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 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 V.C Summer Unit 1 Region: I II X III IV Reactor Type: W X 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 have neither given nor received aid.

Applicant's Signature Results Examination Value ________ Points Applicant's Score ________ Points Applicant's Grade ________ Percent ES-401, Page 47 of 50

2016 V.C. Summer hEZInitial Written Examination Class 14-01 Name _______________________________________ Date ______________________

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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.

• TAVG 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.

A. 1) increasing

2) will B. 1) increasing

2) will not C. 1) decreasing

2) will D. 1) decreasing

2) will not

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.

• TAVG 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 be closed.

A. 1) cannot

2) either MVG-8801A or MVG-8801B, HI HEAD TO COLD LEG INJ B. 1) cannot

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

2) either MVG-8801A or MVG-8801B, HI HEAD TO COLD LEG INJ D. 1) can

2) both MVG-8801A and MVG-8801B, HI HEAD TO COLD LEG INJ

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?

A. Reduces heat input into the RCS.

B. Prevents damage to RCP motor bearings.

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

D. Saves RCPs for future starts in degraded core cooling procedures.

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 in the 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 _________

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

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

C. shifted to fast speed to provide cooling for non-essential loads.

D. shifted to fast speed to provide additional cooling for an RHR heat exchanger.

14-01 NRC written

5. Which ONE of the following identifies a condition that would require the immediate trip of the affected reactor coolant pump?

A. Pump frame vibration of 4 mils and stable.

B. Pump shaft vibration of 8 mils and increasing.

C. Motor stator temperature of 312°F and increasing.

D. Lower seal water bearing temperature 190°F and increasing.

14-01 NRC written

6. Given the following plant conditions:

Time 0600:

• 100% power.

• TAVG 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 level transmitter __(1) __ failing high.

At time 0606 pressurizer level is __(2)__.

ASSUME NO OPERATOR ACTIONS A. 1) LT-459

2) Increasing.

B. 1) LT-459

2) Decreasing.

C. 1) LT-460

2) Increasing.

D. 1) LT-460

2) Decreasing.

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 the instrument readings above?

A. Reactor coolant is being lost outside of the RB.

B. RWST level is above the level at which automatic recirculation realignment occurs.

C. ECCS Pump suction requirements are not met for recirculation.

D. Vital equipment required for accident mitigation in the RB is submerged.

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 be stopped in accordance with AOP-118.1?

A. Stop "A" Charging pump at 1720.

B. Stop "A" Charging pump at 1830.

C. Stop "B" RHR pump at 1720.

D. Stop "B" RHR pump at 1830.

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 the conditions above?

__(1)__ and can be reset from the Main Control Board.

Condenser steam dumps __(2)__ armed.

A. 1) only one (1) train of SI

2) are B. 1) only one (1) train of SI

2) are not C. 1) both trains of SI

2) are D. 1) both trains of SI

2) are not

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 actions are taken in EOP-4.0?

A. The RCS cooldown rate will be restricted to 50°F/hr.

B. The RCS depressurization will take longer to complete.

C. The RCS cooldown rate will not be restricted but will take longer to complete.

D. The RCS depressurization may have to be stopped prior to terminating SI due to voiding in the reactor core.

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 a Feedwater Isolation actuation occurred?

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

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 was required?

A. 1105 because an ATWS has occurred.

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

C. 1106 because there is only one (1) Feedwater Booster pump running.

D. 1106 because there are no Feedwater Booster pumps running.

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 with EOP-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 controlling properly.

A. 1) TAVG

2) 557°F.

B. 1) TCOLD

2) 557°F.

C. 1) TAVG

2) 564°F.

D. 1) TCOLD

2) 564°F.

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 _____.

A. TEST TRANSFER Switch to ALT.

B. MAN BYP Switch to PREF - ISOLATE.

C. MAN BYP Switch to BYP to ALT.

D. MAN BYP Switch to BYP to ALT - ISOLATE.

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 Service cooling if operators take no action?

2) How will diesel be operated after Fire Service cooling is established in accordance with AOP-117.1?

A. 1) Yes.

2) Operated up to the full rated load capacity because Fire Service cooling will provide adequate cooling at the rated load.

B. 1) Yes.

2) Operated at a reduced load capacity because Fire Service cooling will not provide adequate cooling at the rated load.

C. 1) No.

2) Operated up to the full rated load capacity because Fire Service cooling will provide adequate cooling at the rated load.

D. 1) No.

2) Operated at a reduced load capacity because Fire Service cooling will not provide adequate cooling at the rated load.

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?

A. 1) The operating Instrument Air Compressor has tripped.

2) Instrument Air header pressure decreases to 60 psig.

B. 1) The operating Instrument Air Compressor has tripped.

2) An MSIV indicates off it's open seat.

C. 1) A large leak exists in the Instrument Air system.

2) Instrument Air header pressure decreases to 60 psig.

D. 1) A large leak exists in the Instrument Air System.

2) An MSIV indicates off it's open seat.

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 GRID ISSUES.

Which ONE of the choices below completes the following statements in accordance with AOP-301.1?

An increase in V.C. Summer reactor power could be caused by __(1)__, as identified in a CAUTION statement.

The value specified on the Reference Page of AOP-301.1 above which a Reactor Trip is required is ___(1)___

A. 1) Turbine control valves opening due to a decreased grid frequency.

2) 100%

B. 1) Turbine control valves opening due to a decreased grid frequency.

2) 101%

C. 1) a RCS flow increase due to an increase in grid frequency.

2) 100%

D. 1) a RCS flow increase due to an increase in grid frequency.

2) 101%

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 has been entered.

• Steam Generator levels indicate 10% wide range level.

Which ONE of the choices below answer both of the following questions in accordance with 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 be opened, would Reactor Vessel Head vents also be opened?

A. 1) Yes.

2) Yes.

B. 1) Yes.

2) No.

C. 1) No.

2) Yes.

D. 1) No.

2) No.

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)___.

A. 1) 0801

2) compliance is maintained with Technical Specification Shutdown Margin requirements.

B. 1) 0801

2) Axial Flux Differential remains within the Technical Specification requirement.

C. 1) 0802

2) rods do not go below Technical Specification rod insertion limits.

D. 1) 0802

2) compliance with Technical Specification Shutdown Margin requirements is restored.

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 is dropped in the Reactor Building.

Under the conditions above, a release of noble gases from a fuel assembly dropped in the Reactor Building __(2)__ be detected by RM-A3, MAIN PLANT VENT.

A. 1) new

2) would B. 1) new

2) would not C. 1) spent

2) would D. 1) spent

2) would not

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 action provided by __(2)__.

Assume that a Reactor trip setpoint has NOT been reached.

A. 1) RM-A9, CNDSR EXHAUST GAS ATMOS.

2) RM-L7, NUCLEAR BLOWDOWN WASTE EFFLUENT LIQUID.

B. 1) RM-A9, CNDSR EXHAUST GAS ATMOS.

2) RM-L3, STEAM GENERATOR BLOWDOWN LIQUID.

C. 1) RM-G19B, STMLN HI RNG GAMMA.

2) RM-L7, NUCLEAR BLOWDOWN WASTE EFFLUENT LIQUID.

D. 1) RM-G19B, STMLN HI RNG GAMMA.

2) RM-L3, STEAM GENERATOR BLOWDOWN LIQUID.

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 action statement in accordance with either of the following V.C. Summer Technical Specifications for CONTAINMENT SYSTEMS?

T.S. 3.6.1.4 - INTERNAL PRESSURE T.S. 3.6.1.5 - AIR TEMPERATURE

2) Is the action required to be completed within one (1) hour?

A. 1) Negative Containment pressure of 0.3 psig (- 0.3 psig).

2) Yes.

B. 1) Negative Containment pressure of 0.3 psig (- 0.3 psig).

2) No.

C. 1) Containment average air temperature of 115°F.

2) Yes.

D. 1) Containment average air temperature of 115°F.

2) No.

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 in progress.

• Attempts to restore an ECCS injection flowpath have failed.

Which ONE of the following identifies the next major action required in an attempt to restore adequate core cooling in accordance with EOP-14.0?

A. Restart an RCP.

B. Open pressurizer PORVs.

C. Depressurize steam generators.

D. Open the reactor head vent valves.

14-01 NRC written

24. Which ONE of the choices below answers both of the following questions regarding EOP-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?

A. 1) Yes.

2) Check if PRT conditions are normal.

B. 1) Yes.

2) Verify no SG tubes are ruptured.

C. 1) No.

2) Check if PRT conditions are normal.

D. 1) No.

2) Verify no SG tubes are ruptured.

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- LOCA COOLDOWN AND DEPRESSURIZATION.

Which ONE of the following describes the method and rate at which the RCS cooldown will occur in accordance with EOP-2.1?

A. Condenser steam dumps will be used at the maximum achievable rate. RCS cooldown rate limits do not apply for this condition.

B. Condenser steam dumps will be used at less than 100°F per hour cooldown rate.

C. S/G PORVs will be used at the maximum achievable rate. RCS cooldown rate limits do not apply for this condition.

D. S/G PORVs will be used at less than 100°F per hour cooldown rate.

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 with OAP-103.4 EOP/FSP/AOP USER'S GUIDE?

EOP-15.1, STEAM GENERATOR OVERPRESSURE __(1)__ allowed to be used in the current condition.

The CRS __(2)__ required to enter EOP-15.1 when the use of YELLOW path procedures is allowed by OAP-103.4.

A. 1) is

2) is B. 1) is

2) is not C. 1) is not

2) is D. 1) is not

2) is not

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 in progress.

• 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 the EOP-2.1 Reference Page, is either a subcooling value less than __(1)__ or a PZR level less than __(2)__.

A. 1) 52.5°F

2) 10%.

B. 1) 52.5°F

2) 28%.

C. 1) 67.5°F

2) 10%.

D. 1) 67.5°F

2) 28%.

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 the allowed range in accordance with SOP-101, REACTOR COOLANT SYSTEM.

A. 1) Flow has increased.

2) Lower to less than the maximum allowed value of 13 gpm.

B. 1) Flow has increased.

2) Lower to less than the maximum allowed value of 10 gpm.

C. 1) Flow has decreased.

2) Raise to more than the minimum allowed value of 8 gpm.

D. 1) Flow has decreased.

2) Raise to more than the minimum allowed value of 6 gpm.

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?

A. Closure of MVB-9524B/9526B, LP B NON-ESSEN LOAD ISOL.

B. Closure of MVG-9600, TO THERM BARR ISOL.

C. Closure of MVG-9568, TO RB LOAD.

D. Trip of "A" CCW pump.

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)__ be provided.

After 30 seconds, RCP seal injection will automatically be reestablished using water from the __(2)__.

ASSUME NO OPERATOR ACTIONS A. 1) will not

2) RWST.

B. 1) will not

2) VCT.

C. 1) will

2) RWST.

D. 1) will

2) VCT.

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.

A. 1) MVG-8809B, RWST TO RHR PP B

2) RCS failures near the Nil Ductility Temperature B. 1) MVG-8809B, RWST TO RHR PP B

2) loss of heat removal capability during Mode 4 conditions C. 1) MVG-8702B, RCS LP C TO PUMP B

2) RCS failures near the Nil Ductility Temperature D. 1) MVG-8702B, RCS LP C TO PUMP B

2) loss of heat removal capability during Mode 4 conditions

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 LEG RECIRCULATION.

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 valve MVG-8106, CHG PP will be __(2)__.

A. 1) RWST.

2) open.

B. 1) RWST.

2) closed.

C. 1) RHR pump discharge.

2) open.

D. 1) RHR pump discharge.

2) closed.

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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 increased to the current value of 2300 psig.

Which ONE of the choices below completes the following statements?

PRT level is increasing because there is coolant flowing from a _____ .

A. Pressurizer Code Safety valve.

B. relief valve on the RHR pump suction.

C. relief valve on the normal letdown line.

D. relief valve on the Seal Return line.

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 ISOL are open.

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

Time 1715:

• Operator realigned the valves above in accordance with SOP-102, CHEMICAL AND VOLUME CONTROL SYSTEM as follows:

- PVT-8149B, LTDN ORIFICE B ISOL and PVT-8149C, LTDN ORIFICE C ISOL 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 that occurred as a result of realigning valves to the current condition?

Assume all parameters are stable at the current conditions.

A. Cooling flow through the Letdown Heat Exchanger is higher.

B. Regenerative Heat Exchanger outlet temperature is lower.

C. Flow through the normal letdown line is lower.

D. VCT level is lower.

14-01 NRC written

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 occurs Which ONE of the following identifies the earliest time at which the trip of a component is required in accordance with AOP-118.1, LOSS OF COMPONENT COOLING WATER?

Assume CCW is not restored.

A. "A" RCP at 1310.

B. "A" RCP at 1320.

C. "B" RHR pump at 1320.

D. "B" RHR pump at 1330.

14-01 NRC written

36. Given the following plant conditions:

• 75% power and stable.

• The TAVG 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.

A. 1) is

2) FCV-122, CHG FLOW opened further B. 1) is.

2) Pressurizer backup heaters energized C. 1) is not

2) FCV-122, CHG FLOW opened further D. 1) is not

2) Pressurizer backup heaters energized

14-01 NRC written

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 a replacement part.

Which ONE of the following identifies a set of actions that will be required in accordance 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.

A. 1) taken to MAN

2) will not B. 1) taken to MAN

2) will C. 1) left in AUTO

2) will not D. 1) left in AUTO

2) will

14-01 NRC written

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 on low RCS flow.

A. 1) P-7 is in its proper condition

2) one (1)

B. 1) P-7 is in its proper condition

2) two (2)

C. 1) P-7 is not in its proper condition

2) two (2)

D. 1) P-8 is not in its proper condition

2) one (1)

14-01 NRC written

39. Which ONE of the following identifies the power supply to "B" Train Engineered Safety Features Loading Sequencer?

A. APN-5902 B. APN-5903 C. APN01DB2 D. DPN-1HB1

14-01 NRC written

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 with SOP-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)__.

A. 1) energized.

2) 2.

B. 1) energized.

2) 3.

C. 1) deenergized.

2) 2.

D. 1) deenergized.

2) 3.

14-01 NRC written

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 these conditions?

A. XFN-64B stops; XFN0064A-AH and XFN0065B-AH remain running.

Cooling water swaps to Service Water for all RBCUs.

B. XFN-64B stops; XFN0064A-AH and XFN0065B-AH remain running.

Cooling water swaps to Service Water for running RBCUs only.

C. All RBCUs stop; XFN0064A-AH and XFN0065B-AH start.

Cooling water swaps to Service Water for all RBCUs.

D. All RBCUs stop; XFN0064A-AH and XFN0065B-AH start.

Cooling water swaps to Service Water for running RBCUs only.

14-01 NRC written

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 first occurred at time __(1)__.

The actuation system circuit logic to allow closure of these valves was first satisfied at time __(2)__.

A. 1) 0700

2) 0716 B. 1) 0701

2) 0716 C. 1) 0706

2) 0717 D. 1) 0706

2) 0718

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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 in progress.

• 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 ________.

A. transition to EOP-3.0, E-2 FAULTED STEAM GENERATOR ISOLATION.

B. transition to EOP-3.1, ECA-2.1 UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS.

C. transition to EOP-2.0, LOSS OF REACTOR OR SECONDARY COOLANT.

D. ensure MSIVs are closed and remain in EOP-2.1.

14-01 NRC written

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 Main Steamline Isolation actuation signals?

A. Neither signal has actuated.

B. Only Phase B isolation has actuated.

C. Only Main Steamline isolation has actuated.

D. Both signals have actuated.

14-01 NRC written

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 pump speed until a maximum Feedwater pump pressure of __(1)__ is reached and will direct operators to __(2)__ if necessary.

A. 1) 1250 psig

2) open FCV-3321, LOOP A MAIN FW BYPASS from the Control Board.

B. 1) 1250 psig

2) dispatch an AO to locally operate PVT-478, SG A FWF.

C. 1) 1600 psig

2) open FCV-3321, LOOP A MAIN FW BYPASS from the Control Board.

D. 1) 1600 psig

2) dispatch an AO to locally operate PVT-478, SG A FWF.

14-01 NRC written

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% and indicate 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 the Motor-driven (MD) EFW pumps?

Assume no operator actions.

A. "A" and "B" MD EFW Pumps are running; FCV-3531(3541)(3551) are closed.

B. "A" and "B" MD EFW Pumps are running; FCV-3531(3541)(3551) are 100% open.

C. "A" and "B" MD EFW Pumps are off.

FCV-3531(3541)(3551) are closed.

D. "A" and "B" MD EFW Pumps are off.

FCV-3531(3541)(3551) are 100% open.

14-01 NRC written

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 strictly observed 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 of 4676 KW _____, in accordance with SOP-306, EMERGENCY DIESEL GENERATOR.

A. continuously without limits on duration.

B. for one 7-day period only.

C. 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.

D. 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.

14-01 NRC written

48. Given the following plant conditions;

• 20% power Which ONE of the following would require, if it were isolated, entry into an action statement of T.S. 3.8.1.1. AC SOURCES until the component is restored to service?

Assume no plant modifications or temporary cabling.

A. XTF005, UNIT 2 ENGINEERED SAFEGUARD TRANSFORMER.

B. XTF0031, EMERGENCY AUXILIARY TRANSFORMER #1.

C. XTF5052, ALTERNATE AC SOURCE TRANSFORMER.

D. 230 KV switchyard Bus 2.

14-01 NRC written

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 terminal voltage that can be expected on batteries XBA1A and XBA1B is __(1)__.

EOP-6.0 __(2)__ contain actions to shed non-safety related DC loads.

A. 1) 108 VDC.

2) does B. 1) 108 VDC.

2) does not C. 1) 110 VDC.

2) does D. 1) 110 VDC.

2) does not

14-01 NRC written

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 the procedure that will be implemented at time 0702?

A. Verify the reactor is tripped.

EOP-13.0, FR-S.1 RESPONSE TO ABNORMAL NUCLEAR POWER GENERATION.

B. Trip the Main turbine.

EOP-13.0, FR-S.1 RESPONSE TO ABNORMAL NUCLEAR POWER GENERATION.

C. Trip the Main turbine.

EOP-6.0, ECA-0.0 LOSS OF ALL ESF AC POWER.

D. Restore power to any ESF bus.

EOP-6.0, ECA-0.0 LOSS OF ALL ESF AC POWER.

14-01 NRC written

51. Which ONE of the following sets of valves will re-position as indicated on a sensed Hi Radiation signal generated by detector RM-L3, STEAM GENERATOR BLOWDOWN LIQUID MONITOR?

A. PVT-524, TO CW will close.

PVG-525, DIVERT TO NB will open.

B. PVT-524, TO CW will close.

PVG-525, DIVERT TO NB will close.

C. PVD-6121, NUC BLOWDOWN DISCHARGE will close.

PVG-525, DIVERT TO NB will close.

D. PVD-6121, NUC BLOWDOWN DISCHARGE will close.

PVG-525, DIVERT TO NB will open.

14-01 NRC written

52. 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 A. 1DB 1B2X B. 1DB 1DB2X C. 1DB1 1B2X D. 1DB1 1DB2X

14-01 NRC written

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 be used in these conditions in accordance with SOP-220, STATION AND BACKUP INSTRUMENT AIR SYSTEMS?

A. Instrument air compressor "B" using backup cooling supplied from Raw Water.

B. Diesel air compressor with pressure control selected to "ONBOARD".

C. Reactor Building air compressors through XVA-2659, RB INSTRUMENT AIR BACK-UP SUP ISOL VLV.

D. Supplemental instrument air compressor through XVB02633-IA IN BACKUP SYSTEM SUP HDR ISOLATION VLV.

14-01 NRC written

54. Which ONE of the following describes the normal position of SVX-9364B RCS LOOP B SAMPLE HEADER ISOLATION VLV and which ESF function closes this valve?

A. Normally open and receives a CLOSE signal on phase A B. Normally open and receives a CLOSE signal on phase B C. Normally closed and receives a CLOSE signal on phase A D. Normally closed and receives a CLOSE signal on phase B

14-01 NRC written

55. Given the following plant conditions:

• A LOCA has occurred.

• The operating crew has entered EOP-17.1, RESPONSE TO REACTOR BUILDING FLOODING.

Which ONE of the following describes the method that will be used to evaluate for leakage from Service Water to the Reactor Building?

A. Compare flow indication from each SW Booster Pump discharge to that pumps return flow to the pond.

B. Compare "A" SW Booster pump flow and pressure to "B" SW Booster pump flow and pressure.

C. Isolate Service Water to one (1) RBCU train and monitor the rate of sump increase.

D. Verify indications for Service Water flow to all individual loads are normal.

14-01 NRC written

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 is not restored?

Assume no operator actions.

A. The reactor will trip on high pressurizer pressure.

B. The pressurizer spray valves will open to maintain RCS pressure.

C. Two pressurizer PORVs will cycle to maintain RCS pressure.

D. The reactor will trip on low pressurizer pressure.

14-01 NRC written

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 +4 Time 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 +7 N-43 +7 N-44 +7 Which 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 actions A. 1) Xenon

2) positive B. 1) Xenon

2) negative C. 1) Iodine

2) positive D. 1) Iodine

2) negative

14-01 NRC written

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 it fails both high or low?

2) Do LT-459 and LT-460 both serve as Reactor Trip protection channels?

A. 1) LT-459

2) Yes.

B. 1) LT-459

2) No.

C. 1) LT-460

2) Yes.

D. 1) LT-460

2) No.

14-01 NRC written

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 of power if either bus __(2)__ is restored, A. 1) 3°F/hr.

2) 1DA or 1DB B. 1) 3°F/hr.

2) 1A or 1B C. 1) 20°F/hr.

2) 1DA or 1DB D. 1) 20°F/hr.

2) 1A or 1B

14-01 NRC written

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?

A. Closing the equipment hatch.

B. Stopping XFN-11A.

C. Stopping XFN-13A.

D. Starting XFN-20, FUEL BLDG SPLY FAN.

14-01 NRC written

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 regarding operation of the ECCS system?

SI Reinitiation Criteria, as contained on the EOP-1.2 REFERENCE PAGE, are first applicable when __(1)__

When Safety Injection is reinitiated per the REFERENCE PAGE, operators __(2)__.

A. 1) MVG-8801A(B), HI HEAD TO COLD LEG INJ are closed.

2) open injection valves and start Charging pumps manually.

B. 1) MVG-8801A(B), HI HEAD TO COLD LEG INJ are closed.

2) actuate Safety Injection using switches SI ACTUATION CS-CR0IB(C).

C. 1) the RHR pumps are stopped.

2) open injection valves and start Charging pumps manually.

D. 1) the RHR pumps are stopped.

2) actuate Safety Injection using switches SI ACTUATION CS-CR0IB(C).

14-01 NRC written

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 the release.

Which ONE of the choices below answers both of the following questions:

1) What condition must be satisfied prior to recommencing the release in accordance with HPP-709, SAMPLING AND RELEASE OF RADIOACTIVE GASEOUS EFFLUENTS?

2) What is the minimum control manipulation necessary to enable opening of HCV-014?

A. 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.

B. 1) A Request for Redundant Analysis must be initiated.

2) HCV-014 controller must be taken to ZERO (0), then the valve re-opened.

C. 1) A Request for Redundant Analysis must be initiated.

2) HCV-014 selector switch must be cycled to CLOSE, then the valve re-opened.

D. 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.

14-01 NRC written

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, PROCESS AND AREA RADIATION MONITORING SYSTEM, the final position of the INTERLOCK switch on RM-G17A will be __(2)__.

A. 1) 1 and 3

2) ON.

B. 1) 1 and 3

2) OFF.

C. 1) 2 and 4

2) ON D. 1) 2 and 4

2) OFF

14-01 NRC written

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)__.

A. 93 psig B. 90 psig C. 70 psig D. 65 psig

14-01 NRC written

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 Control Board.

• FEP-4.0, CONTROL ROOM EVACUATION DUE TO A FIRE has been implemented by the Shift Manager.

- Operators determine that immediate actions can be performed in the control room 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 perform in the Control Room?

A. Trip RCPs.

B. Open PORV disconnect switches.

C. Emergency start "B" EDG.

D. Start "B" Motor-driven EFW pump.

14-01 NRC written

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 maximum temperature of ______.

REFERENCE PROVIDED A. 482°F B. 469°F C. 466°F D. 453°F

EOP-4.0 REVISION 24 E3, STEAM GENERATOR TUBE RUPTURE ACTION/EXPECTED RESPONSE ALTERNATIVE ACTION 9 Determine the required core exit TC temperature for RCS cooldown from the table below:

LOWEST RUPTURED CORE EXIT CONTROLLER SG PRESS TC TEMP SETPOINT (PSIG) (°F) 1101-1200 494 [478] 4.9 1001-1100 482 [466] 4.4 901-1000 469 [453] 3.8 801-900 455 [439] 3.4 701-800 439 [423] 2.8 601-700 421 [405] 2.3 460-600 392 [376] 1.6 10 Check if any RCP is running. 10 With no RCP running, RCS cooldown and depressurization may cause RUPTURED loop Tcold to falsely indicate a transition to EOP-16.0, FR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK, is required. Disregard the RUPTURED loop Tcold indication prior to performing Step 40.

PAGE 8 OF 51

14-01 NRC written

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)__.

A. 1) does

2) 0.10 ppm B. 1) does not

2) 0.10 ppm C. 1) does

2) 0.15 ppm D. 1) does not

2) 0.15 ppm

14-01 NRC written

68. Given the following plant conditions:

50% power Which ONE of the choices below answers both of the following questions?

1) What is the plant position that maintains OAP-100.6, CONTROL ROOM CONDUCT AND CONTROL OF SHIFT ACTIVITIES, ATTACHMENT IA - REACTIVITY CONTROL PARAMETERS.

2) What is the frequency at which Attachment IA is required to be performed?

A. 1) Reactor Engineer

2) Daily B. 1) Reactor Engineer

2) Weekly C. 1) Reactor Operator

2) Daily D. 1) Reactor Operator

2) Weekly

14-01 NRC written

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, has been isolated to replace the actuator.

Which ONE of the choices below completes the following statement in accordance with SAP-0205 STATUS CONTROL AND REMOVAL AND RESTORATION?

An ___(1)___ Removal and Restoration will be used to track the status of IFV-3531-O-EF.

When the valve is restored to the NEUTRAL position a ___(2)____ chain will be installed.

A. 1) Action

2) red B. 1) Action

2) silver C. 1) Outage

2) red D. 1) Outage

2) silver

14-01 NRC written

70. Initial conditions:

• Reactor startup in progress in accordance with GOP-3 REACTOR STARTUP FROM 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 CNTRL BANK SEL Switch is required to be in the ___(1)___ position in accordance with GOP-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.

A. 1) CBA

2) 10%

B. 1) CBA

2) 15%

C. 1) MANUAL

2) 10%

D. 1) MANUAL

2) 15%

14-01 NRC written

71. Given the following plant conditions:

• Mode 6.

• Spent Fuel Pool level decreasing.

• AOP-123.1, DECREASING LEVEL IN THE SPENT FUEL POOL OR REFUELING 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 immediate evacuations of all personnel from the RB is _____.

A. 2 R/hr, as read on RM-G5, RB PERSONNEL ACCESS AREA GAMMA.

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

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

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

14-01 NRC written

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 from containment to the environment.

Which ONE of the following describes the highest allowed radiation dose to perform this operation in accordance with EPP-020, EMERGENCY PERSONNEL EXPOSURE CONTROL?

A. No more than 5 Rem.

B. No more than 10 Rem.

C. No more than 25 Rem.

D. Greater than 25 Rem on a voluntary basis.

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 Intermediate Building 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 from an EOP step under the current plant conditions in accordance with OAP-103.4, EOP/AOP USER'S GUIDE?

A. Closure of all MSIVs.

B. Reduction of EFW flow to a total of 450 gpm.

C. Complete Isolation of EFW flow to all Steam Generators.

D. Isolation of steam to the Turbine-driven EFW pump.

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 SECONDARY COOLANT.

• 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 in progress.

• 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 psig 0620 600 psig 0625 550 psig 0630 500 psig Which 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 contained in EOP-2.1, if at all?

ASSUME NO ADDITIONAL OPERATOR ACTIONS.

ASSUME A CONSTANT RATE OF RCS PRESSURE DECREASE.

A. They must be restarted at 0630.

B. They must be restarted between 0635 and 0640.

C. They must be restarted between 0640 and 0645.

D. They must be restarted between 0645 and 0650.

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 are complete.

• Operators transferred to EOP-3.0, E-2 FAULTED STEAM GENERATOR ISOLATION one (1) second ago.

Which ONE of the following identifies a Major Action Category of EOP-3.0 in accordance with the EOP-3.0 (E-2) Background Document?

A. Terminate Safety Injection.

B. Prepare for cooldown to COLD SHUTDOWN.

C. Check for at least one non-faulted Steam Generator.

D. Identify and isolate ruptured SGs.

ANSWER KEY REPORT for 14-01 NRC written Test Form: 0 Answers

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

ANSWER KEY REPORT for 14-01 NRC written Test Form: 0 Answers

1. 0 48 B 49 A 50 C 51 A 52 A 53 A 54 C 55 A 56 C 57 A 58 A 59 C 60 C 61 A 62 D 63 A 64 B 65 A 66 B 67 A 68 D 69 D 70 D 71 D 72 D 73 A 74 D 75 C Tuesday, June 14, 2016 2:20:17 PM 2

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

• • • • • • KEY******

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****