ML16179A268

(Unit 1) 2016-301 RO As-Given Written Exam

ML16179A268
Person / Time
Site:	Summer
Issue date:	06/24/2016
From:	NRC/RGN-II
To:	South Carolina Electric & Gas Co
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Download: ML16179A268 (81)

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ES-401, Page 47 of 50 ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet U. S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name: Date: Facility / Unit Region: I II III IV Reactor Type:

W CE BW GE Start Time:

Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins Applicant Certification

All work done on this examination is my own. I hav e neither given nor received aid.

_______________________________

Applicant's Signature Results Examination Value

________ Points Applicant's Score

________ Points Applicant's Gra de ________ Percent

2016 V.C. Summer Initial Written Examination Class 14-01 Name _______________________________________

Date ______________________

1. 26. 5 1. 2. 27. 5 2. 3. 28. 5 3. 4. 29. 5 4. 5. 30. 5 5. 6. 3 1. 5 6. 7. 3 2. 5 7. 8. 3 3. 5 8. 9. 3 4. 5 9. 10. 3 5. 6 0. 1 1. 3 6. 6 1. 1 2. 3 7. 6 2. 1 3. 3 8. 6 3. 1 4. 3 9. 6 4. 1 5. 4 0. 6 5. 1 6. 4 1. 6 6. 1 7. 4 2. 6 7. 1 8. 4 3. 6 8. 1 9. 4 4. 6 9. 20. 4 5. 7 0. 21. 4 6. 71. 22. 4 7. 72. 23. 4 8. 73. 24. 4 9. 74. 25. 5 0. 75.

Name: _____________

___________________ 14-01 NRC written

Form: 0 Version: 0

1. Given the following plant conditions:

• 100% Power.

• Reactor trip occurs.

• One (1) control rod is stuck at 220 steps.

• ALL other control rods indicate 0 steps.

• T AVG 557°F and stable.Which ONE of the choices below completes the following statements?Ten (10) minutes after the trip, shutdown margin is ____(1)____ ; For the conditions above, operators __(2)__ be required to borate using MVT-8104,EMERG BORATE in accordance with EOP-1.1, ES-0.1, REACTOR TRIP RESPONSE.

1) increasing2) will1) increasing 2) will not1) decreasing2) will1) decreasing2) will not A.B.C.D.

14-01 NRC written

2. Given the following plant conditions:

• PCV-445A PWR RELIEF has failed partially open.

• Reactor trip and Safety Injection (SI) occurred.

• RCS pressure is 1700 psig and decreasing.

• T AVG is 550°F and decreasing. * "A" Charging pump is running. * "B" Charging pump failed to start manually or automatically.

• Pressurizer level is 32% and increasing at 7%/minute.

• All steam generator levels are 50% and stable.Which ONE of the choices below completes the following statements?In accordance with EOP-1.2 ES-1.1 SAFETY INJECTION TERMINATION, operators___(1)___ terminate SI in the current plant condition.When operators are restoring normal charging, EOP-1.2 will require ___(2)___ to beclosed.1) cannot2) either MVG-8801A or MVG-8801B, HI HEAD TO COLD LEG INJ1) cannot2) both MVG-8801A and MVG-8801B, HI HEAD TO COLD LEG INJ

1) can2) either MVG-8801A or MVG-8801B, HI HEAD TO COLD LEG INJ

1) can2) both MVG-8801A and MVG-8801B, HI HEAD TO COLD LEG INJ A.B.C.D.

14-01 NRC written

3. Given the following plant conditions:Time 1400:

• A Small break LOCA has occurred.

• Safety injection has actuated. * "A" and "B" Charging pumps started automatically then tripped

.Time 1425:

• EOP-2.0, LOSS OF REACTOR OR SECONDARY COOLANT is in progress. * "A" and "B" Charging pumps are still tripped.

• RB pressure is 12.5 psig and rising.

• RCS pressure is 1400 psig and decreasing.

• The crew tripped all Reactor Coolant Pumps (RCPs).Which ONE of the following identifies the reason that operators tripped the RCPs?Reduces heat input into the RCS.

Prevents damage to RCP motor bearings.

Conserves inventory by reducing the flow of coolant from the break.

Saves RCPs for future starts in degraded core cooling procedures.

A.B.C.D.

14-01 NRC written

4. Initial conditions:* 100% Power

• "A" CCW train is the active loop.

• "B" CCW pump inoperable.* "C" CCW pump aligned to "B" train.Final conditions:* Large break LOCA occurred.

• EOP-2.2, TRANSFER TO COLD LEG RECIRCULATION in progress.

• Operators are reading EOP-2.2 step 13, "Shift the CCW Train to fast speed inthe Active Loop. REFER TO SOP-118, COMPONENT COOLING WATER."Which ONE of the choices below completes the following statement?The active loop CCW train will be _________ kept in slow speed to prevent damage to the RHR pump on that train.

kept in slow speed to prevent damage to the Charging pump on that train.

shifted to fast speed to provide cooling for non-essential loads.shifted to fast speed to provide additional cooling for an RHR heat exchanger.

A.B.C.D.

14-01 NRC written

5. Which ONE of the following identifies a condition that would require the immediate tripof the affected reactor coolant pump?Pump frame vibration of 4 mils and stable.

Pump shaft vibration of 8 mils and increasing.

Motor stator temperature of 312°F and increasing.

Lower seal water bearing temperature 190°F and increasing.

A.B.C.D.

14-01 NRC written

6. Given the following plant conditions:Time 0600:

• 100% power.

• T AVG is stable on program.

• PZR LEVEL CNTRL is selected to 459 + 460.

• PVT-8149A, LTDN ORIFICE A ISOL is open.

• PVT-8149B, LTDN ORIFICE B ISOL is open.

• PVT-8149C, LTDN ORIFICE C ISOL is closed.

• FI-122A, CHG FLOW GPM, reads 90 gpm and stable. Time 0605:

• FI-122A, CHG FLOW GPM, decreases to 15 gpm and stabilizes.Time 0606:

• PVT-8149B, LTDN ORIFICE B fails closed.Which ONE of the choices below answers both of the following questions:The flow value, as read on FI-122A, at time 0605 can be caused by pressurizer leveltransmitter __(1) __ failing high.At time 0606 pressurizer level is __(2)__.ASSUME NO OPERATOR ACTIONS1) LT-459 2) Increasing. 1) LT-4592) Decreasing.

1) LT-4602) Increasing.1) LT-4602) Decreasing.

A.B.C.D.

14-01 NRC written

7. Given the following plant conditions:

• A Large break LOCA has occurred.

• RM-G7/18 - CNTMT HI RNG GAMMA are in alarm.

• All other radiation monitor readings are normal.

• RHR A(B) LEVEL FEET, LI-1969/ 1970 read 413 feet and increasing.

• RWST LEVEL %, LI-990/992 read 17% and decreasing.Which ONE of the following identifies a condition that is present as indicated by theinstrument readings above?Reactor coolant is being lost outside of the RB.RWST level is above the level at which automatic recirculation realignment occurs.ECCS Pump suction requirements are not met for recirculation.Vital equipment required for accident mitigation in the RB is submerged.

A.B.C.D.

14-01 NRC written

8. Given the following plant conditions:Time 1700:* Mode 4* RHR Train "B" running in the shutdown cooling mode.* "A" CCW loop is active.

• "A" CCW pump has tripped.

• XCP-601, 1-2, CCP A/C AUTOSTART FAIL.

• "A" Charging pump in service.

• AOP-118.1, LOSS OF COMPONENT COOLING WATER is in progress.* Component temperatures are being monitored in the Control Room only.Which ONE of the following identifies the earliest time at which a pump must bestopped in accordance with AOP-118.1?Stop "A" Charging pump at 1720.

Stop "A" Charging pump at 1830.

Stop "B" RHR pump at 1720.

Stop "B" RHR pump at 1830.

A.B.C.D.

14-01 NRC written

9. Initial conditions:* 100% power initially.

• Reactor Protection System testing was in progress.

• A small break LOCA occurred.* The NROATC reported an ATWS during Immediate Actions.Current conditions:* Reactor Trip Bypass Breaker "B" is racked-in , closed and will not open locally.* All other reactor trip breakers are OPEN.* EOP-2.0, LOSS OF REACTOR OR SECONDARY COOLANT in progress.

• Operators are attempting to reset Safety Injection (SI).Which ONE of the choices below completes the following statement, given theconditions above?__(1)__ and can be reset from the Main Control Board.Condenser steam dumps __(2)__ armed.1) only one (1) train of SI2) are1) only one (1) train of SI2) are not1) both trains of SI2) are1) both trains of SI2) are not A.B.C.D.

14-01 NRC written

10. Initial conditions:

• 100% power. * "A" EDG is inoperable

.Current conditions:

• A tube rupture on "A" Steam Generator occurred.

• Reactor Trip and Safety Injection occurred.

• 230 KV offsite power has been lost.

• EOP-4.0, E-3 STEAM GENERATOR TUBE RUPTURE is in progress.Which ONE of the choices identifies an effect of the loss of 230 KV power as actionsare taken in EOP-4.0? The RCS cooldown rate will be restricted to 50°F/hr. The RCS depressurization will take longer to complete.The RCS cooldown rate will not be restricted but will take longer to complete.The RCS depressurization may have to be stopped prior to terminating SI due tovoiding in the reactor core.

A.B.C.D.

14-01 NRC written

11. Given the following plant conditions:Time 1000:* 45% power initially.

• A steam leak begins on "B" Main Steam line.* "B" NR Steam Generator rose to 70% and then began to decrease.Time 1001:* Operators manually tripped the reactor.Time 1002:* XCP 615, 1-2, RCS TAVG LO goes into alarm.Time 1003:* XCP 615, 1-3, RCS TAVG LO-LO goes into alarm.Which ONE of the following identifies the earliest time stated above at which aFeedwater Isolation actuation occurred?

1000 1001 1002 1003 A.B.C.D.

14-01 NRC written

12. Given the following plant conditions:Time 1100:

• 35% power, plant startup is in progress. * "B", "C" and "D" Feedwater Booster pumps are running. * "A" and "B" Feedwater pumps are operating.Time 1105:

• XCP-639, 2-2, BUS 1C O/C 51BX-1C comes into alarm.Time 1106:

• BOP reports that "B" Feedwater Booster pump has tripped.Which ONE of the following identifies the time at which a manual Reactor Trip wasrequired?1105 because an ATWS has occurred.

1105 because there is only one (1) Feedwater Booster pump running.

1106 because there is only one (1) Feedwater Booster pump running.1106 because there are no Feedwater Booster pumps running.

A.B.C.D.

14-01 NRC written

13. Given the following plant conditions:

• A loss of offsite power (115 KV and 230 KV) occurred.

• The reactor is tripped.

• EOP-1.0, E-0, REACTOR TRIP OR SAFETY INJECTION in progress.

• Operators are reading step 9, "Check RCS temperature."Which ONE of the choices below completes the following statement in accordance withEOP-1.0?Given the conditions above, EOP-1.0, step 9 will have operators check to ensure that__(1)__ is trending toward __(2)__ to ensure that automatic controls are controllingproperly.1) T AVG2) 557°F.

1) T COLD2) 557°F.

1) T AVG2) 564°F.

1) T COLD2) 564°F.

A.B.C.D.

14-01 NRC written

14. Given the following plant conditions;* 100% power

• A failure of internal regulator circuitry on Inverter XIT-5901 occurred.

• The XIT-5901 static switch failed to automatically transfer.* APN-5901 is deenergized.* All other equipment is OPERABLE.Which ONE of the choices completes the following statement?To restore power to APN-5901 using a path that is not routed through the static switch,the operator will take the _____.TEST TRANSFER Switch to ALT.

MAN BYP Switch to PREF - ISOLATE.

MAN BYP Switch to BYP to ALT.

MAN BYP Switch to BYP to ALT - ISOLATE.

A.B.C.D.

14-01 NRC written

15. Given the following plant conditions:Time 0900:

• 100% power. * "C" Service Water pump breaker was inoperable

.

• A loss of offsite power (115 KV and 230 KV) occurred.

• "A" and "B" Service Water pump breakers tripped and cannot be reclosed.

• Operators entered AOP-117.1, LOSS OF SERVICE WATER.Time 0910:

• XCP-636, DGA ENG TEMP TRBL is in alarm.

• An AO reports a jacket water temperature of 193°F and rising.

• System controller reports that power will not be available for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.Which ONE of the choices below answers both of the following questions:1) Will the diesel cooling system design provide automatic initiation of Fire Servicecooling if operators take no action?2) How will diesel be operated after Fire Service cooling is established in accordancewith AOP-117.1?1) Yes.2) Operated up to the full rated load capacity because Fire Service cooling willprovide adequate cooling at the rated load.1) Yes.2) Operated at a reduced load capacity because Fire Service cooling will notprovide adequate cooling at the rated load.1) No.2) Operated up to the full rated load capacity because Fire Service cooling willprovide adequate cooling at the rated load.1) No.2) Operated at a reduced load capacity because Fire Service cooling will notprovide adequate cooling at the rated load.

A.B.C.D.

14-01 NRC written

16. Given the following plant conditions:

• 5% power initially.

• Plant Startup was in progress.

• The following alarms were received in the control room: - XCP-607, 2-5, INSTR AIR PRESS LO FLOW HI - XCP-607, 2-6, SERV AIR PRESS LO

• Instrument Air pressure is now 75 psig and decreasing.

• AOP-220.1, LOSS OF INSTRUMENT AIR has been entered.

• An AO has been sent to investigate.Which ONE of the choices below answers both of the following questions?1) What is the event that caused the indications above?2) What is a condition that requires a reactor trip, in accordance with AOP-220.1?1) The operating Instrument Air Compressor has tripped. 2) Instrument Air header pressure decreases to 60 psig.1) The operating Instrument Air Compressor has tripped. 2) An MSIV indicates off it's open seat.1) A large leak exists in the Instrument Air system. 2) Instrument Air header pressure decreases to 60 psig.1) A large leak exists in the Instrument Air System. 2) An MSIV indicates off it's open seat.

A.B.C.D.

14-01 NRC written

17. Given the following plant conditions:

• 100% power.

• HMI screen indicates "LIMITING" for turbine control.

• Weather reports indicate a massive thunderstorm is approaching.

• Operators are reviewing AOP-301.1, RESPONSE TO ELECTRICAL GRIDISSUES.Which ONE of the choices below completes the following statements in accordancewith AOP-301.1?

An increase in V.C. Summer reactor power could be caused by __(1)__, as identifiedin a CAUTION statement.The value specified on the Reference Page of AOP-301.1 above which a Reactor Trip is required is ___(1)___1) Turbine control valves opening due to a decreased grid frequency.2) 100%1) Turbine control valves opening due to a decreased grid frequency.2) 101%1) a RCS flow increase due to an increase in grid frequency.2) 100%1) a RCS flow increase due to an increase in grid frequency.2) 101%A.B.C.D.

14-01 NRC written

18. Given the following plant conditions:

• 100% power initially.

• A loss of all Feedwater pumps occurred.

• Emergency Feedwater flow (EFW) cannot be established.

• EOP-15.0, FR-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK hasbeen entered.

• Steam Generator levels indicate 10% wide range level.Which ONE of the choices below answer both of the following questions in accordancewith EOP-15.0?1) Is bleed and feed cooling required in the current plant condition?2) If bleed and feed were required and only two (2) pressurizer PORVs could beopened, would Reactor Vessel Head vents also be opened?1) Yes.2) Yes.1) Yes.2) No.1) No.2) Yes.1) No.2) No.A.B.C.D.

14-01 NRC written

19. Given the following plant conditions:Time 0800:

• 45% power initially.

• A Stator coolant runback begins.Time 0801:

• XCP-621, 1-2, CRB INSRT LMT LO goes into alarm.

Time 0802:

• XCP-621, 1-1, CRB INSRT LMT LO LO goes into alarm.

• The runback stops.Which ONE of the choices below completes the following statements?___(1)___ is the earliest time that an Emergency Boration is required.It is required to ensure that ___(2)___.1) 0801 2) compliance is maintained with Technical Specification Shutdown Marginrequirements.1) 0801 2) Axial Flux Differential remains within the Technical Specification requirement.1) 08022) rods do not go below Technical Specification rod insertion limits.1) 08022) compliance with Technical Specification Shutdown Margin requirements isrestored.A.B.C.D.

14-01 NRC written

20. Given the following plant conditions:* Mode 6.

• Core reload in progress.* The personnel hatch is closed.* Reactor Building Purge is in service.* Auxiliary Building ventilation is in service.Which ONE of the choices below answers both of the following questions:The highest potential magnitude of release would occur if a __(1)__ fuel assembly isdropped in the Reactor Building.Under the conditions above, a release of noble gases from a fuel assembly dropped inthe Reactor Building __(2)__ be detected by RM-A3, MAIN PLANT VENT.1) new 2) would1) new2) would not1) spent2) would1) spent2) would not A.B.C.D.

14-01 NRC written

21. Given the following plant conditions:

• 100% power.

• Steam Generator blowdown return is aligned to the condenser.

• One tube on Steam Generator "B" has just completely ruptured.Which ONE of the choices below completes the following statement?The first alarm to indicate that a primary to secondary break has occurred will be from__(1)__ and the return of blowdown to the condensor is terminated by automatic actionprovided by __(2)__.Assume that a Reactor trip setpoint has NOT been reached

.1) RM-A9, CNDSR EXHAUST GAS ATMOS.2) RM-L7, NUCLEAR BLOWDOWN WASTE EFFLUENT LIQUID.1) RM-A9, CNDSR EXHAUST GAS ATMOS.2) RM-L3, STEAM GENERATOR BLOWDOWN LIQUID.1) RM-G19B, STMLN HI RNG GAMMA.2) RM-L7, NUCLEAR BLOWDOWN WASTE EFFLUENT LIQUID.1) RM-G19B, STMLN HI RNG GAMMA.2) RM-L3, STEAM GENERATOR BLOWDOWN LIQUID.

A.B.C.D.

14-01 NRC written

22. Which ONE of the choices below answer both of the following questions:1) What value for a containment parameter would require entry into an actionstatement in accordance with either of the following V.C. Summer TechnicalSpecifications for CONTAINMENT SYSTEMS? T.S. 3.6.1.4 - INTERNAL PRESSURE T.S. 3.6.1.5 - AIR TEMPERATURE2) Is the action required to be completed within one (1) hour?1) Negative Containment pressure of 0.3 psig (- 0.3 psig).2) Yes.1) Negative Containment pressure of 0.3 psig (- 0.3 psig).2) No.1) Containment average air temperature of 115°F.2) Yes.1) Containment average air temperature of 115°F.2) No.A.B.C.D.

14-01 NRC written

23. Given the following plant conditions:

• A small break LOCA has occurred.

• There are no ECCS pumps available.

• All RCPs are stopped.

• NR RVLIS level is 32% and decreasing.

• Core Exit TCs are 790°F and increasing.

• EOP-14.0, FR-C.1 RESPONSE TO INADEQUATE CORE COOLING is inprogress.

• Attempts to restore an ECCS injection flowpath have failed.Which ONE of the following identifies the next major action required in an attempt torestore adequate core cooling in accordance with EOP-14.0?Restart an RCP.

Open pressurizer PORVs.

Depressurize steam generators.

Open the reactor head vent valves.

A.B.C.D.

14-01 NRC written

24. Which ONE of the choices below answers both of the following questions regardingEOP-1.5, REDIAGNOSIS?1) Is a demand or actuation of Safety Injection required for using EOP-1.5,REDIAGNOSIS?2) What is a check that is performed in EOP-1.5 to diagnose an event?1) Yes.2) Check if PRT conditions are normal.1) Yes.2) Verify no SG tubes are ruptured.1) No.2) Check if PRT conditions are normal.1) No.2) Verify no SG tubes are ruptured.

A.B.C.D.

14-01 NRC written

25. Given the following plant conditions:

• A small break LOCA has occurred.

• Condenser pressure is 6" Hg.

• All Circulating Water pumps are running.

• RCS pressure is 1100 psig and stable. * "A" Charging pump is running with lower than normal amperage. * "B" Charging pump is OFF.

• Core Exit TCs are 570°F and rising.

• The crew is performing actions contained in EOP-2.1, ES-1.2 POST- LOCACOOLDOWN AND DEPRESSURIZATION.Which ONE of the following describes the method and rate at which the RCS cooldownwill occur in accordance with EOP-2.1?Condenser steam dumps will be used at the maximum achievable rate. RCScooldown rate limits do not apply for this condition.Condenser steam dumps will be used at less than 100°F per hour cooldown rate.S/G PORVs will be used at the maximum achievable rate. RCS cooldown ratelimits do not apply for this condition.S/G PORVs will be used at less than 100°F per hour cooldown rate.

A.B.C.D.

14-01 NRC written

26. Given the following plant conditions:

• 100% power initially.

• A reactor trip occurred.

• Steam dumps failed to operate.

• Steam Generator Safety valves failed to operate.

• All Steam Generator Pressures are at 1235 psig.

• A YELLOW status is indicated on IPCS for HEAT SINK.

• EOP-1.1, ES-0.1 REACTOR TRIP RESPONSE, step 1 is in progress.Which ONE of the choices completes the following statements in accordance withOAP-103.4 EOP/FSP/AOP USER'S GUIDE?EOP-15.1, STEAM GENERATOR OVERPRESSURE __(1)__ allowed to be used inthe current condition.The CRS __(2)__ required to enter EOP-15.1 when the use of YELLOW pathprocedures is allowed by OAP-103.4.1) is2) is1) is2) is not1) is not2) is1) is not2) is not A.B.C.D.

14-01 NRC written

27. Initial conditions:

• A small break LOCA occurred.

• Charging pumps failed to start manually or automatically.

• Indications of inadequate core cooling were present.Current conditions:

• Charging pump capability has been restored.

• EOP-2.1, ES-1.2 POST-LOCA COOLDOWN AND DEPRESSURIZATION inprogress.

• RB pressure is 3 psig and decreasing.

• Integrated dose for RB Radiation is 200,000 Rads. * "A" Charging pump has just been stopped in accordance with EOP-2.1.Which ONE of the choices completes the following statement?The SI Re-initiation Criteria for the current conditions, as specifically stated on theEOP-2.1 Reference Page, is either a subcooling value less than __(1)__ or a PZR levelless than __(2)__.1) 52.5°F2) 10%.1) 52.5°F2) 28%.1) 67.5°F2) 10%.1) 67.5°F2) 28%.A.B.C.D.

14-01 NRC written

28. Initial conditions:

• 100% power.

• Alternate Seal Injection is out of service.

• The meter deflection on the HCV-186 INJ FLOW control is at 100%.Current condition:

• The meter deflection on the HCV-186 INJ FLOW control is at 0%.Which ONE of the choices below answers both of the following questions:1) How has Seal Injection flow changed due to the change in the position of HCV-186?2) What is the minimum adjustment that will restore Seal Injection flow to within theallowed range in accordance with SOP-101, REACTOR COOLANT SYSTEM.1) Flow has increased.2) Lower to less than the maximum allowed value of 13 gpm.1) Flow has increased.2) Lower to less than the maximum allowed value of 10 gpm.1) Flow has decreased.2) Raise to more than the minimum allowed value of 8 gpm.1) Flow has decreased.2) Raise to more than the minimum allowed value of 6 gpm.

A.B.C.D.

14-01 NRC written

29. Given the following plant conditions:

• 100% power.

• "A" CCW train is the active loop.

• All CCW pumps are OPERABLE.Which ONE of the following events would require tripping of all Reactor Coolant Pumps the soonest?Closure of MVB-9524B/9526B, LP B NON-ESSEN LOAD ISOL.Closure of MVG-9600, TO THERM BARR ISOL.

Closure of MVG-9568, TO RB LOAD.

Trip of "A" CCW pump.

A.B.C.D.

14-01 NRC written

30. Initial conditions:

• 100% power.

• "A" Charging pump is running.

Current conditions: * "A" Charging pump tripped.Which ONE of the choices below completes the following statements?For the first 30 seconds after the Charging Pump trip, RCP seal cooling __(1)__ beprovided.After 30 seconds, RCP seal injection will automatically be reestablished using waterfrom the __(2)__.ASSUME NO OPERATOR ACTIONS1) will not2) RWST.1) will not2) VCT.1) will2) RWST.1) will 2) VCT.A.B.C.D.

14-01 NRC written

31. Given the following plant conditions:

• Plant is shut down with a cooldown in progress. * "A" RHR train is in service.

• "B" RHR pump switch is in PULL TO LK NON-A. * "A" RCP is running.

• All Steam Generator NR levels are at 60% and stable.

• XCP-610, 2-5, RCS TEMP LO AND RHR SUCT VLV NOT OPEN is in alarm.

• Operators verified that "A" RHR train valves are in the normal alignment.Which ONE of the choices below completes the following statements?This alarm could be caused by ___(1)___ being partially closed.Technical Specifications that protect against ___(2)___ are not fully met.1) MVG-8809B, RWST TO RHR PP B2) RCS failures near the Nil Ductility Temperature1) MVG-8809B, RWST TO RHR PP B2) loss of heat removal capability during Mode 4 conditions1) MVG-8702B, RCS LP C TO PUMP B2) RCS failures near the Nil Ductility Temperature1) MVG-8702B, RCS LP C TO PUMP B2) loss of heat removal capability during Mode 4 conditions A.B.C.D.

14-01 NRC written

32. Given the following plant conditions:Time 0100:

• A large-break LOCA occurred.

• XCP-612, 4-3, RWST LVL LO-LO XFER TO SUMP is in alarm.Time 0101:

• The CRS begins reading step 1 of EOP-2.2, ES-1.3 TRANSFER TO COLD LEGRECIRCULATION.Which ONE of the choices below completes the following statements?

At time 0101, Charging Pump suctions are supplied from the __(1)__.When the actions of EOP-2.2 are complete, Charging Pump miniflow line valveMVG-8106, CHG PP will be __(2)__.1) RWST.2) open. 1) RWST.2) closed.1) RHR pump discharge.2) open. 1) RHR pump discharge.2) closed.

A.B.C.D.

14-01 NRC written

33. Given the following plant conditions:

• 100% power initially.

• A faulted steam generator occurred.

• Both Charging pumps are running in injection mode.

• RCS pressure lowered to 1520 psig and then steadily incr eased to the currentvalue of 2300 psig.Which ONE of the choices below completes the following statements?PRT level is increasing because there is coolant flowing from a _____ . Pressurizer Code Safety valve.relief valve on the RHR pump suction.

relief valve on the normal letdown line.

relief valve on the Seal Return line.

A.B.C.D.

14-01 NRC written

34. Given the following plant conditions:Time 1700:

• 100% power.

• VCT level is 35% and stable.

• PVT-8149A, LTDN ORIFICE A ISOL and PVT-8149B, LTDN ORIFICE B ISOLare open.

• PVT-8149C, LTDN ORIFICE C ISOL is closed.Time 1715:

• Operator realigned the valves above in accordance with SOP-102, CHEMICALAND VOLUME CONTROL SYSTEM as follows: - PVT-8149B, LTDN ORIFICE B ISOL and PVT-8149C, LTDN ORIFICE CISOL are now open. - PVT-8149A, LTDN ORIFICE A ISOL is now closed.Time now 1730.Which ONE of the choices below identifies a change in a system parameter thatoccurred as a result of realigning valves to the current condition?Assume all parameters are stable at the current conditions

.Cooling flow through the Letdown Heat Exchanger is higher.Regenerative Heat Exchanger outlet temperature is lower.Flow through the normal letdown line is lower.

VCT level is lower.

A.B.C.D.

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35. Given the following plant conditions:

• Time 1300.

• Plant startup in progress using GOP-2, PLANT STARTUP AND HEATUP(MODE 5 TO MODE 3). * "B" RHR Train is in service.

• "A" RCP is running.

• A loss of Component Cooling Water occursWhich ONE of the following identifies the earliest time at which the trip of a componentis required in accordance with AOP-118.1, LOSS OF COMPONENT COOLINGWATER?Assume CCW is not restored

."A" RCP at 1310.

"A" RCP at 1320.

"B" RHR pump at 1320."B" RHR pump at 1330.

A.B.C.D.

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36. Given the following plant conditions:

• 75% power and stable.

• The T AVG input to the Master Level Controller fails promptly to a value of 557°F.Which ONE of the choices below completes the following statements?XCP-616, 1-5, PZR LCS DEV HI/LO __(1)__ in alarm.As a result of this malfunction, __(2)__

automatically. 1) is2) FCV-122, CHG FLOW opened further1) is.2) Pressurizer backup heaters energized1) is not2) FCV-122, CHG FLOW opened further1) is not2) Pressurizer backup heaters energized A.B.C.D.

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37. Given the following plant conditions:

• 100% power.

• Power range channel N-43 has failed high.

• I&C reports that the channel will take a week to repair due to the lack of areplacement part.Which ONE of the following identifies a set of actions that will be required inaccordance with AOP-401.10, POWER RANGE CHANNEL FAILURE?The ROD CNTRL BANK SEL Switch will be __(1)__ . Tripping of an Overtemperature T bistable __(2)__ be required.1) taken to MAN 2) will not1) taken to MAN 2) will1) left in AUTO2) will not1) left in AUTO2) will A.B.C.D.

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38. Given the following plant conditions:

• A plant load reduction is in progress.

• Turbine First Stage Pressure Channel, PT-446, sticks at 50% of range.

• Reactor power is currently 25%.Which ONE of the choices below completes the following statements?RPS permissive __(1)__ for this reactor power.In this condition, a minimum of __(2)__ RCP(s) tripped will cause a Reactor Trip onlow RCS flow.

1) P-7 is in its proper condition2) one (1)1) P-7 is in its proper condition2) two (2)1) P-7 is not in its proper condition2) two (2)1) P-8 is not in its proper condition2) one (1)

A.B.C.D.

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39. Which ONE of the following identifies the power supply to "B" Train Engineered SafetyFeatures Loading Sequencer?APN-5902 APN-5903APN01DB2 DPN-1HB1 A.B.C.D.

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40. Given the following plant conditions:

• 100% power.

• PT-951, Reactor Building Pressure Channel, has failed HIGH.Which ONE of the choices below completes the following statements?1) When the PT-951 bistable associated with HIGH-1 is tripped in accordance withSOP-401 REACTOR PROTECTION AND CONTROL SYSTEM it is __(1)__.2) After the HIGH-1 bistable is tripped, the logic using the remaining operable bistables that will initiate a HIGH-1 RB Pressure actuation is 1 out of __(2)__.1) energized.2) 2.1) energized.2) 3.1) deenergized.2) 2.1) deenergized.2) 3. A.B.C.D.

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41. Initial conditions:

• 100% power.

• The following Reactor Building Cooling Units are running in NORM: - XFN0064A-AH - XFN0064B-AH - XFN0065B-AH

• RBCU TRAIN A EMERG is in XFN-64A.

• RBCU TRAIN B EMERG is in XFN-65B.

Current conditions:

• A large break LOCA occurs.Which ONE of the following describes the operation of the RBCUs for theseconditions?XFN-64B stops;XFN0064A-AH and XFN0065B-AH remain running.Cooling water swaps to Service Water for all RBCUs. XFN-64B stops;XFN0064A-AH and XFN0065B-AH remain running.Cooling water swaps to Service Water for running RBCUs only.All RBCUs stop;XFN0064A-AH and XFN0065B-AH start.Cooling water swaps to Service Water for all RBCUs. All RBCUs stop;XFN0064A-AH and XFN0065B-AH start.Cooling water swaps to Service Water for running RBCUs only. A.B.C.D.

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42. Given the following plant conditions:

• 100% power initially.

• A LOCA event is in progress.

• The HI-3 signal actuation failed to occur automatically at the required setpoint.

• The following timeline of actions and events occur:

0700 - XCP-626, 5-1, PZR SI is in alarm. 0701 - RB pressure is 4 psig, increasing.

0705 - RB pressure is 14 psig, increasing. 0706 - RB spray is manually actuated. 0715 - SI is RESET.

0716 - Phase A isolation is RESET.

0717 - Phase B isolation is RESET.

0718 - RB Spray is RESET.Which ONE of the choices below completes the following statements?A demand signal for MVG-3003A(B), SPRAY HDR ISOL LOOP A(B) to open firstoccurred at time __(1)__.The actuation system circuit logic to allow closure of these valves was first satisfiedat time __(2)__.1) 07002) 07161) 07012) 0716

1) 07062) 07171) 07062) 0718 A.B.C.D.

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43. Initial conditions:

• A small break LOCA has occurred.

• EOP-2.1, ES-1.2 POST- LOCA COOLDOWN AND DEPRESSURIZATION is inprogress.

• Steam generator pressures are 825 psig and lowering at 1 psig/ second.Current conditions:

• Operators are preparing to begin a RCS cooldown.

• Steam generator pressures are 500 psig and dropping at 10 psig/sec.

• RB pressure is 15 psig and increasing.Which ONE of the choices below completes the following statement?In accordance with EOP-2.1, operators will ________.transition to EOP-3.0, E-2 FAULTED STEAM GENERATOR ISOLATION.

transition to EOP-3.1, ECA-2.1 UNCONTROLLED DEPRESSURIZATION OF ALLSTEAM GENERATORS.transition to EOP-2.0, LOSS OF REACTOR OR SECONDARY COOLANT.ensure MSIVs are closed and remain in EOP-2.1.

A.B.C.D.

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44. Given the following plant conditions:

• 100% power initially.

• The reactor tripped automatically.

• EOP-1.0, E-0 REACTOR TRIP OR SAFETY INJECTION is in progress.

• RB pressure has steadily increased to the current value of 5.5 psig.

• Steam Generator pressures have steadily decreased to the following values: "A" 650 psig.

"B" 670 psig.

"C" 670 psig.Which ONE of the following describes the status of the Phase B isolation and MainSteamline Isolation actuation signals?Neither signal has actuated. Only Phase B isolation has actuated.Only Main Steamline isolation has actuated.

Both signals have actuated.

A.B.C.D.

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45. Initial conditions:

• Plant power escalation was in progress. * "A" S/G Feedwater Flow Control Valve (PVT-478) will not move from it's current position automatically or manually from the Main Control Board. * "A" S/G level is 57% and decreasing. * "B" and "C" S/G levels are 61% and stable.

• Power is 35% and stable.

Current conditions:

• AOP-210.1, FEEDWATER FLOW CONTROL VALVE FAILURE in progress.

• Operators are attempting to stabilize "A" SG level. * "A" S/G level is 52% and decreasing.

• All SG pressures are 1000 psig.Which ONE of the choices below completes the following statements?The immediate actions of AOP-210.1, will allow operators to raise Feedwater pumpspeed until a maximum Feedwater pump pressure of __(1)__ is reached and willdirect operators to __(2)__ if necessary.1) 1250 psig2) open FCV-3321, LOOP A MAIN FW BYPASS from the Control Board.1) 1250 psig2) dispatch an AO to locally operate PVT-478, SG A FWF.1) 1600 psig2) open FCV-3321, LOOP A MAIN FW BYPASS from the Control Board.1) 1600 psig2) dispatch an AO to locally operate PVT-478, SG A FWF.

A.B.C.D.

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46. Given the following plant conditions:Time 10:00* 8% power.

• "A" Feedwater pump running. * "B" and "C" Feedwater pumps TRIP/RESET switches indicate TRIP.* Turbine-driven EFW pump is OFF.

• "A" and "B" MD EFW Pumps are in NORMAL AFTER STOP.* Hand Controllers IFV-3531(3541)(3551), MD EFP TO SG A(B)(C) are at 0% andindicate full closed.* Flow Control Valve Switches FCV-3531(3541)(3551), MD EFP TO SG A(B)(C)are in MANUAL

.Time 10:02* "A" Feedwater pump has tripped.* Steam Generator narrow range levels are at 45%, lowering.Which ONE of the following describes the condition of components associated with theMotor-driven (MD) EFW pumps?Assume no operator actions."A" and "B" MD EFW Pumps are running; FCV-3531(3541)(3551) are closed."A" and "B" MD EFW Pumps are running; FCV-3531(3541)(3551) are 100% open."A" and "B" MD EFW Pumps are off.FCV-3531(3541)(3551) are closed."A" and "B" MD EFW Pumps are off.FCV-3531(3541)(3551) are 100% open.

A.B.C.D.

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47. Given the following plant conditions:

• A partial loss of off-site power occurred.

• "A" EDG is supplying bus 1DA.

• No other power source can be restored.

• The Shift Manager has directed that a maximum limit of 4676 KW be strictlyobserved on bus 1DA.Which ONE of the choices below completes the following statement?In order to prevent failure of the "A" EDG, bus 1DA can be loaded to a maximum of4676 KW _____, in accordance with SOP-306, EMERGENCY DIESEL GENERATOR.continuously without limits on duration. for one 7-day period only.for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> out of every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the next year only.for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> out of every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the next year or for one 7-day period.

A.B.C.D.

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48. Given the following plant conditions;

• 20% powerWhich ONE of the following would require, if it were isolated, entry into an actionstatement of T.S. 3.8.1.1. AC SOURCES until the component is restored toservice?Assume no plant modifications or temporary cabling

.XTF005, UNIT 2 ENGINEERED SAFEGUARD TRANSFORMER.

XTF0031, EMERGENCY AUXILIARY TRANSFORMER #1.

XTF5052, ALTERNATE AC SOURCE TRANSFORMER.

230 KV switchyard Bus 2.

A.B.C.D.

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49. Given the following plant conditions:Time 1400:

• A loss of all offsite power (115 KV and 230 KV) has occurred. * "A" and "B" EDGs failed to start.

• EOP-6.0, ECA-0.0 LOSS OF ALL ESF AC POWER is in progress.Which ONE of the choices below completes the following statement?In accordance with V.C. Summer design basis, at time 1800, the minimum terminalvoltage that can be expected on batteries XBA1A and XBA1B is __(1)__.EOP-6.0 __(2)__ contain actions to shed non-safety related DC loads.1) 108 VDC.2) does1) 108 VDC.2) does not1) 110 VDC.2) does1) 110 VDC.2) does not A.B.C.D.

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50. Given the following plant conditions:Time 0700:

• 100% power initially.

• MAIN XFMR FEED XCB 8902 opens spuriously. * "A" RCP tripped.

• NROATC reports both reactor trip breakers are closed.Time 0702:

• XTF-31 transformer lockout occurs.

• 51BX-1DA lockout occurs. * "B" EDG fails to start automatically or manually.Which ONE of the following describes an Immediate Action that is contained in theprocedure that will be implemented at time 0702?Verify the reactor is tripped.EOP-13.0, FR-S.1 RESPONSE TO ABNORMAL NUCLEAR POWER GENERATION.Trip the Main turbine.EOP-13.0, FR-S.1 RESPONSE TO ABNORMAL NUCLEAR POWER GENERATION.Trip the Main turbine.EOP-6.0, ECA-0.0 LOSS OF ALL ESF AC POWER.Restore power to any ESF bus.EOP-6.0, ECA-0.0 LOSS OF ALL ESF AC POWER.

A.B.C.D.

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51. Which ONE of the following sets of valves will re-position as indicated on a sensed HiRadiation signal generated by detector RM-L3, STEAM GENERATOR BLOWDOWN LIQUID MONITOR?PVT-524, TO CW will close.PVG-525, DIVERT TO NB will open.PVT-524, TO CW will close.PVG-525, DIVERT TO NB will close.PVD-6121, NUC BLOWDOWN DISCHARGE will close.PVG-525, DIVERT TO NB will close.PVD-6121, NUC BLOWDOWN DISCHARGE will close.PVG-525, DIVERT TO NB will open.

A.B.C.D.

14-01 NRC written52. Which ONE of the following describes the buses that directly supply power to the "B"CCW pump and the "B" Component Cooling Water Booster Pump?

"B" CCW "B" CCWBP 1DB 1B2X 1DB 1DB2X 1DB1 1B2X 1DB1 1DB2X A.B.C.D.

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53. Given the following plant conditions:* Refueling is in progress.

• TBCCC has been taken out of service.

• The Supplemental Air Compressor is running supplying breathing air.Which ONE of the following identifies a supply of Station Instrument Air that can beused in these conditions in accordance with SOP-220, STATION AND BACKUPINSTRUMENT AIR SYSTEMS?Instrument air compressor "B" using backup cooling supplied from Raw Water.Diesel air compressor with pressure control se lected to "ONBOARD".Reactor Building air compressors through XVA-2659, RB INSTRUMENT AIRBACK-UP SUP ISOL VLV.Supplemental instrument air compressor through XVB02633-IA IN BACKUPSYSTEM SUP HDR ISOLATION VLV.

A.B.C.D.

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54. Which ONE of the following describes the normal position of SVX-9364B RCS LOOP BSAMPLE HEADER ISOLATION VLV and which ESF function closes this valve?Normally open and receives a CLOSE signal on phase ANormally open and receives a CLOSE signal on phase BNormally closed and receives a CLOSE signal on phase ANormally closed and receives a CLOSE signal on phase B A.B.C.D.

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55. Given the following plant conditions:

• A LOCA has occurred.

• The operating crew has entered EOP-17.1, RESPONSE TO REACTORBUILDING FLOODING.Which ONE of the following describes the method that will be used to evaluate forleakage from Service Water to the Reactor Building?Compare flow indication from each SW Booster Pump discharge to that pumpsreturn flow to the pond.Compare "A" SW Booster pump flow and pressure to "B" SW Booster pump flowand pressure.Isolate Service Water to one (1) RBCU train and monitor the rate of sump increase.Verify indications for Service Water flow to all individual loads are normal.

A.B.C.D.

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56. The following plant conditions exist:

• 100% power.

• The Master Pressure Controller is in AUTO.

• Power has been lost to Pressurizer pressure transmitter PT-444.Which ONE of the following describes the condition that will occur if power to PT-444 isnot restored?Assume no operator actions

.The reactor will trip on high pressurizer pressure.

The pressurizer spray valves will open to maintain RCS pressure.

Two pressurizer PORVs will cycle to maintain RCS pressure.

The reactor will trip on low pressurizer pressure.

A.B.C.D.

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57. Given the following plant condition:Time 0500:

• The reactor at 100% power at End of Life and stable.

• XCP-620, 5-1, ROD CNTRL SYS FAIL URGENT is in alarm.

• AXIAL FLUX DIFFERENCE (AFD) indications are as follows. N-41 +4 N-42 +4 N-43 +4 N-44 +4Time 0501:

• A Main Turbine runback begins.Time 0502:

• The Main Turbine runback stopped.

• Power is at 95% and stable.

• AFD indications are now as follows:

N-41 +7 N-42 +7N-43 +7 N-44 +7Which ONE of the following completes the following statement?Over the next 10 minutes, changes in __(1)__ will directly cause AFD to change.During that time AFD will trend in the __(2)__ direction.Assume no operator actions1) Xenon 2) positive1) Xenon2) negative

1) Iodine2) positive

1) Iodine2) negative A.B.C.D.

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58. Given the following plant conditions:

• 100% power.

• Pressurizer Level Control Channel Selector switch is in the "459 + 460" position. Which ONE of the choices below answers both of the following:1)Which level channel will eventually cause a reactor trip with no operator action if itfails both high or low?2)Do LT-459 and LT-460 both serve as Reactor Trip protection channels?1) LT-4592) Yes.1) LT-4592) No.1) LT-4602) Yes.1) LT-4602) No.A.B.C.D.

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59. Given the following plant conditions:Time 0300:

• The plant is in a refueling outage.

• The core off-load has just been completed.

• The spent fuel pool temperature is 102°F.Time 0305

• A loss of all offsite power (115KV and 230 KV) has occurred.

• Both EDGs failed to start.In accordance with a note in AOP-123.4, LOSS OF SPENT FUEL COOLING, the maximum expected heatup rate in the Spent Fuel Pool for the condition above is __(1)__.One Spent Fuel Cooling pump can be started from it's normally aligned source ofpower if either bus __(2)__ is restored, 1) 3°F/hr.2) 1DA or 1DB1) 3°F/hr.2) 1A or 1B1) 20°F/hr.2) 1DA or 1DB1) 20°F/hr.2) 1A or 1B A.B.C.D.

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60. Given the following plant conditions:

• Mode 6.

• Reactor cavity is at the normal level for refueling.

• Fuel Transfer Tube is open.

• The equipment hatch is open.

• Reactor Building Purge is in progress. - XFN-11A, SPLY FAN A is running. - XFN-11B, SPLY FAN B is OFF.

- XFN-13A, EXH FAN A is running.

- XFN-13B, EXH FAN B is running.Which ONE of the following identifies an action that would cause Reactor Cavity level to decrease?Closing the equipment hatch.Stopping XFN-11A.

Stopping XFN-13A.

Starting XFN-20, FUEL BLDG SPLY FAN.

A.B.C.D.

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61. Given the following plant conditions:Time 0900:

• A spurious safety injection previously occurred.

• EOP-1.2, ES-1.1 SAFETY INJECTION TERMINATION is in progress.Time 0910:

• A double-ended rupture of one (1) Steam Generator u-tube occurs.

• RCS pressure is 1700 psig and decreasing.Which ONE of the choices below completes the following statement regardingoperation of the ECCS system?SI Reinitiation Criteria, as contained on the EOP-1.2 REFERENCE PAGE, are firstapplicable when __(1)__When Safety Injection is reinitiated per the REFERENCE PAGE, operators __(2)__.1) MVG-8801A(B), HI HEAD TO COLD LEG INJ are closed.2) open injection valves and start Charging pumps manually.1) MVG-8801A(B), HI HEAD TO COLD LEG INJ are closed.2) actuate Safety Injection using switches SI ACTUATION CS-CR0IB(C).1) the RHR pumps are stopped.2) open injection valves and start Charging pumps manually.1) the RHR pumps are stopped.2) actuate Safety Injection using switches SI ACTUATION CS-CR0IB(C).

A.B.C.D.

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62. Given the following plant conditions:

• A waste gas release was in progress.

• HCV-014, WASTE GAS DISCHARGE CONTROL VALVE, has tripped shut.

• XCP-644, 3-1, PLANT VENT GAS RM-A3 HI RAD in alarm.

• XCP-645, 2-3, GAS WST DISCH RM-A10 HI RAD has not alarmed during therelease.Which ONE of the choices below answers both

of the following questions:1) What condition must be satisfied prior to recommencing the release in accordancewith HPP-709, SAMPLING AND RELEASE OF RADIOACTIVE GASEOUS EFFLUENTS?2) What is the minimum control manipulation necessary to enable opening ofHCV-014?1) RM-A3 reading must decrease to pre-release background reading.2) HCV-014 selector switch

must be cycled to CLOSE, then the valve re-opened.1) A Request for Redundant Analysis must be initiated.2) HCV-014 controller

must be taken to ZERO (0), then the valve re-opened.1) A Request for Redundant Analysis must be initiated.2) HCV-014 selector switch

must be cycled to CLOSE, then the valve re-opened.1) RM-A3 reading must decrease to pre-release background reading.2) HCV-014 controller

must be taken to ZERO (0), then the valve re-opened.

A.B.C.D.

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63. Given the following plant conditions:

• Mode 6.

• RB Purge is in progress.

• The following alarms come in on XCP-644: - 1-5, RM-G17A, MANIP CRN RM-G17A HI RAD - 1-6, RM-G17A, MANIP CRN RM-G17A TRBL

• Operators have determined that the RM-G17A detector has failed high.NOTE THE FOLLOWING NUMBERS AND VALVE NAMES:1 XVB00001A-AH, REACTOR BUILDING PURGE SUPPLY ISOLATION VALVE 2 XVB00001B-AH, RB PURGE SUPPLY ISOL VALVE (IRC).3 XVB00002A-AH, REACTOR BUILDING PURGE EXHAUST ISOLATION VALVE 4 XVB00002B-AH, RB PURGE EXHAUST ISOL VALVE (IRC).Which ONE of the choices below completes the following statements?Valves __(1)__

closed as a result of the failure.When RM-G17A is removed from service in accordance with SOP-124, PROCESSAND AREA RADIATION MONITORING SYSTEM, the final position of the INTERLOCKswitch on RM-G17A will be __(2)__. 1) 1 and 3 2) ON.1) 1 and 3 2) OFF.1) 2 and 42) ON1) 2 and 42) OFF A.B.C.D.

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64. Which ONE of the choices below completes the following statement?The highest pressure, as read on PI-8386, RB AIR HDR PRESS, at which PVA-2659,INST AIR TO RB AIR SERV will open is __(1)__.93 psig 90 psig 70 psig 65 psig A.B.C.D.

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65. Given the following conditions:

• The plant was operating at 100% power.

• The Control Room (CR) is being evacuated due to a fire in the Main ControlBoard.

• FEP-4.0, CONTROL ROOM EVACUATION DUE TO A FIRE has beenimplemented by the Shift Manager. - Operators determine that immediate actions can be performed in the controlroom as necessary prior to leaving the Control Room.

• A spurious Reactor trip occurred.Which ONE of the following describes an immediate action the NROATC will performin the Control Room?Trip RCPs.Open PORV disconnect switches.

Emergency start "B" EDG.

Start "B" Motor-driven EFW pump.

A.B.C.D.

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66. Initial conditions:* 100% power initially.

• A Steam generator tube rupture occurred on "A" Steam Generator.Current conditions:* "B" Steam Generator was also determined to be ruptured

.* EOP-4.0, E-3 STEAM GENERATOR TUBE RUPTURE is in progress.* Operators are reading step 9 of EOP-4.0.

• Steam Generator pressures are as follows:

"A" 1050 psig "B" 950 psig "C" 950 psig* Operators have determined that there is a coincident RCS leak to the RB.* Reactor Building pressure is 2.0 psig and rising slowly.Which ONE of the choices below completes the following statement?In accordance with EOP-4.0, operators will cool the RCS to less than a maximumtemperature of ______.REFERENCE PROVIDED 482°F 469°F 466°F 453°F A.B.C.D.

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67. Which ONE of the choices below completes the following statement regarding T.S.3.4.7, CHEMISTRY?T.S. 3.4.7, CHEMISTRY __(1)__apply in Mode 5.The steady state limit for oxygen in the Reactor Coolant System is __(2)__.1) does2) 0.10 ppm1) does not2) 0.10 ppm1) does2) 0.15 ppm1) does not2) 0.15 ppm A.B.C.D.

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68. Given the following plant conditions:50% powerWhich ONE of the choices below answers both of the following questions?1) What is the plant position that maintains OAP-100.6, CONTROL ROOM CONDUCTAND CONTROL OF SHIFT ACTIVITIES, ATTACHMENT IA - REACTIVITY CONTROL PARAMETERS.2) What is the frequency at which Attachment IA is required to be performed?1) Reactor Engineer2) Daily1) Reactor Engineer2) Weekly1) Reactor Operator2) Daily1) Reactor Operator2) Weekly A.B.C.D.

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69. Given the following plant conditions:* The Reactor Vessel head is removed.* IFV-3531-O-EF, OPER-SG A MTR DR EF PUMP FLOW CONT VLV, hasbeen isolated to replace the actuator.Which ONE of the choices below completes the following statement in accordance withSAP-0205 STATUS CONTROL AND REMOVAL AND RESTORATION?An ___(1)___ Removal and Restoration will be used to track the status ofIFV-3531-O-EF. When the valve is restored to the NEUTRAL position a ___(2)____ chain will beinstalled.1) Action2) red1) Action2) silver1) Outage2) red1) Outage2) silver A.B.C.D.

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70. Initial conditions:

• Reactor startup in progress in accordance with GOP-3 REACTOR STARTUPFROM HOT STANDBY TO STARTUP (MODE 3 TO MODE 2).

• The NROATC is withdrawing Control Bank "A" Rods.Current condition:

• Power ascension in progress in accordance with GOP-4A POWER OPERATION(MODE 1 - ASCENDING).Which ONE of the choices below completes the following statements?While withdrawing Control Bank "A" under the initial conditions, the ROD CNTRLBANK SEL Switch is required to be in the ___(1)___ position in accordance withGOP-3. The ROD CNTRL BANK SEL Switch is placed in AUTO when power is greater than a minimum of ___(1)___ in accordance with GOP-4A.1) CBA2) 10%1) CBA2) 15%1) MANUAL2) 10%1) MANUAL2) 15%A.B.C.D.

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71. Given the following plant conditions:* Mode 6.

• Spent Fuel Pool level decreasing.

• AOP-123.1, DECREASING LEVEL IN THE SPENT FUEL POOL ORREFUELING CAVITY DURING REFUELING, in progress.Which ONE of the choices below completes the following statement(s)?The radiation threshold that is specifically used in AOP-123.1 to trigger immediateevacuations of all personnel from the RB is _____.2 R/hr, as read on RM-G5, RB PERSONNEL ACCESS AREA GAMMA.

2 R/hr, as read on RM-G17A(B), RB MANIP CRANE AREA GAMMA.

20 R/hr, as read on RM-G5, RB PERSONNEL ACCESS AREA GAMMA.

20 R/hr, as read on RM-G17A(B), RB MANIP CRANE AREA GAMMA.

A.B.C.D.

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72. Given the following plant conditions:

• A Large break LOCA has occurred.

• Major core damage has occurred.

• The Severe Accident Management Guidelines have been entered.

• The Auxiliary Building has been evacuated due to high radiation levels.

• An operator must be dispatched to close a valve to terminate a release fromcontainment to the environment.Which ONE of the following describes the highest allowed radiation dose to performthis operation in accordance with EPP-020, EMERGENCY PERSONNEL EXPOSURECONTROL? No more than 5 Rem.No more than 10 Rem.

No more than 25 Rem. Greater than 25 Rem on a voluntary basis.

A.B.C.D.

14-01 NRC written

73. Given the following plant conditions:

• Initially at 100% power.

• A Reactor trip and Safety Injection occurred.

• EOP-1.0, E-0 REACTOR TRIP OR SAFETY INJECTION has been entered.

• Operators have just completed the IMMEDIATE ACTIONS of EOP-1.0.

• An AO reports that there is a loud rumbling noise at the door to the IntermediateBuilding on 436' and that the door is hot.

• RB pressure is 0.5 psig and stable.

• All RB sump levels are normal.

• All Steam Generator pressures are 750 psig and decreasing. * "A" and "B" Motor-driven EFW pumps breakers indicate tripped.Which one of the following manipulations is performed without specific direction froman EOP step under the current plant conditions in accordance with OAP-103.4,EOP/AOP USER'S GUIDE?Closure of all MSIVs.

Reduction of EFW flow to a total of 450 gpm.Complete Isolation of EFW flow to all Steam Generators.Isolation of steam to the Turbine-driven EFW pump.

A.B.C.D.

14-01 NRC written

74. Given the following plant conditions:Time 0600:

• A Small break LOCA occurred.

• Operators entered EOP-2.0, LOSS OF REACTOR OR SECONDARYCOOLANT.

• RCS pressure was 1300 psig and stable.

• Operators stopped "A" and "B" RHR pumps.

Time 0630:

• EOP-2.1 ES-1.2 POST- LOCA COOLDOWN AND DEPRESSURIZATION is inprogress.

• Operators are preparing to commence a operator-controlled cooldown. - Actions have been delayed due to failure of steam dumps to open.

• The NROATC notes the following history of RCS pressure indications.

Time 0615 650 psig0620 600 psig0625 550 psig 0630 500 psigWhich ONE of the following identifies the earliest time at which operators are required to restart the RHR pumps in injection mode in accordance with direction containedin EOP-2.1, if at all?ASSUME NO ADDITIONAL OPERATOR ACTIONS.ASSUME A CONSTANT RATE OF RCS PRESSURE DECREASE.They must be restarted at 0630.They must be restarted between 0635 and 0640. They must be restarted between 0640 and 0645. They must be restarted between 0645 and 0650.

A.B.C.D.

14-01 NRC written

75. Given the following plant conditions:

• A Reactor trip and Safety Injection occurred.

• Actions of EOP-1.0, E-0 REACTOR TRIP OR SAFETY INJECTION arecomplete.

• Operators transferred to EOP-3.0, E-2 FAULTED STEAM GENERATORISOLATION one (1) second ago.Which ONE of the following identifies a Major Action Category of EOP-3.0 inaccordance with the EOP-3.0 (E-2) Background Document?Terminate Safety Injection.Prepare for cooldown to COLD SHUTDOWN.Check for at least one non-faulted Steam Generator.Identify and isolate ruptured SGs.

A.B.C.D.

ANSWER KEY REPORTfor 14-01 NRC written Test Form: 0 Answers 0#1B 2B 3B 4B 5C 6B 7C 8A 9A 10C 11C 12C 13B 14D 15B 16D 17D 18B 19D 20D 21C 22A 23C 24B 25D 26B 27D 28D 29C 30C 31C 32B 33D 34A 35A 36B 37D 38B 39B 40C 41D 42A 43A 44C 45C 46A 47DTuesday, June 14, 2016 2:20:17 PM 1

ANSWER KEY REPORTfor 14-01 NRC written Test Form: 0 Answers 0#48B49A 50C 51A 52A53A54C 55A 56C 57A 58A 59C 60C 61A 62D63A64B 65A 66B 67A 68D 69D 70D 71D 72D 73A 74D75CTuesday, June 14, 2016 2:20:17 PM 2

2016 V.C. Summer NRC Initial Written Examination Class 14-01

Name _______________________________________ Date ______________________

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

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