged loss of seal cooling.
  • The Shift Manager has directed a cooldown to less than 2000 F within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> due to impending weather conditions.

Based on the current conditions, which ONE of the following correctly completes the statements listed below?

(1) will be used to complete the cooldown.

And (2) if Pressurizer level increases to 90% during RCS depressurization.

A. (1) 1-ES-0.2 (NATURAL CIRCULATION COOLDOWN)

(2) Increase RCS Pressure by 100 psi using Pressurizer Heaters B. (1) 1-ES-0.2 (NATURAL CIRCULATION 000LDOWN)

(2) Adjust charging and letdown flows to restore Pressurizer level to required band C. (1) 1-ES-0.4 (NATURAL CIRCULATION 000LDOWN WITH STEAM VOID IN RX VESSEL) (W/O RVLIS)

(2) Increase RCS Pressure by 100 psi using Pressurizer Heaters D. (1) 1-ES-0.4 (NATURAL CIRCULATION COOLDOWN WITH STEAM VOID IN RX VESSEL) (W/O RVLIS)

(2) Adjust charging and letdown flows to restore Pressurizer level to required band

86. Initial Conditions
  • 1-GOP-2.5, Unit Cooldown 351°F to Less Than 205°F is complete.
  • All safety systems are aligned lAW 1 -OSP-ZZ-004, Unit 1 Safety Systems Status List for Cold Shutdown/Refueling Conditions.
  • 1-CH-PCV-1145, LTDN LINE PRESS CNTRL is in AUTO and set to 300 psig.
  • 1-RC-Pl-1458, RCS PRESS NAR RANGE, indicates 305 psig.
  • 1-RC-LI-1462, PRZR LEVEL START UP indicates 83%.
  • Charging flow has been adjusted to increase PRZR level to SOLID lAW step 5.2.19.e.3 of 1-GOP-2.6.

Current Conditions

  • The PRZR is solid.
  • 1-RC-PCV-1456 and 1-RC-PCV-1455C, PRZR PORVs, have cycled.
  • Annunicator 1 D-B6, PRZR NDTT HI PRESS is alarming.

Which ONE of the following describes the required actions?

Per ARP 1 D-B6, the most effective method to lower RCS pressure is by (1) . In accordance with Technical Specification 6.6.C, Special Reports, this event 2) required to be reported to the NRC.

A. (1) lowering charging flow (2) is B. (1) lowering charging flow (2) is not C. (1) securing PRZR heaters while maintaining spray flow (2) is D. (1) securing PRZR heaters while maintaining spray flow (2) is not

87. kiWal Conditions
  • Unit 1 is operating at 100% power.

Current Conditions:

  • Rx Trip due to load rejection.
  • 1-E-0 is in progress.
  • AC Emergency Bus H has no power.
  • SI has initiated.
  • RCS temperature trending to 547° F.
  • PRZR PORV 1-RCPCV-1455C stuck open.
  • PRZR PORV Block valve 1 -RC-MOV-1 536 will not close.
  • 1-CH-P-1B Charging pump red lights lit, green light off.
  • 1 -CH-P-1 B Charging pump indicating 5 amps on the control panel.
  • RCS subcooling 17°F decreasing.

Based on the current conditions, which ONE of the following describes (1) the procedure that FIRST gives guidance for RCP operation and (2) what direction it gives?

A. (1) 1-E-1 (2) Stop all RCPs B. (1) 1-E-0 (2) Stop all RCPs C. (1) 1-E-1 (2) Do NOT stop RCPs D. (1) 1-E-0 (2) Do NOT stop RCPs

88. A reactor startup sin progress. Power is currently at 9% and holding for turbine issues. An Intermediate Range Instrument fails low.

Which ONE of the following is acceptable by Technical Specification 3.7 (Instrumentation Systems)?

A. Reduce power to below P-6 within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

B. Raise power to greater than 11% within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C. Power operation may continue without restriction.

D. Current power can be maintained indefinitely. Return the instrument to OPERABLE status prior to raising power.

89. Current Conditions:
  • Unit 1 is operating at 100% power.
  • 1 -CC-RM-1 05 radiation levels have remained stable over the last 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
  • 1 -CC-RM-1 06 radiation levels have shown a lowering trend over the last 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
  • An instrumentation technician reports that the cause of the lowering trend on 1 -CC-RM-1 06 is calibration drift in the detector.
  • HCV-CC-100, CC Surge Tank Vent Valve is OPEN.

Based on the current conditions, which ONE of the following describes (A) the effect of the calibration drift on the CC system (if any), and (B) the requirements of Technical Specification (TS) 3.13, Component Cooling System?

HCV-CC-100, CC Surge Tank Vent Valve, 1) have the ability to close automatically and (2)____

A. (1) does (2) may remain OPEN.

B. (1) does (2) must be SHUT.

C. (1)does not (2) may remain OPEN.

D. (1)doesnot (2) must be SHUT.

90. Initial Condition:

- Both Units at 100% power

- While moving equipment in the turbine building in preparation for an upcoming refueling outage, a forklift strikes an instrument air pipe and separates the line in two.

Current Conditions:

- Feed flow is decreasing to all Unit One Steam Generators

- Current S/G Narrow Range levels are:

- A S/G 19%

- B S/G 22%

- C S/G 20%

- 1F-C7 (STM GEN 1A CH 3 FW < STM FLOW) is LIT

- 1 F-D7 (STM GEN 1A CH 4 FW <STM FLOW) is LIT

- 1 F-C8 (STM GEN 1 B CH 3 FW <STM FLOW) is LIT

- 1 F-D8 (STM GEN 1 B CH 4 FW <STM FLOW) is LIT

- 1F-C9 (STM GEN 1C CH 3 FW <STM FLOW) is LIT

- 1F-D9 (STM GEN 1C CH 4 FW <STM FLOW) is LIT

- Demand on all main feedwater regulating valves is 72% and increasing Which ONE of the following states 1) the appropriate team response to these indications, and

2) the first procedure to be initiated by the SRO?

A. 1) Direct the BOP operator to manually increase demand on the feed reg valves.

2) 0-AP-40.00 B. 1) Direct the reactor operator to perform immediate actions of 1 -E-0.
2) 1-E-O C. 1) Direct the operator to perform the immediate actions of 1-FR-S.1
2) 1-FR-S.1 D. 1) Direct the BOP operator to start the r 3d condensate pump and reduce turbine load using the limiter.
2) 1-AP-21.00
91. WhkDh ONE of the followig completes the statement regarding the Manulator Crane Lifting Hoist Overload Interlock?

The OVERLOAD interlock (1) be bypassed, and the reason for this interlock, in accordance with the basis for Technical Specification 3.10 (REFUELING), is (2)

A. (1)can (2) to prevent movement of a disengaged fuel assembly that is hung up on the gripper B. (1) can NOT (2) to prevent movement of a disengaged fuel assembly that is hung up on the gripper C. (1)can (2) to prevent movement of more than one fuel assembly at a time D. (1)canNOT (2) to prevent movement of more than one fuel assembly at a time

92. Unit One Reactor Startup is in progress and a bance shot has just been completed on the main turbine. The team is preparing to assign admin control of the main steam trip valve bypass valves in accordance with 1 -OP-TM-001, attachment 2 (Adminstrative Control Requirements for Main Steam Trip Valve Bypass Valves).

The briefing for the admin control states: The valve shall be immediately closed upon notification from the Control Room of a SI initiation.

Which ONE of the following states 1) the specific time requirement to satisfy immediate in accordance with SUADM-O-26 (Administrative Control of Operational Components), and 2) whether the operator assigned admin controls can perfrom the pre-start checks of 1 -FW-P-2 (to support upcoming start-up activities) while assigned admin control?

A. 1) 60 seconds

2) Yes B. 1)40 seconds
2) Yes C. 1) 60 seconds
2) No D. 1) 40 seconds
2) No

r 93. Current Conditions

  • Unit 2 is stable at the POAH with physics testing in progress.
  • PR Channel N-44 is still in trip because the reactivity recorder is installed.
  • The National Hurricane Center just issued a Hurricane Warning for Surry County.
  • Unit Two has just been directed to shut down due to hurricane force winds expected onsite within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
  • Unit One is currently shutdown and maintaining 300°F in the RCS.
  • A fault occurs in the 2B1 UPS that causes the loss of Vital Bus II and llA.
  • The reactor is tripped as required by 2-AP-10.02, Loss of Vital Bus II.

Which ONE of the following describes:

(1) How many SR indications are available on Unit 2 after tripping the unit?

AND (2) What RCS temperature should be maintained?

A. (1)0 (2) 200°F to 345°F per 0-AP-37.01, Abnormal Environmental Conditions.

B. (1)1 (2) 200°F to 345°F per 0-AP-37.01, Abnormal Environmental Conditions C. (1)0 (2) > 530° F per 1 -AP-4.0, Nuclear Instrumentation Malfunction.

D. (1)1 (2) > 530°F per 1-AP-4.0, Nuclear Instrumentation Malfunction.

94. Initial Conditions:
  • At time 0930, unexpected grid fluctuations caused an automatic turbine trip from 100%

power.

  • Chemistry personnel drew a post-trip RCS sample at time 1005.
  • Control room operators have stabilized the unit at 547 °F and normal operating pressure.

Current conditions:

  • At time 1045, chemistry reports the following:
  • E-bar is 10 Mev/disintegration.
  • Dose Equivalent 1-131 is 0.5 microcuries/cc.
  • RCS specific activity 15 microcuries/cc.

Based on the current conditions, which ONE of the following describes (1) the appropriate actions in accordance with Technical Specification (TS) 3.1 .D, Maximum Reactor Coolant Activity, and (2) the reporting requirements lAW TS 6.6.A.2, if any?

LCO 3.1.D for Dose Equivalent 1-131 (1) met, and the current chemistry results

2) reportable to the Commission pursuant to TS 6.6.A.2.

REFERENCE PROVIDED A. (1)is (2) are B. (1)is (2) are NOT C. (1)isNOT (2) are D. (1)isNOT (2) are NOT

95. Which ONE of the following correctly completes the statements listed below?

Per SY-AA-1O1 (Security Access and Control), (1) escort(s) is\are required for escorting ten personnel into the Control Room area.

And Per OP-AA-100 (Conduct of Operations), the (2) shall give prior approval for Control Room tours.

A. (1)one (2) Unit Supervisor B. (1)one (2) Shift Manager C. (1)two (2) Unit Supervisor D. (1)two (2) Shift Manager

E 9 6 A temporary level indkator is to be installed for the VCT using the Temporary Modif ication process detailed in CM-AA-TDC-204, Temporary Modifications.

Which ONE of the following describes the Temporary Modification process lAW CM-AA-TDC-204?

The Manager Radiological Protection (or alternate) (1) required to be a member of the Facility Safety Review Committee (FSRC) for this modification, and the MINIMUM level of Station Management approval required for Extension of Temporary Modification Duration, assuming no unresolved conditions, is the (2)

A. (1)is (2) FSRC B. (1)is (2) Site Vice President C. (1) is not (2) FSRC D. (1)isnot (2) Site Vice President

97. The 1A RHR Pump surveHlance has just been completed. The following data has been recorded on the Data Sheet from Attachment 4 of 1-OPT-RH-003, RHR System Operability Test:

Note: Recorded data is in the shaded region.

Record ReFerence Satisfactory Alert Unsatisfactory Adjusted = 375 psid 81 4 to 90.1 psid 73.3 to 81,4 psid LP 78.8 pd P 892 psid or From Substep > 90.1 pd 6 .513c Vh =0i052 in/sec \Th = 0 0837 1< 0 2092 insec 0 2092 Vh = Vim> 0.5022 n sac in.sec 05fl22 in.c I, = 0 0972 in/sec = U 323 1 2u35 in ec fl2Li35 Ii 4.E3 ii sec nsec 01956 n.c Va 0i288 in/sec Vs = 0 0502 Va< 0.1255 insec 01255 Va Va> 0 3 012 insec insec 0.3012 n.sec Which ONE of the following completes the statement:

The 1A RHR pump is __(1)_; __(2)__ required.

A. (1) operable (2) no further action is B. (1) operable (2) a Condition Report is C. (1) inoperable (2) an immediate retest is D. (1) inoperable (2) a Condition Report is

98. Initial conditions:

- Unit One experiencing a LOCA with fuel failure Present conditions:

- 1-RM-Rl-157, Main Control Room Radiation Monitor, alarms. It currently reads 2.6 mr/hr and is rising.

- Main control room supply and exhaust has been isolated, and 1 -VS-F-41, Emergency Supply Fan has been started.

- The following data is noted:

  • PDI-VS-100, D.P.-U1CR/U1TB -0.2 water
  • PDI-VS-101, D.P.-U1RR/U1TB +O.1water
  • PDI-VS-200, D.P.-U2CR/U2TB -0.1 water
  • PDI-VS-201, D.P.-U2RR/U2TB ÷0.1 water
  • All pressure indications are degrading Based on the above conditions, which ONE of the following describes (1) what action(s) is (are) required by 1 -E-0 (Reactor Trip or Safety Injection), and (2) what the status of the Control Room Envelope is, per TS 3.21?

A. (1) Secure MCR Boundary Fans.

(2) Operable B. (1) Secure MCR Boundary Fans.

(2) Inoperable C. (1) Start an additional emergency supply fan.

(2) Operable D. (1) Start an additional emergency supply fan.

(2) Inoperable

99. Initial Conditions:
  • Unit 1 is experiencing a sustained Loss of All AC Power condition.
  • The TDAFW pump shaft sheared on startup, and all efforts to cross-connect AFW with Unit 2 have failed.

Current Conditions:

  • All emergency buses remain de-energized.
  • Operators have just completed the step in ECA-0.0 to Check DC Bus Loads, and have placed both the DC emergency oil pump and the Air Side seal oil backup pump in PTL.
  • STA reports the following Critical Safety Function Status Trees:
  • Core Cooling: RED
  • Heat Sink: RED
  • Containment: ORANGE
  • Inventory: YELLOW
  • Subcriticality: GREEN
  • Integrity: GREEN Based on the current conditions, which ONE of the following describes the appropriate procedure to be used NEXT to mitigate the casualty?

A. Transition to 1 -SACRG-1, SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL RESPONSE.

B. Continue in 1-ECA-0.0, LOSS OF ALL AC POWER.

C. Transition to 1-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.

D. Transition to 1-FR-C.1, RESPONSE TO INADEQUATE CORE COOLING.

1 00. Unit 1 Initial Conditions:

  • 100% power Current conditions:
  • A maintenance worker inadvertently tripped the Unit 1 Main Turbine while working at the turbine front end.
  • The Reactor Protective System automatically initiated a Reactor Trip.

Based on the current conditions, which ONE of the following correctly describes (1) whether the Reactor Trip should be considered a VALID or INVALID actuation, as defined by VPAP-2802, Notifications and Reports, AND (2) the shortest time requirement to report this event to the NRC, as specified by VPAP-2802?

REFERENCE PROVIDED A. (1) VALID actuation (2) 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification B. (1) INVALID actuation (2) 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification C. (1) VALID actuation (2) 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification D. (1) INVALID actuation (2) 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification

ANSWER KEY REPORT for Surry RO-SRO Combined 2012 Test Form: 0 Answers W ID Points Type 0 1 007 EK2.02 1 1.00 MCS B 2 008 AKI.01 1 1.00 MCS C 3 011 EAI.09 1 1.00 MCS C 4 022 AA2.02 1 1.00 MCS D 5 025 G2.4.31 1 1.00 MCS B 6 026 AA2.01 1 1.00 MCS A 7 027 AK2.03 1 1.00 MCS D 8 029 EA 1.03 1 1.00 MCS C 9 038 EK3.01 1 1.00 MCS B 10 040 WEI2 EK2.1 1 1.00 MCS D 11 055 EKI.02 1 1.00 MCS B 12 057 AK3.01 1 1.00 MCS C 13 058 AAI.01 1 1.00 MCS A 14 062 AA2.01 1 1.00 MCS ID 15 065 G2.1.31 1 1.00 MCS B 16 WIEO4 G2.4.45 1 1.00 MCS B 17 W/E11 EK1.2 1 1.00 MCS B 18 WIEO5 EK3.2 1 1.00 MCS ID 19 003 AK3.07 1 1.00 MCS C 20 024 AK2.03 1 1.00 MCS A 21 028 AK2.02 1 1.00 MCS ID 22 033 AKI.01 1 1.00 MCS A 23 069 WE14 EK3.4 1 1.00 MCS B 24 W/E13 EAI.1 1 1.00 MCS C 25 032 AA2.02 1 1.00 MCS B 26 W/E03 G2.1.20 1 1.00 MCS D 27 WIEO8 EA2.2 1 1.00 MCS D 28 003 K6.02 1 1.00 MCS C 29 003 A3.03 1 1.00 MCS B 30 004 A2.13 1 1.00 MCS D 31 004 G2.4.2 1 1.00 MCS A 32 005 K5.02 1 1.00 MCS C 33 005 G2.2.42 1 1.00 MCS C 34 006A4.101 1.00 MCS ID 35 007 K4.01 1 1.00 MCS A 36 007 A3.01 1 1.00 MCS A 37 008 A2.04 1 1.00 MCS C 38 010 K2.02 1 1.00 MCS B 39 010 A1.04 1 1.00 MCS A 40 012 K6.03 1 1.00 MCS ID 41 013K1.121 1.00 MCS D 42 013 K5.02 1 1.00 MCS B 43 022 K4.05 1 1.00 MCS C 44 026 K3.02 1 1.00 MCS B 45 039 A4.04 1 1.00 MCS B 46 059 K1.02 1 1.00 MCS C Tuesday, September 25, 2012 7:49:33 AM

ANSWER KEY REPORT for Surry RO-SRO Combined 2012 Test Form: 0 Answers

  1. ID Points Type 0 47 061 K2.01 1 1.00 MCS D 48 061 K5.02 1 1.00 MCS D 49 078 K3.02 1 1.00 MCS B 50 063 K4.02 1 1.00 MCS B 51 063 A1.01 1 1.00 MCS B 52 064 K6.07 1 1.00 MCS B 53 073 A2.01 1 1.00 MCS A 54 076 A1.02 1 1.00 MCS C 55 103 A3.01 1 1.00 MCS B 56 001 K2.03 1 1.00 MCS B 57 011 K3.01 1 1.00 MCS B 58 017 K6.01 1 1.00 MCS B 59 027 K1.01 1 1.00 MCS D 60 028 02.1.28 1 1.00 MCS C 61 041 A4.02 1 1.00 MCS B 62 035 A3.01 1 1.00 MCS D 63 056 A2.04 1 1.00 MCS C 64 071 A1.06 1 1.00 MCS D 65 072 KS .01 1 1.00 MCS A 66 02.1.1 1 1.00 MCS C z.ss 67 02.1.8 1 1.00 MCS D 68 02.1.26 1 1.00 MCS A 69 02.2.35 1 1.00 MCS B 70 02.2.44 1 1.00 MCS C 71 02.3.71 1.00 MCS e D i/L//_

72 02.3.12 1 1.00 MCS D 73 02.4.5 1 1.00 MCS C 74 02.4.20 1 1.00 MCS B 75 02.4.37 1 1.00 MCS B 76 00902.1.191 1.00 MCS D 77 015 AA2.08 1 1.00 MCS A 78 027 02.1.23 1 1.00 MCS B 79 O4OWEI2EA2.22 1.00 MCS D 80 055 02.4.9 1 1.00 MCS C 81 077 AA2.05 2 1.00 MCS C 82 005.AA2.03 1 1.00 MCS B 83 067 02.4.11 1 1.00 MCS D 84 W/E1S G2.4.18 1 1.00 MCS D 85 WIEIO EA2.1 1 1.00 MCS C 86 004 A2.01 1 1.00 MCS A 87 006 A2.05 1 1.00 MCS D 88 012 02.2.38 1 1.00 MCS B 89 073 A2.03 1 1.00 MCS B 90 078 02.1.7 2 1.00 MCS B 91 034 K4.03 1 1.00 MCS C 92 045 02.1.23 1 1.00 MCS D Tuesday, September 25, 2012 7:49:33 AM 2

ANSWER KEY REPORT for Surry RO-SRO Combined 2012 Test Form: 0 Answers

  1. ID Points Type 0 93 015 A2.04 1 1.00 MCS A 94 02.1.34 1 1.00 MCS A 95 G2.1.13 1 1.00 MCS D 96 02.2.11 1 1.00 MCS A 97 02.2.12 1 1.00 MCS B 98 G2.3.13 1 1.00 MCS B 99 G2.4.16 1 1.00 MCS A 100 02.4.30 1 1.00 MCS A SECTION 1 (100 ftems) 100.00 Tuesday, September 25, 2012 7:49:33 AM 3

NRC Exam Reference Materials Table of Contents Page 1á

RO Exam References Page Reference 4 1-AP-9.OO Attachment 4 (Determining No. 3 Seal Cavity Pressure (P3) Using RCP Seal Leakoff) 5 1-AP-27.OO Attachment 2 (Minimum RCS Level Versus RHR Flow (1-RC-Ll-100A)

Page 2

SRO Exam References Page Reference 4 1-AP-9.OO Attachment 4 (Determining No. 3 Seal Cavi ty Pressure (P3) Using RCP Seal Leakoff) 5 1-AP-27.OO Attachment 2 (Minimum RCS Level Vers us RHR Flow (1-RC-Ll-100A) 6 PCS Drawing Unit 1 Low Head Safety Injection 7 Surry Power Station EAL Matrix Revision 2 8,9 Technical Specifications 3.1.D (Pages 3.1-1 5a & 3.1-15b) 10 VPAP- 2802 Notifications and Reports Page 3

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