ML102110188

Initial Exam 2010-301 Final RO Written Exam

ML102110188
Person / Time
Site:	North Anna
Issue date:	07/16/2010
From:	NRC/RGN-II
To:	Virginia Electric & Power Co (VEPCO)
References
50-338/10-301, 50-339/10-301, ES-401, ES-401-7 50-338/10-301, 50-339/10-301
Download: ML102110188 (80)

Text

FAC FAC JE: E: North North Anna Anna Section Section 88 REP REF 3ER: R: 05000338/2010301 05000339/2010301 05000338/2010301 AND 05000339/2010301 FI RO WRITTEN EXAM co co~r FZO Written Exam Exam (75 'as given questions with changes made as given' ng ng administration administration annotated) annotated)

Drence rence Handouts Handouts Provided Provided To To Applicants Applicants

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Subn Submi y: _ _ _ _ _ _ _ Verified Verified By:

By: _ _ _ _ _ _ _ __

II ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission I Site-Specific RO Written Examination Applicant Information Name:

Date: 06/16/10 Facility/Unit: North Anna Units 11 & 2 2

Region: I E II 10110 Ill DivE 1II0lVO Reactor Type: W w0 CEO CEE BWOBWE GEO GEE 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. II have neither given nor received aid.

Applicants Signature Applicant's Results Examination Value 75 Points Applicants Applicant's Score Points Applicants Applicant's Grade Percent ES-401, Page 30 of 33

NAPS 2010 NAPS 2010 NRCNRC RO RO ExamExam 1.

Given the Given thefollowing following conditions:

conditions:

• Unit 11 isis at Unit MOL, starting at MOL, starting upup following following aa forced forced outage.

outage.

• The crew The crew has has just just completed completed taking taking critical critical data.

data.

• The QATC The OATC pulls pulls rods rods to establish aa positive to establish positive startup startup rate.

rate.

When the When OATC releases the OATC releases thethe IN-HOLD-OUT IN-HOLD-OUT switch, switch, rods rods continue continue toto step step outward.

outward.

Assuming NO Assuming operator actions NO operator actions are are taken, taken, which which ONE ONE of of the the following following identifies identifies the the plant plant response response to to this this event?

event?

Power will Power will increase increase to to _ _ _ _ _. The The power power increase increase is is terminated terminated byby the the _ _ _ __

A.

A. 30%; Intermediate 30%; Intermediate Range Range rodrod stop stop signal.

signal.

B.

B. 30%; Power 30%; Power Range rod stop signal.

C.

C. 25%; Intermediate 25%; Intermediate Range reactor trip signal.

D.

O. 25%; Power 25%; Power Range reactor trip signal.

NAPS 2010 NAPS 2010 NRC NRC RO RD Exam Exam 2.

2.

Plant conditions Plant conditions are are asas follows:

follows:

• The crew The crew is is preparing preparing toto roll roll Unit Unit 11 turbine.

turbine.

• Reactor power Reactor power is is 8%.

8%.

• Turbine power Turbine power is is 0%.

0%.

• RCSTAVG15551°F.

RCS T AVG is 551°F.

Based on these conditions, PRZR program level is _ _ _ _ , and letdownletdown will automatically isolate if level decreases to _ _ __

PRZR level A. 28.4%; 15%

B.

B. 28.4%; 23.4%

C. 32.7%; 15%

D. 32.7% ; 27.7%

32.7%;

NAPS 2010 NAPS 2010 NRCNRC RO RO ExamExam 3.

3.

Given the Given the following following conditions:

conditions:

Unit 11 isis starting Unit starting up following aa mid-cycle up following mid-cycle forced forced outage.

outage.

• The crew The crew has has commenced commenced slowly sowly raising raising power power inin preparations preparations for for rolling rolling the the turbine.

turbine.

At approximately At approximately 4% 4% power, power, "B" B RCP RCP trips.

trips.

Which ONE Which ONE of of thethe following following identifies identifies the the effect effect of of the the RCP RCP trip trip on on the the Departure Departure fromfrom Nucleate Nucleate Boiling Boiling Ratio (DNBR), AND Ratio (DNBR), AND includes includes the the procedurally procedurally required required action action the the crew will take to mitigate this crew will take to mitigate this event?

event?

A. DNBR has DNBR has decreased; decreased ; stop powerpower increase increase and be be in in Mode Mode 33 within 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br />.

hours.

B.

B. decreased ; trip the reactor.

DNBR has decreased; C. DNBR has increased; increased ; stop power increase and be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

D.

D. increased trip the reactor.

DNBR has increased;

NAPS 2010 NAPS 2010 NRCNRC RO Exam RO Exam 4.4.

TheAuxiliary The Auxiliary Building Building Operator Operatorreports reports that thatthe the running running charging charging pump, pump, 1-CH-P-1A, 1-CH-P-1A, seems seems toto be be making making some unusual some unusual noises.

noises.

Which ONE Which ONE ofof the the following following identifies identifies the PCS parameter the PCS parameter that that can can be be trended trended by by the the OATCs OATCs to to evaluate evaluate the status the status of 1-CH-P-1A?

of 1-CH-P-1A?

A. Cubicle A. Cubicle Temperature.

Temperature.

B.

B. Inboard Pump Inboard Pump Bearing Bearing Temperature.

Temperature.

C. Gear C. Gear Box Box Cooler Cooler Outlet Outlet Service Service Water Water Temperature.

Temperature.

D.

D. Lube Oil Lube Cooler Service Oil Cooler Service Water Water Outlet Outlet Flow.

Flow.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 5.

5.

Unit 11 isis at Unit at 100%

100% power power with with the following charging the following charging pump pump configuration:

configuration:

• 1-OH-P-lA is 1-CH-P-1A is running.

running.

• 1-CH-P-1B is 1-CH-P-1B is in in AUTO.

AUTO.

• 1-CH-P-1C 1-CH-P-1 is tagged C is tagged out out for for breaker breaker inspections.

inspections.

The OA The OATC notes the TC notes following indications:

the following indications:

• 1-CH-Pl-1121, Discharge 1-CH-PI-1121, Discharge Header Header Pressure Pressure - erratic.

• 1-CH-Fl-1 122, Charging 1-CH-FI-1122, Charging Flow - erratic.

Flow - erratic.

• 1-OH-P-lA, Motor Amps - erratic.

1-CH-P-1A, -

Based on these plant conditions, which ONE of the following identifies the cause of these indications AND includes the actions taken per 1-AP-49, Loss of Normal Charging, to mitigate this event? --

A. Gas binding of 1-CH-P-1A; 1-OH-P-lB place 1-CH-P-1 Bandand 1-CH-P-1 1-OH-P-lA A in PTL, then vent and start 1-CH-P-1 B.

1-CH-P-1B.

B. 1-OH-P-lA; Gas binding of 1-CH-P-1A; 1-OH-P-lB start 1-CH-P-1 1-OH-P-lA, B and stop 1-CH-P-1 1-CH-P-IA.

A, then vent 1-CH-P-1 A.

C. Relief valve stuck open on 1-CH-P-1 1-CH-P-1A; A; 1-OH-P-lA and close 1-CH-P-1A stop 1-CH-P-1A 1-CH-P-IA discharge MOVs, then start 1-CH-P-1B.

D. Relief valve stuck open on 1-CH-P-1A; 1-CH-P-1 A; start 1-CH-P-1 l-CH-P-1B, B, then stop 1-CH-P-1A and close 1-CH-P-lA 1-CH-P-1A discharge MOVs.

NAPS 2010 NAPS 2010 NRC NRC RORD Exam Exam 6.

6.

Given the Given following conditions:

the following conditions:

• RCS temperature is RCS temperature is 175°F.

175°F.

• RCS pressure RCS pressure is is 305 psig.

305 psig.

• The PRZR is The PRZR is solid.

solid.

• Charging flow control Charging control isis in in manual.

manual.

• RHR is RHR in service, is in service, with with the the "A" A RHR heat exchanger RHR heat exchanger and and 1-RH-P-1A 1-RH-P-lA in in service.

service.

• 1-RH-FCV-1 605, RHR 1-RH-FCV-1605, RHR H/X bypass, bypass, is in in AUTO.

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

Which ONE of the following identifies the effect of this malfunction on RHR Q!!.IJJQ pump flow, and on RCS pressure?(assume NO operator actions are taken)

A. RHR pump flow remains the same; RCS pressure remains the same B. RHR pump flow remains the same; same: RCS pressure decreases C. RHR pump flow increases; RCS pressure remains the same D. RHR pump flow increases; RCS pressure decreases

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 7.

7.

Unit 11 was Unit was at 100% power at 100% power when when aa small-break small-break LOCA LOCA occurred.

occurred. The The crew crew is is currently currently performing performing 1-E-1, 1-E-1, Loss of Loss of Reactor Reactor or or Secondary Secondary Coolant.

Coolant.

The Unit The Unit Supervisor Supervisor isis at at step step 6, 6, Check Check ifif SI SI Can Can 8eBe Terminated.

Terminated.

The following The following conditions conditions exist:

exist:

• Containment pressure Containment pressure is is 22 22 psia psia and and slowly slowly decreasing.

decreasing.

• RCS pressure RCS pressure is 1085 psig is 1085 psig and and slowly slowly increasing.

increasing.

• PRZR level is 30% and slowly increasing.

PRZR

• CETCs are 490°F and and stable.

• RCS loop hot-leg temperatures are 475°F and stable.

• AFW has been throttled to 150 gpm to each SG.

• A ICCM indicates subcooling of 66°F.

"A"

• B ICCM indicates subcooling of 80°F.

"8" Given these conditions, _ _ _ _ _ , and SI termination criteria _ _ _ __

A. A ICCM is indicating correctly; are met "A"

B.

8. A ICCM "A" 10CM is indicating correctly; are NOT met C. B "8" ICCM is indicating correctly; are met D. B "8" ICCM is indicating correctly; are NOT NOT met

NAPS 2010 NAPS 2010 NRC NRC RO RO ExamExam 8.

8.

Given the following Given the following conditions:

conditions;

• Unit 11 isis at Unit at 50%

50% power.

power.

• "8" and "c" B and C MFW MFW pumps pumps areare tagged tagged out.

out.

• A MFW "A" MFW pump pump trips.

trips.

The OATC The OATC attempted attempted to to trip trip the the reactor, reactor, but the reactor but the reactor trip trip breakers breakers did did NOT NOT open.

open.

Assuming NO Assuming NO additional additional operator operator actions actions are are taken, taken, which ONEONE of of the the following following identifies how how the the System will function to mitigate AMSAC System mitigate this event?

event?

AMSAC will open the Rod Rod Drive MG Set _ _ _ __

A. supply breakers immediately after level in 2/3 SGs reaches 13% narrow-range. narrow-range.

B.

B. supply breakers 27 seconds after level in 2/3 SGs reaches 13% narrow-range. narrow-range.

C.

C. output breakers immediately after level in 2/3 SGs reaches 13% narrow-range. narrow-range.

D. output breakers 27 seconds after level in 2/3 SGs reaches 13% narrow-range. narrow-range.

NAPS 2010 NAPS 2010 NRC NRC RO Exam RO Exam 9.

9.

Unit 11 isis at Unit 100% power at 100% when annunciator power when annunciator 1B-H1, lB-Hi, PRZPRZ RELIEF RELIEF TK TK HI HI TEMP, TEMP, isis received.

received.

The OATC The confirms the OATC confirms alarm isis valid, the alarm valid, and and notes notes that that PRT PRT level, level, pressure, pressure, and and temperature have been temperature have been slowly increasing slowly increasing since since assuming assuming the the watch.

watch.

Which ONE Which ONE of of the following identifies the following identifies the the source source of of PRT PRT inleakage in leakage that that has has caused caused these these plant plant conditions conditions AND includes AND includes the the flowpath flowpath used used to drain the to drain the heated heated water water from from the the PRT?

PRT?

A. Letdown Relief Letdown Relief Valve 1-CH-RV-1203 1-CH-RV-1203 leakingleaking by; by; PRT is PRT drained to the PDTT is drained PDTT and the PDTT and the PDTT is is pumped pumped directly directly to the in-service in-service Boron Recovery Tank.

Boron Recovery B.

B. Letdown Relief Letdown Relief Valve 1-CH-RV-1203 i-CH-RV-1203 leakingleaking by; by; PRT is drained to the PDTT and the PDTT is pumped directly to the Gas Stripper.

C. Reactor Vessel Flange O-ring 0-ring leakage; PRT is drained to the PDTT and the PDTT is pumped directly to the in-service Boron Recovery Tank.

D. Reactor Vessel Flange O-ring 0-ring leakage; PRT is drained to the PDTT and the PDTT is pumped directly to the Gas Stripper.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 10.

10.

Operators are Operators performing 1-0P-1.1, are performing 1-OP-1.1, UnitUnit Startup Startup from from ModeMode 55 atat Less Less Than Than 140°F 140°F to to Mode Mode 55 at at Less Less Than 200°F, Than 200°F, inin order order to to establish establish aa steam steam bubble bubble inin the the PRZR.

PRZR.

Which ONE Which ONE of the following of the following identifies identifies the the PRZR PRZR temperature temperature that that operators operators should should expect expect the the steam steam bubble to form as stated in 1-OP-i.

bubble to form as stated in 1-0P-1.1, AND 1, includes the J{Q includes the action action toto be be taken taken once once bubble bubble formation formation begins?

begins?

A. 425°F; A. 425°F; throttle throttle closed closed 1-CH-PCV-1145, 1-CH-PCV-1145, LetdownLetdown Pressure Pressure Control Control Valve.

Valve.

B. 425°F; B. 425°F; throttle throttle open open 1-CH-PCV-1145, 1-CH-PCV-1 145, LetdownLetdown Pressure Pressure Control Control Valve.

Valve.

C. 450°F; throttle C. 450°F; throttle closed closed 1-CH-PCV-1145, 1-CH-PCV-1145, LetdownLetdown Pressure Pressure Control Control Valve.

Valve.

D. 450°F; D. 450°F; throttle throttle open open 1-CH-PCV-1145, 1-CH-PCV-1 145, LetdownLetdown Pressure Pressure Control Control Valve.

Valve.

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 11.

11.

Both Units Both Units are are at at 100% power.

100% power.

1-CC-PCV-1 10, Component 1-CC-PCV-110, Component Clg CIg Pps Pps Recirc Recirc Hdr Hdr Pressure Pressure Control Control Vv, Vv, isis 50%

50% open open and and controlling controlling CC CC system pressure.

system pressure.

Due to Due to aa tagging tagging error, error, thethe instrument instrument air air supply to 1-CC-PCV-11 supply to 1-CC-PCV-1 100 is is inadvertently inadvertently closed.

closed.

When instrument When instrument air air is is isolated isolated to 1-CC-PCV-110, to 1-CC-PCV-11 indicated pressure 0, indicated pressure on on 1-CC-PI-100, 1-CC-Pl-100, CC CC HX HX Outlet Outlet Pressure, will Pressure, will and 2-CC-PCV-210 and 2-CC-PCV-210 will _ _ _ _ _ _ _ __

A.

A. decrease ; throttle decrease; throttle closed.

closed.

B. decrease; NOT change position.

C. increase; throttle open.

D. increase; NOT change position.

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 12.

12.

Unit 11 is Unit is at at 100% power.

100% power.

A PRZR A PRZR safety valve has safety valve has indications indications of of leakage.

leakage.

The following The following conditions conditions exist:

exist:

• PRZR pressure PRZR pressure is 2220 psig is 2220 psig and slowly increasing.

and slowly increasing.

• PRT pressure PRT pressure is 10 psig is 10 psig and and slowly slowly increasing.

increasing.

Which ONE of the following identifies identifies the expected temperature temperature indication indication downstream of the safety valve, valve, AND includes the reason the reason forfor the the indication?

indication?

A. Approximately 240°F because Approximately because this is an isenthalpic process.

B. Approximately 240°F because this is an isentropic process.

Approximately c.

C. Approximately 650°F because this is an isenthalpic process.

Approximately Approximately 650°F because this is an isentropic process.

D. Approximately

NAPS 2010 NAPS 2010 NRC NRC RORO Exam Exam 13.

13.

Both Units are Both Units are at at 100% power.

100% power.

Component Cooling Component Cooling pumps 1-CC-P-lA and pumps 1-CC-P-1A 2-CC-P-lA are and 2-CC-P-1A are running.

running.

The following Unit The following Unit 11 alarms alarms are received:

are received:

• 1G-B3, CC 1G-B3, CC HX lA-lB CC HX 1A-1B OUTLET LO CC OUTLET LO FLOW.

FLOW.

• 1C-C4, RCP 1C-C4, RCP 1A-B-C lA-B-C THERM THERM BARR BARR CC Hl/LO FLOW.

CC HI/LO FLOW.

ALL other Unit Unit 11 alarms are clear.

dear.

Which ONE of the following explains the cause of these alarms, AND includes the appropriate operator response?

A. Breaker 15H12, Stub Bus Supply Breaker, inadvertently opened; 1-CC-P-i B.

manually start 1-CC-P-1 B. Breaker 15H12, Stub Bus Supply Breaker, inadvertently opened; 1 -CC-P-i B verify 1-CC-P-1 B automatically starts after 20 seconds.

C. Breaker 15H15H13, 1-CC-P-lA 13, 1-CC-P-1 A Supply Breaker, overcurrent trip; manually start 1-CC-P-1 1-CC-P-i B.

D. 1-CC-P-lA Supply Breaker, overcurrent trip; Breaker 15H13, 1-CC-P-1A verify 1-CC-P-i 1-CC-P-1 B B automatically starts after 20 seconds.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 14.

14.

Given the Given the following following conditions:

conditions:

• Unit 11 was Unit was initially initially at at 100%

100% power.

power.

• An RCS An LOCA occurred.

RCS LOCA occurred.

• The crew The crew tripped tripped thethe Unit Unit and and initiated initiated safety safety injection.

injection.

Plant conditions Plant conditions degraded, degraded, and CDA automatically and COA automatically actuated actuated several several minutes minutes later.

later.

Based on Based on the above sequence the above sequence of of events, events, the the RSHX RSHX SW SW Outlet Outlet Radiation Radiation Monitor Monitor Sample Sample Pumps, Pumps, 1-SW-P-5, 6, 1-SW-P-5, 6, 7, and 8, 7, and 8, started started _ _ _ _ _.

A.

A. immediately after SI SI was initiated.

B.

B. 2 minutes after SI was initiated.

C.

C. immediately after COA CDA actuated.

D.

O. 2 minutes after COACDA actuated.

NAPS 2010 NAPS 2010 NRC NRC RORO Exam Exam 15.

15.

Unit 11 is Unit is at power.

100% power.

at 100%

The OATC The OATC notesnotes that that all all of of the PRZR Backup the PRZR Backup Heater Heater white white status status lights lights on on the the vertical vertical board board are are ON, ON, and and PRZR pressure is PRZR pressure is 2260 2260 psig and slowly psig and slowly increasing.

increasing.

Assuming no operator action is taken, taken, which ONE of the following identifies the failed channel, AND includes the system response includes response to to this this failure?

A. 1-RC-PT-1444 failed; 1-RC-PT-1444 failed ; the PRZR PRZR spray valves will modulate open.

B. 1-RC-PT-1444 failed;failed ; one PRZR PORV will open.

C. 1-RC-PT-1445 failed;failed ; the PRZR spray valves will modulate open.

D. 1-RC-PT-1445 failed;failed one PRZR PORV will open.

NAPS 2010 NAPS 2010 NRCNRC RO Exam RO Exam 16.

16.

Unit 11 was Unit was initially initially at at 100%

100% power.

power.

A LOCA A LOCA occurred, occurred, andand operators operators have have transitioned transitioned to to 1-E-1, 1-E-1, Loss Loss of of Reactor Reactor or or Secondary Secondary Coolant.

Coolant.

The following The following conditions conditions exist:

exist:

• RCS pressure RCS pressure is 450 psig is 450 psig and and decreasing decreasing slowly.

slowly.

• SG pressures are SG pressures are 800 800 psig and decreasing psig and decreasing slowly.

slowly.

• CETC5 are CETCs are 580°F 580°F and and decreasing.

decreasing.

• RCS loop RCS loop cold-leg cold-leg temperatures temperatures are are 290°F 290°F and and decreasing.

decreasing.

Based on these conditions, which ONE of the following identifies ALL of the systems that are providing cooling water to the core, AND includes the status of natural circulation?

A. High Head SI flow AND Low Head SI flow; natural circulation is occurring B. High Head SI flow AND Low Head SI flow; natural circulation is NOT occurring C. ONLY High Head SI flow; natural circulation is occurring D. ONLY High Head SI flow; natural circulation is NOT occurring

NAPS 2010 NAPS 2010 NRC NRC RO RO ExamExam 17.

17.

The Solid The Solid State State Protection Protection System System slave slave relays relays are are powered powered from 120VAC 12OVAC Vital busses.

busses.

Train "A" Train A is is powered powered from , and and Train Train "B" B is is powered powered from _ _ _ __

A.

A. busses II and busses and IIII;; busses busses III Ill and and IV IV B. busses II and III Ill;; busses II and IV C. bus I ONLY; bus III III ONLY D. bus II ONLY; bus IV ONLY

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 18.

18.

Which ONE Which ONE of the following of the following reactor reactor trips trips isis designed designed to to protect protect the the core from aa Departure core from Departure from from Nucleate Nucleate Boiling condition?

Boiling condition?

A.

A. Overpower Delta Overpower Delta TT B.

B. Overtemperature Delta Overtemperature Delta TT

c. Pressurizer High C. Pressurizer Level High Level D.

D. Steam Generator Low-Low Low-Low Water Level Level

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 19.

19.

Which ONE Which ONE of the following of the following identifies identifies the the source source of control power of control power for for the the breaker breaker for for 1-SI-P-1A, 1-SI-P-lA, "A" A Low Low Head Safety Injection Pump?

Head Safety Injection Pump?

A.

A. 12OVAC Vital 120VAC Vital bus bus 1-11-I B.

B. 12OVAC Vital 120VAC Vital bus 1-Ill bus 1-111 C.

C. 125VDC Vital 125VDC Vital bus bus 1-11-I D.

D. 125VDC Vital bus 125VDC bus 1-111 1-Ill

NAPS 2010 NAPS 2010 NRC NRC RO RD Exam Exam 20.

20.

Given the Given the following following conditions:

conditions:

• Unit 11 was Unit was initially initially at at 100% power.

100% power.

• Reactor trip Reactor and SI trip and occurred due SI occurred due to large-break LOCA.

to aa large-break LOCA.

• A loss A loss of inventory outside of inventory outside containment containment isis occurring occurring and and the the crew crew is is unable unable to to isolate isolate it.it.

• RWST level RWST level isis continuing continuing to to decrease.

decrease.

Which ONE Which ONE of the following of the following identifies identifies the RWST level the RWST level setpoint setpoint atat which which automatic automatic swapover swapover to to Containment Sump Containment Sump willwill occur occur ANDAND includes includes the actions actions that that will will prevent prevent the the automatic automatic swapover?

swapover?

A. 16%; reset COA 16%; CDA and push both SI Recirc Recirc Mode Reset Push buttons Pushbuttons B. 16%; reset SI and push both SI Recirc Mode Reset Pushbuttons C. 23% ; reset COA 23%; CDA and push both SI Recirc Mode Reset Push buttons Pushbuttons D.

O. 23%; reset SI and push both SI Recirc Mode Reset Pushbuttons

NAPS 2010 NAPS 2010 NRC NRC RO RD Exam Exam 21.

21.

Which ONE Which ONE of the following of the following identifies identifies the the normal normal power power source source toto Unit Unit 11 Individual Individual Rod Rod Position Position Indication Indication (IRPI) System, includes the (lRPI) System, AND includes the system system response response inin the the event event of of aa loss loss of of that that power power supply?

supply?

A.

A. MCC1HI-1; MGG 1H 1-1 ;

The Unit The Unit 11 IRPI IRPI System System will will have have power power for for an an indefinite indefinite period period of of time.

time.

B.

B. MCC1H1-1; MGG 1H1-1; The Unit The Unit 11 IRPI IRPI System System will will have have power power for for aa limited limited period period of of time.

time.

C.

G. MCC1J1-1; MGG 1J1-1; Unit 11 IRPI The Unit IRPI System will have power power for an indefinite indefinite period of time.

D.

D. MCC1J1-1; MGG 1J1-1; The Unit 11 IRPI System will have have power for a limited period of time.

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 22.

22.

Unit 11 isis at Unit at 100%

100% power.

power.

AA total total loss loss of CC flow of CC flow has occurred, and has occurred, and the the crew crew entered entered 1-AP-15, 1-AP15, Loss Loss ofof Component Component Cooling.

Cooling.

Which ONE Which ONE of of the following identifies the following identifies the the component component that that will will reach reach its its temperature temperature limit limit the the soonest soonest for for this event, includes this event, AND includes the maximum the maximum temperature temperature that that isis allowed allowed byby 1-AP-15 1-AP-15 before before aa reactor reactor trip trip isis required?

required?

A.

A. RCP pump RCP pump radial radial bearing; bearing; 195°F 195°F B.

B. RCP pump RCP pump radial radial bearing; bearing ; 225°F 225°F C. RCP C. RCP motor motor bearings; bearings; 195°F 195°F D.

D. RCP motor RCP motor bearings; bearings ; 225°F

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 23.

23.

Given the Given following conditions:

the following conditions:

• Unit 11 is Unit in mode is in mode 3.3.

• Power Range Power Range channel channel N-44 N-44 isis tagged tagged out.

out.

• A loss A loss ofof 120VAC 12OVAC Vital Vital bus 1-Ill occurs.

bus 1-111 occurs.

Based on Based on these conditions, which these conditions, which ONE ONE of of the the following following identifies identifies the the response response of of the the Source-range Source-range Nls, Nis, AND includes the reason?

Source-range channel(s) _ _ _ _ _ _ __

A.

A. N-31 only jy will be de-energized due to the P-10 P-1O permissive.

B. N-31 and N-32 will both be de-energized due to the P-10 P-1O permissive.

C. N-31 only will be de-energized due to the P-6 permissive.

D. N-31 and N-32 will both be de-energized due to the P-6 permissive.

NAPS 2010 NAPS 2010 NRC NRC RO Exam RO Exam 24.

24.

Given the Given following conditions:

the following conditions:

• Unit was initially Unit 11 was initially at at 100%

100% power power with H EDG with 11 H EDG tagged tagged out.

out.

• A loss A loss ofof offsite offsite power power occurred, occurred, and and 11J J EDG EDG locked locked out.

out.

• Operators implemented Operators implemented 1-ECA-O.O, 1-ECA-0.0, Loss Loss ofof All All AC Power.

AC Power.

• Power was Power was restored restored to to one one emergency emergency bus bus from from the the SBO SBO Diesel.

Diesel.

The crew The crew transitioned transitioned to 1 -ECA-0.2, Loss to 1-ECA-0.2, Loss of of All AC Power Power Recovery Recovery with SI SI Required, Required, Step Step 1.

1.

The following following conditions conditions exist:

• Containment pressure is 18 18 psia and slowly increasing.

• pressure is 1100 RCS pressure 1100 psig and stable.

• CETCs are 1300°F and slowly increasing.

• RVLIS is oscillating between 64% and 68%.

RVLlS Based on these conditions, which ONE of the following identifies the procedural flowpath the crew will take to mitigate this event?

A. Immediately transition to 1-FR-C.1, 1-FR-Cl, Response to Inadequate Core Cooling; once the core cooling function is restored, return to 1-ECA-0.2, Step 1.

B. Immediately transition to 1-FR-C.2, 1-FR-C.2, Response to Degraded Core Cooling; once the core coolingCOOling function is restored, return to 1-ECA-0.2, 1-ECA-0.2, Step 1. 1.

C. Continue performing 1-ECA-0.2; transition to 1-FR-C.l 1-FR-C.1 when directed by 1-ECA-0.2.

1-ECA-0.2.

D. Continue performing 1-ECA-0.2; 1-ECA-0.2; transition to 1-FR-C.2 1-FR-C.2 when directed by by 1-ECA-0.2.

1-ECA-0.2.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 25.

25.

loss of IfIf aa loss chilled water of chilled water occurs, occurs, must be must be aligned aligned to to the the CARFs CARFs in in order order to to prevent prevent containment temperature containment temperature from from exceeding exceeding the the Technical Technical Specification Specification limit of _ _ _ __

limit of A.

A. Component Cooling Component Cooling Water; Water; 105°F 105°F B. Component B. Component Cooling Cooling Water; Water; 115°F 115°F C. SeN C. Service Water; 105°F ice Water; 105°F D. SeNice D. Service Water; 115°F 115°F

NAPS 2010 NAPS 2010 NRC NRC RO RO ExamExam 26.

26.

Given the Given following conditions:

the following conditions:

• Unit 11 is Unit on RHR, is on RHR, and and has has just just entered entered Mode Mode 55 for for aa scheduled scheduled refueling refueling outage.

outage.

• Unit 221s Unit at 100%

is at 100% power.

power.

• Unit 11 has Unit has one one CC CC pump pump and and one one SW SW pump pump running.

running.

• Unit 22 has Unit has two two CC pumps and CC pumps two SW and two SW pumps pumps running.

running.

• All Service All Service Water Water spray spray arrays arrays are are in in service.

service.

Unit experiences a catastrophic failure Unit 22 experiences failure of the "A" A Main Main Steam Steamline line inside Containment.

Containment.

Which ONE of the following describes the initial Which itial effect effect of this event on Unit 11 RHR temperature, AND includes the reason?

includes RHR temperature will _ _ _ __

A.

A. increase due to the decrease in total CC flow.

increase B.

B. increase due to the decrease in total SW flow.

C.

C. decrease due to the increase in total CC flow.

D. decrease due to the increase in total SW flow.

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 27.

27.

Given the Given the following following conditions:

conditions:

• Unit was initially Unit 11 was initially at at 100%

100% power power with with Quench Quench Spray Spray pump pump 1-QS-P-1 1-QSP-1B B tagged tagged out.

out.

• A LOCA occurred A LOCA occurred 77 minutes minutes ago.

ago.

The crew The crew is is performing performing 1-E-0, 1-E-0, Reactor Reactor Trip Trip or Safety Injection, or Safety Injection, Attachment Attachment 2, 2, Verification Verification of of Phase Phase BB Isolation.

Isolation.

The crew The crew notes notes the the following following indications:

indications:

• 1-QS-MOV-102A, Chemical 1-QS-MOV-102A, Chemical Addition Tank Outlet Valve, GREENGREEN and RED RED lights lights both both OFF.

OFF.

• 1-QS-MOV-102B, Chemical 1-QS-MOV-102B, Chemical Addition Tank Tank Outlet Outlet Valve, Valve, GREEN GREEN light light ON, ON, RED RED light light OFF.

OFF.

• 1-QS-LI-101, Chemical Addition Tank Level, 90% and stable.

1-QS-U-101, Which ONE of the following describes the action required by 1-E-0, Attachment 2, AND includes the consequence if the above malfunction is not corrected?

A. Locally open 1-QS-MOV-102A, Chemical Addition Tank Outlet Valve; reduced boron concentration of containment sump water.

B.

B. Locally open 1-QS-MOV-102A, Chemical Addition Tank Outlet Valve; reduced effectiveness of containment Iodine removal.

C. Manually open 1-QS-MOV-102B, Chemical Addition Tank Outlet Valve; reduced boron concentration of containment sump water.

D. Manually Manually open 1-QS-MOV-102B, 1-QS-MOV-102B, Chemical Addition Tank Outlet Valve; reduced effectiveness of containment Iodine removal.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 28.

28.

In the In the event event that CC isis lost that CC lost and and cannot cannot be readily restored, be readily restored, 1-AP-15, 1-AP-15, Loss Loss of of Component Component Cooling, Cooling, will will direct the direct the operator operator to to align align to the to the Fuel Fuel Pit Pit Coolers.

Coolers.

A.

A. Chilled Water Chilled Water B.

B. Fire Protection Fire Protection Water Water C. Primary Grade C. Primary Grade Water Water D. Service D. Service Water

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 29.

29.

Given the Given the following following conditions:

conditions:

• Unit 11 isis at Unit at 30%

30% power power and and holding holding for for chemistry.

chemistry.

• The block The block valve valve for for 1-RC-PCV-1455C, 1-RC-PCV-1455C, PRZR PRZR PORV, PORV, isis closed.

closed.

1-RC-PC-1444J, PRZR 1-RC-PC-1444J, PRZR Master Master Pressure Pressure Controller, Controller, fails fails to to 100%

100% demand demand and and will will not not swap swap to to MANUAL.

MANUAL.

In response In response toto this this event, event, the the crew crew will will _ _ _ _ __

A.

A. manually open manually open sprayspray valves valves to prevent cycling to prevent cycling aa PRZR PRZR PORV.PORV.

B.

B. manually open manually open sprayspray valves to prevent aa reactor to prevent reactor trip.

trip.

C.

c. manually close spray valves to prevent a turbine run manually runback.

back.

D.

D. manually close spray valves to prevent a reactor trip.

manually

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 30.

30.

Containment Purge Containment Purge isis inin service serviceon on Unit Unit 1.1 Which ONE Which ONE of of the the following following identifies identifies conditions conditions that will automatically that will automatically isolate isolate Containment Containment Purge?

Purge?

AA. 1-RM-RMS-159, 1-RM-RMS-159, Containment Containment Particulate Particulate Radiation Radiation Monitor, Monitor, Hi-Hi Hi-Hi alarm.

alarm.

1-VG-Rl-179-1, MGP 1-VG-RI-179-1, MGP VentVent Stack Stack A A Rad Rad monitor, monitor, HiHi alarm.

alarm.

B.

B. 1-RM-RMS-162, Manipulator 1-RM-RMS-162, Manipulator Crane Crane Radiation Radiation Monitor, Monitor, Hi-Hi Hi-Hi alarm.

alarm.

1-VG-RI-180-1, MGP 1-VG-RI-180-1, MGP Vent Vent Stack Stack BRad B Rad monitor, monitor, HiHi alarm.

alarm.

C. 1-RM-RMS-159, C. 1-RM-RMS-159, Containment Particulate Containment Particulate Radiation Radiation Monitor, Monitor, Hi-Hi Hi-Hi alarm.

alarm.

1-RM-RMS-162, 1-RM-RMS-162, Manipulator Crane Radiation Monitor, Manipulator Crane Radiation Monitor, Hi-Hi Hi-Hi alarm.

alarm.

D.

D. 1-RM-RMS-160, Containment 1-RM-RMS-160, Containment Gaseous Gaseous Radiation Radiation Monitor, Monitor, Hi-Hi Hi-Hi alarm.

1-VG-Rl-180-1, MGP 1-VG-RI-180-1, MGP Vent Vent Stack Stack BRad B Rad monitor, monitor, Hi Hi alarm.

alarm.

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 31.

31.

The Plant The Plant Computer Computer System System (PCS)

(PCS) isis unavailable.

unavailable.

In the In the event event that that the the Main Main Control Control Room Room isis evacuated, evacuated, which which ONEONE ofof the the following following identifies identifies the the instrument used instrument used toto monitor monitor reactor reactor status, status, AND AND includes includes the the location location of of the the indicator?

indicator?

A.

A. Excore Neutron Flux Excore Neutron Monitor System Flux Monitor System Ch.Ch. II;; Emergency Emergency Switchgear Switchgear Room Room B.

B. Excore Neutron Excore Neutron Flux Monitor System Flux Monitor System Ch.

Ch. II ;; Fuel Fuel Building Building C. Source C. Source Range Channel N-31 Range Channel N-31 ; Emergency Emergency Switchgear Switchgear Room Room D. Source D. Source Range Range Channel Channel N-31 N-31 ; Fuel Fuel Building Building

NAPS 2010 NAPS 2010 NRCNRC RO RO ExamExam 32.

32.

Unit 11 isis inin Mode Unit Mode 2.2.

CONTROL POWER AA CONTROL POWER fuse fuse blows blows on on Intermediate Intermediate Range Range Channel Channel N-35.N-35.

Which ONE Which ONE of of the the following following identifies identifies the the plant plant response response for for this this event?

event?

A.

A. N-35 detector N-35 detector will will indicate indicate downscale downscale and and the the reactor reactor will will trip.

trip.

B.

S. N-35 detector N-35 detector will will indicate indicate normally normally and and the the reactor reactor will will trip.

trip.

C.

C. N-35 detector N-35 detector will will indicate indicate downscale downscale andand the the reactor reactor will will NOT NOT trip.

trip.

D.

D. N-35 detector N-35 detector will will indicate indicate normally normally and and the the reactor reactor will will NOT NOT trip.

trip.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 33.

33.

Given the Given the following following conditions:

conditions:

• Unit 11 has Unit has been been shutdown shutdown for for6 days.

6 days.

• Containment purge Containment purge isis inin service service onon Unit Unit 1.1.

• "A" containment air A containment air recirc recirc fan fan (CARF)

(CARF) isis running.

running.

• Core off-load Core off-load isis inin progress.

progress.

The "A" The A CARF CARF trips, trips, and and the the crew crew is unable to is unable restart any to restart any CARF.

CARF.

Which ONE Which ONE of of the the following following describes describes impacts impacts ofof this this failure failure on on the the Radiation Radiation Monitoring Monitoring System, AND on System, AND on the core off-load the core off-load in accordance with in accordance with 1-0P-4.1, 1-OP-4.1, Controlling Controlling Procedure Procedure for for Refueling?

Refueling?

A.

A. 1-RM-RMS-159 and 1-RM-RMS-159 -160, Containment and -160, Containment Particulate Particulate andand Gaseous Gaseous monitors, monitors, are BOTH BOTH inoperable; inoperable; Station Management Station Management approval is required in order to continue continue core core off-load.

B.

B. 1-RM-RMS-160, Containment Gaseous monitor ONLY is inoperable; 1-RM-RMS-160, Station Management Station Management approval is required in order to continue core off-load.

C.

C. 1-RM-RMS-159 and -160, Containment Particulate and Gaseous monitors, are BOTH inoperable; 1-RM-RMS-159 Nuclear Analysis and Fuels approval is required in order to continue core off-load.

Nuclear D.

D. 1-RM-RMS-1-RM-RMS-160, 160, Containment Gaseous monitor ONLY is inoperable; Nuclear Analysis Nuclear Analysis and Fuels approval is required in order to continue core off-load.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 34.

34.

Unit 22 is Unit in aa refueling is in refueling outage outage with with core core on-load on-load in in progress.

progress.

Given the Given the below instruments, which below instruments, which ONE ONE of the following of the identifies ALL following identifies ALL of of the the instruments instruments that that can can cause cause AUTOMATIC actuation AUTOMATIC actuation of of the the Containment Containment Evacuation Evacuation alarm?

alarm?

1) Source Range

1) Source Channel N-31 Range Channel N-31

2) Manipulator Crane

2) Manipulator Crane Radiation Radiation Monitor, Monitor, 2-RM-RMS-262 2-RM-RMS-262

3) Containment Gaseous

3) Containment Gaseous Radiation Radiation Monitor, Monitor, 2-RM-RMS-260 2-RM-RMS-260 A. 1&3 B.

B. 22&3&3 C. 11 only D. 2 only

NAPS 2010 NRC NAPS NRC RO Exam RD Exam 35.

35.

Given the Given the following following conditions:

conditions:

• Unit was at Unit 11 was at 100% power when 100% power when aa 50 50 gpm gpm tube tube leak leak was was identified identified in in "B" B SG.

SG.

• The crew The crew is is performing performing 1-AP-24, 1-AP-24, Steam Steam Generator Generator Tube Tube Leak.

Leak.

Supervisor is at Step 18, The Unit Supervisor 18, Verify Flow from Affected SGs - ISOLATED.

- ISOLATED.

BOP reports The BOP reports that Attachment 3, MSVH Steam Generator Isolation MSVH Steam Isolation Local Local Actions, has has been been initiated, initiated, but has but has NOT NOT been been completed.

Which ONE of the following identifies the crew response, AND includes the reason?

A. Continue with Step 19 and initiate RCS cooldown without delay; B SG.

precludes overfill of "B" B. Continue with Step 19 and initiate RCS cool cooldown down without delay; minimizes offsite dose.

C. Do NOT continue with Step 19, RCS cooldown can NOT be initiated until Attachment 3 is complete; ensures adequate delta-P is maintained between "B" B SG and the unaffected SGs.

0.

D. Do NOT continue with Step 19, RCS cooldown can not be initiated until Attachment 3 is complete; B SG PORV remains available.

ensures "B"

NAPS 2010 NRC RO RD Exam 36.

foIIowinc conditions:

Given the following

• A SG tube rupture has occurred on Unit 1.

• The crew is preparing to initiate RCS depressurization to minimize break flow in accordance with 1-E-3, Steam Generator Tube Rupture.

• Ruptured SG level is OFF-SCALE HIGH.

• All equipment is available and operating as required.

Which ONE of the following describes the action that will be required to initiate RCS depressurization in 1 -E-3?

accordance with 1-E-3?

A. Initiate normal PRZR spray flow.

B. Initiate auxiliary spray flow.

C. Open one PRZR PORV.

D. Open both PRZR PORVs.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 37.

37.

In accordance In accordance with with 1-0P-28.3, 1-OP-28.3, Startup Startup of the Moisture of the Moisture Separator Separator Reheaters, Reheaters, when placing placing the the Reheat Reheat Steam System Steam System in in service, the total rate the total rate of change of of change of the LPLP Turbine Turbine Inlet Inlet (Reheater (Reheater Outlet)

Outlet) temperature temperature should NOT should NOT exceed exceed . This heatup heatup rate rate is is initially initially controlled controlled by by _ _ _ _ _ _ _ __

A. 100°F per 100°F per hour; hour; throttling the MSR FCVsFCV5 from the Benchboard B.

B. 100°F per per hour; throttling the 3-inch bypass valves locally 3-inch bypass C. 150°F per 150°F hour; throttling the MSR per hour; FCVs from the Benchboard MSR FCVs Benchboard D. 150°F per hour; throttling the 3-inch bypass valves locally

NAPS 2010 NAPS NRC RO 2010 NRC RO Exam Exam 38.

38.

An unisolable An unisolable steam steamline break has line break has led led to an excessive to an cooldown of excessive cooldown of the the RCS RCS and and anan ORANGE ORANGE path path onon RCS Integrity.

RCS Integrity.

Which ONE Which ONE of of the following describes the following describes the the area area of of most most concern concern for for the the propagation propagation of of an an existing existing flaw flaw in in the RCS the RCS during this event?

during this event?

A.

A. Plastic deformation Plastic deformation due due to to tensile tensile stresses stresses inin the the reactor reactor vessel vessel upper upper head head area.

area.

B.

B. Brittle fracture Brittle fracture due due to compressive stresses to compressive stresses inin the the reactor reactor vessel vessel hothot leg leg area.

area.

C.

C. Plastic deformation due Plastic due to compressive compressive stresses in in the reactor reactor vessel cold cold leg leg area.

D. Brittle fracture due to tensile stresses in the reactor vessel downcomer beltline beitline area.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 39.

39.

Given the Given the following following conditions:

conditions:

• Unit 11 was Unit initially stable was initially stable at at 50%

50% power.

power.

• RCS TTAVG RCS AVG & & TTREF were initially REF were initially matched matched and and on on program.

program.

An event occurs, An event occurs, which causes causes rods rods toto begin begin stepping stepping IN.

IN.

The crew observes The crew observes the following indications:

the following indications:

• TAVG T AVG is is 568°F.

568°F.

• TREE T REF is 560°F.

• Power Range Channel N-44 is 48%.

Which ONE of the following identifies the correct response to this event AND includes the reason for this response?

A.

A. Place rods in MANUAL because they are moving in response to a N-44 failure.

B.

B. Place rods in MANUAL because they are moving in response to a T REF failure.

TREE C.

C. Leave rods in AUTO because they are moving in response to an increase in steam demand due to aa malfunction in the turbine control system.

D. Leave rods in AUTO because they are moving in response to a decrease in steam demand due to aa malfunction in the turbine control system.

NAPS 2010 NAPS 2010 NRC NRC RO RD ExamExam 40.

40.

Given the Given the following conditions:

following conditions:.

• 1-ECA-0.0, Loss 1-ECA-0.0, Loss of All AC ofAll Power, isis inin progress.

AC Power, progress.

• The crew The crew isis performing performing step step 22, 22, Depressurize Depressurize all all Intact Intact SGs SGs toto 290 290 psig.

psig.

• The BOP The BOP mistakenly mistakenly did did NOT NOT stop stop depressurizing depressurizing SGs SGs atat 290 290 psig.

psig.

• Pressure inin all Pressure all SGs SGs reaches reaches 180180 psig psig before before the the depressurization depressurization isis stopped.

stopped.

What isis the What the potential potential operational operational implication implication that that could could result result from from the the excessive excessive SG SG depressurization?

depressurization?

A.

A. Nitrogen injection Nitrogen injection from from the the accumulators accumulators may may occur, occur, causing causing natural natural circulation circulation flow flow in in the the RCS RCS to to be be interrupted.

interrupted.

B.

B. Excessive RCS Excessive RCS cooldown, cooldown, which couldcould require require transition to to 1-FR-P.1, 1-FR-Fl, Response Response to to Imminent Imminent Pressurized Pressurized Thermal Shock.

Shock.

C.

C. Voiding may occur in the reactor vessel, causing the upper portion of the core to become uncovered uncovered and potentially causing core damage.

D.

D. An undesired automatic Safety Injection signal may occur, complicating other recovery actions that An undesired that are in progress.

are in progress.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 41.

41.

Which ONE Which ONE of of the foflowing identifies the following identifies the the post-accident post-accident instrument instrument required required by by TR TR 3.3.9, 3.3.9, Regulatory Regulatory Guide (RG) 1.97 Instrumentat Guide (RG) 1.97 Instrumentation, JjQ includes ion, AND includes the the TR TR 3.3.9 3.3.9 Mode(s)

Mode(s) of of Applicability?

Applicability?

A. 1-MS-RM-170, A. 1-MS-RM-170, AA Steamline Steamline Radiation Radiation Monitor; Monitor; Mode Mode 11 ONLY.

ONLY.

B.

B. 1-MS-RM-170, AA Steamline 1-MS-RM-170, Steamline Radiation Radiation Monitor; Monitor; Modes Modes 1,2, 1 2, or or 3.

3.

C.

C. 1-SV-RM-121, Condenser 1-SV-RM-121, Condenser AirAir Ejector Ejector Radiation Radiation Monitor; Monitor; Mode Mode 1I ONLY.

ONLY.

D.

D. 1-SV-RM-121 Condenser 1-SV-RM-121, Condenser AirAir Ejector Ejector Radiation Radiation Monitor; Monitor; Modes Modes 1,2, 1, 2, or or 3.

3.

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 42.

42.

Given the following Given the following conditions:

conditions:

• Unit 11 RCS Unit RCS cooldown cooldown isis inin progress progress due due to leakage from to leakage from aa PRZR PRZR manway.

manway.

• A RHR "A" RHR pump pump isis in in service.

service.

• RCS temperature is RCS temperature is 190°F with aa 30°F/Hr 190°F with 30°F/Hr cooldown cooldown rate.

rate.

A loss A loss of of "F" F transfer transfer bus bus occurs.

occurs.

In accordance accordance with 1-AP-11, 1-AP-1 1 LossLoss of of RHR, RHR, in order order to re-establish RHR to re-establish RHR cooling after after the EDG EDG energizes the bus, the the crew bus, the crew is is directed directed to to _ _ _ _ _ _ _ _ _ _ _ __

A. verify "A" A RHR pump pump running, and manually manually adjust 1-CC-MOV-100A 1-CC-MOV-100A & B, CC CC HX Outlet Isolation Valves.

B. B RHR pump automatically starts, and manually adjust 1-RH-HCV-1758, verify "B" 1-RH-HCV-1 758, RHR HX Outlet Valve.

C. manually start "A"A RHR pump, and manually adjust 1-RH-HCV-1758, 1-RH-HCV-1758, RHR HX Outlet Valve.

D.

D. manually start "A"A RHR pump, and manually adjust 1-CC-MOV-100A 1-CC-MOV-100A & B, CC HX Outlet Isolation Valves.

NAPS 2010 NAPS 2010 NRC NRC RORO Exam Exam 43.

43.

Unit 11 is Unit is at at 100%

100% power power when when several several Unit Unit 11 annunciators annunciators are are received.

received.

The OATC The verifies all OATC verifies all critical critical parameters parameters are are stable stable and and on program.

on program.

The crew notes The crew notes thethe following:

following:

• All status All status lights lights on L Panel on "L" Panel are are OFF.

OFF.

• Annunciator 11 P-E4, Annunciator P-E4, C-7 C-7 PERM PERM STMSTM DUMP DUMP ARMED ARMED FROMFROM LOSS LOSS OFOF LOAD, LOAD, is is LIT.

LIT.

Which ONE ONE of the following identifies identifies the 120VAC 12OVAC Vital bus bus that has has lost power, AND includes lost power, includes the action needed to reset needed (clear) 11 P-E4 reset (clear) P-E4 once once power power is is restored?

restored?

A. Vital bus I-IIII-Ill ; momentarily place the Steam Dump Mode Selector in the RESET position.

B. Vital bus I-III I-Ill ;; place both Steam Dump INTLK INTLK switches to OFF/RESET and return to ON.

C.

C. Vital bus I-IV;l-IV; momentarily place the Steam Dump Mode Selector in the RESET position.

D. Vital bus I-IV;l-lV; place both Steam Dump INTLK switches to OFF/RESET and return to ON.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam

44. Given the

44. Given the following following conditions:

conditions:

• • Unit 11 isis at Unit 70% power at 70% power

• B Main "B" Main Feedwater Feedwater (MFW)

(MFW) pump pump isis tagged tagged out out The "c" The C MFW MFW pump pump trips.

trips.

Which ONE Which ONE of of the the following following describes describes the the plant plant response?

response?

(Assume no

. (Assume no operator action.)

operator action.)

A.

A. MFRVs modulate MFRVs modulate open; SG levels open: SG levels continue continue toto decrease.

decrease.

B.

B. MFRVs modulate MFRVs modulate open; open; SG SG levels levels are are maintained maintained onon program.

program.

C.

C. MFRVs and MFRVs and bypass bypass valves valves fully fully open; open; SGSG levels continue continue to to decrease.

decrease.

D.

D. MFRVs and MFRVs and bypass valves modulate modulate open; SG SG levels are maintained on program.

program.

NAPS 2010 NAPS 2010 NRCNRC RO Exam RO Exam 45.

45.

Given the Given the following following conditions:

conditions:

• Unit 11 isis at Unit at 25%

25% power power and and ramping ramping up.

up.

• Unit is in Unit 22 is in aa refueling refueling outage.

outage.

• All Unit 11 SGWLC All Unit SGWLC channels channels are are selected selected to to Channel Channel III III (8lue channel).

(Blue channel).

An l&C Tech An I&C inadvertently equalizes Tech inadvertently equalizes and and isolates 1-FW-FT-1487, Unit isolates 1-FW-FT-1487, Unit 11 "8" B SG Feed Flow SG Feed Flow Transmitter Transmitter (Blue channel).

(8lue channel).

Which ONE Which ONE of of the following describes the following describes the the result result of of the the I&C l&C technicians technicians error?

error? (assume (assume NO NO operator operator action isis taken) taken)

A. B SG level decreases until the turbine automatically trips.

"8" trips.

B.

8. B SG level decreases until the reactor automatically trips.

"8" C. 8 SG level increases until the turbine automatically trips.

"8" D. B SG level increases until the reactor automatically trips.

"8"

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 46.

46.

Given the Given the following following conditions:

conditions:

• Unit 11 experiences Unit experiences aa reactor reactor trip trip and and safety safety injection.

injection.

• 1-FWP-2, Turbine 1-FW-P-2, Turbine Driven Driven AFW AFW pump, pump, will will not operate.

not operate.

The crew The crew performs performs 1-AP-22.1, 1-AP-22.1, Loss Loss of of 1-FW-P-2 1-FW-P-2 Turbine Turbine Driven Driven AFW AFW Pump, Pump, to to feed feed all all three three SG's.

SGs.

Which ONE Which ONE ofof the following identifies the following identifies the the AFW AFW alignment alignment once once 1-AP-22.1 1-AP-22.1 has has been been performed?

performed?

A.

A. 1-FW-P-.3A and 1-FW-P-3A and 1-FW-P.-3B feeding 1-FW-P-38 feeding "A" A SG SG thru thru 1-FW-HCV-100A 1-FW-HCV-100A 1-FW-P-3A and 1-FW-P-3A 1-FW-P-3B feeding "8" 1-FW-P-38 B SG thru 1-FW-HCV-1008 1-FW-HCV-100B 1-FW-P-3A and 1-FW-P-3A 1-FW-P-38 feeding "c" 1-FW-P-3B feeding 0 SG thru 1-FW-HCV-100C 1-FW-HCV-1 000 B.

8. 1-FW-P-3A and 1-FW-P-3B feeding "A" 1-FW-P-38 A SG thru 1-FW-HCV-100A 1-FW-HCV-100A 11-FW-P-3A

-FW-P-3A and 11-FW-P-38

-FW-P-3B feeding "8" B SG thru 1-FW-MOV-1008 1 -FW-MOV-1 0DB 1-FW-P-3A and 1-FW-P-3B feeding "c" 1-FW-P-38 C SG thru 1-FW-HCV-100C 1-FW-HCV-100C C.

C. 1-FW-P-3B feeding 1-FW-P-38 A SG thru 1-FW-MOV-100A "A" 1-FW-MOV-100A 1-FW-P-3B feeding 1-FW-P-38 B SG thru 1-FW-MOV-1008 "8" 1-FW-MOV-100B 1-FW-P-3A 1-FW-P-3A feeding "c" C SG thru 1-FW-HCV-1 000 1-FW-HCV-100C D.

D. 1-FW-P-3A feeding A "A" SG thru 1-FW-MOV-100D 1-FW-MOV-100D 1-FW-P-3B feeding B 1-FW-P-38 "8" SG thru 1-FW-MOV-1008 1-FW-MOV-100B 1-FW-P-3A 1-FW-P-3A feeding C "c" SG thru 1-FW-HCV-1-FW-HCV-100C 1 000

NAPS 2010 NAPS 2010 NRC NRC RO RO ExamExam 47.

47.

Unit 11 isis at Unit at 100% power.

100% power.

Which ONE Which ONE of of the following identifies the following identifies the the response response ifif Vital Vital Bus Bus Inverter Inverter 1-11 fails, AND 1-Il fails, AND includes includes the the Technical Specification Technical Specification implications implications of this malfunction?

of this malfunction?

12OVAC Vital 120VAG Vital bus bus 1-11 1-Il will will be powered automatically be powered automatically from from _ _ __

A.

A. MCC 11H1-1 MGG via aa constant H 1-1 via constant voltage voltage transformer; transformer; Unit Unit 11 is is in in an an info-only info-only action.

action.

B.

B. MCC 11H1-1 MGG via aa constant H 1-1 via constant voltage voltage transformer; transformer; Unit Unit 11 is is in in aa limiting limiting action.

action.

C.

G. MOO 1J1-1 MGG 1J1-1 via a constant voltage transformer; Unit Unit 11 is is in in an info-only action.

D.

D. MOO 1J1-1 MGG 1J1-1 via a constant voltage transformer; Unit 11 is is in in a limiting action.

NAPS 2010 NAPS 2010 NRC NRC RORO Exam Exam 48.

48.

Given the Given the following conditions:

following conditions:

• Both Units Both are at Units are at 100%

100% power.

power.

• Service Water (SW)

Service Water (SW) is is throttled.

throttled.

• Water pumps 1-SW-P-1A Service Water i-SW-P-iA and 1-SW-P-1 1-SW-P-i BB are running.

• All SW Spray MOVs MOVs are open and all SW Spray Spray Bypass Bypass MOVs are closed.

crew notes The crew that SW notes that SW reservoir reservoir level level has has been been decreasing decreasing slowly, slowly, and and currently currently indicates indicates 312 312 feet.

The following conditions exist:

• 1-SW-P-lA discharge pressure is 45psig.

1-SW-P-1A

• i-SW-P-lB 1-SW-P-1 B discharge pressure is 55 psig.

Based on these indications, the leak is on _ _ _ _ _ and the Ultimate Heat Sink is _ _ _ __

A. "A"A Service Water Header; operable B. "A"A Service Water Header; inoperable c.

C. "B" B Service Water Header; operable D. B Service Water Header; inoperable "B"

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 49.

49.

Both Units Both Units are at 100%

are at 100% power.

power.

An electrical An electrical fault fault results results in in aa loss of "c" loss of C RSST.

RSST.

Which ONE Which ONE of of the the following following will will occur occur as result of as aa result of this this event?

event?

A.

A. 1H and 1H and 2J EDGs will 2J EDGs will start start and and load; load; breaker breaker 15G10 15G10 will will remain remain open open B. 1H and 2J EDGs 1H EDGs will start and load; breaker 15G10 15G10 will close C. ONLY 2H 2H EDG will start and and load; breaker 15G1 15G10 0 will remain open D. ONLY 2H EDG will start and load; breaker 15G1 15G10 0 will close

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 50.

50.

Which ONE Which ONE of of the the following following describes describes the operation of the operation the 125VDC of the 125VDC Vital Vital bus bus battery battery chargers?

chargers?

The battery The battery chargers chargers havehave an an adjustable adjustable current current limiter limiter device, device, which which _ _ __

A.

A. opens the opens AC input the AC input breaker breaker ifif AC AC input input current current reaches reaches 275 275 amps.

amps.

B. limits B. limits the maximum AC the maximum input current AC input current to to 275 275 amps.

amps.

C. opens C. opens the the DCDC output output breaker breaker ifif DC DC output output current current reaches reaches 275275 amps.

amps.

D. limits D. limits the the maximum maximum DC DC output output current current to to 275 275 amps.

amps.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 51.

51.

With Unit With Unit 11 at at 100%

100% power, power, thethe 11H 4160V bus H 4160V normal feeder bus normal feeder breaker breaker 15H 11 trips 15H11 trips open, open, and and 11H H EDG EDG re-energizes the re-energizes the bus.

bus.

Per 0-AP-1 Per 0-AP-1 0, Loss of 0, Loss Electrical Power, of Electrical Power, configuring configuring 11 HH bus loads isis done bus loads done as as aa high high priority priority in in order order to ____________________

to A.

A. prevent EDG prevent EDG overload overload in in the the event event of of an an SIICDA.

Sl/CDA.

B.

B. restoration of facilitate restoration of the the emergency emergency busbus from from the the normal normal feeder.

C. ensure loads C. ensure loads that that may may have have automatically automatically started started are are returned returned to to their their pre-event pre-event (standby)

(standby) status.

status.

D. ensure that 11 H bus loads will trip selectively in the event of an SI/CDA. Sl!CDA.

NAPS 2010 NRC RO Exam 52 52.

Given the following conditions:

• A loss of Instrument Air (IA) occurs.

• IA pressure decreases to 0 psig.

Which ONE of the following identifies ALL of the Auxiliary Feedwater System components that can be operated for a limited period of time?

A. (1-MS-TV-111A&

AFW Pump 1-FW-P-2 steam supply valves (1-MS-TV-111A & B) ONLY.

B. AFW HCVs (1-FW-HCV-100A, B, & C) AND AFW PCVs (1-FW-PCV-159A (1-FW--PCV-159A & B) ONLY.

C. 1 -FW-P-2 steam supply valves (1-MS-TV-111A AFW Pump 1-FW-P-2 (1 -MS-TV-i 11 A & B) AND (i-FW-HCV-100A, B, & C) ONLY.

AFW HCVs (1-FW-HCV-100A, D. AFW HCVs (1-FW-HCV-100A, B, & C) AND AFW PCVs (1-FW-PCV-159A (i-FW-PCV-159A & B) AND AFW Pump 1-FW-P-2 steam supply valves (1-MS-TV-111A& B).

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 53.

53.

Which ONE Which ONE of the following of the following describes describes the the impact impact ofof aa failure failure of of 1-RM-LW-110, 1-RM-LW-11O, Clarifier Clarifier Inlet Inlet Radiation Radiation Monitor, and 1-RM-LW-111, Monitor, and 1-RM-LW-1 11, Clarifier Clarifier Outlet Outlet Radiation Radiation Monitor, Monitor, onon the the following following valves?

valves?

1-LW-PCV1 15, LW 1-LW-PCV-115, Effluent to LW Effluent Discharge Canal to Discharge Canal 1-LW-FCV-100, Holdup 1-LW-FCV-100, Holdup Tank Tank Influent lnfluent A failure A failure (HIGH)

(HIGH) of of _ __

A. either A. 1-RM-LW-11O or either 1-RM-LW-110 or 1-RM-LW-111 1-RM-LW-111 will will close close 1-LW-PCV-115 1-LW-PCV-115 ONLY. ONLY.

B.

B. 1-RM-LW-11O or either 1-RM-LW-110 or 1-RM-LW-111 1-RM-LW-111 will close 1-LW-PCV-115 1-LW-PCV-115 and 1-LW-FCV-100.

1-LW-FCV-100.

C. 1-RM-LW-111 will close 1-LW-PCV-115 jjy 1-RM-LW-111 only 1-LW-PCV-115 ONLY.

D. only 1-RM-LW-111 will close 1-LW-PCV-115 pjjy 1-RM-LW-111 1-LW-PCV-115 and 1-LW-FCV-100.

1-LW-FCV-100.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 54.

54.

Given the Given thefollowing following conditions:

conditions:

• WGDT release AAWGDT release isis inin progress.

progress.

• HI and HI and HI-HI HI-HI alarms alarms are are received received onon 1-GW-RM-178-1, 1-GW-RM-178-1, Process Process VentVent RM RM NobleNoble Gas Gas Normal.

Normal.

• The cause The cause of of the the alarm alarm waswas determined determined to to be be the the detector detector spiking.

spiking.

• 1-GW-RM-178-1 indication 1-GW-RM-178-1 indication isis trending trending back back to normal.

to normal.

Which ONE ONE of of the the following following describes describes thethe automatic automatic action action that that the the OATC OATC will verify, AND will verify, AND includes Which includes the the procedural direction given to re-establish the procedural direction given to re-establish the WGDT WGDT release release once once the the detector detector isis operating operating normally?

normally?

A. Verify A. Verify 1-GW-FCV-101, 1 -GW-FCV-1 01 WGDT WGDT to to Process Process Vents, Vents, CLOSED; CLOSED; the WGDT the WGDT release release cancan bebe re-established re-established once once the the OATC OATC verifies verifies the the HI HI alarm alarm clears.

clears.

B.

B. Verify 1-GW-FCV-101, Verify 1-GW-FCV-101, WGDT WGDT to Process Vents, to Process Vents, CLOSED; CLOSED; the WGDT the WGDT release release can can bebe re-established re-established once once the the Instrument Instrument Department Department resets resets thethe HI-HI HI-HI alarm alarm AND restores AND restores the the MGP MGP system system to normal normal range range monitoring.

monitoring.

C.

C. Verify 1-GW-TV-106, Verify 1-GW-TV-106, Equipment Vents, CLOSED; the WGDT the WGDT release release can be re-established re-established once the OATC verifies the HI alarm clears.

D.

D. Verify 1-GW-TV-1 Verify 1-GW-TV-10 6, Equipment Vents, CLOSED; 06, the WGDT release the WGDT release can be re-established re-established once the Instrument Department resets the HI-HI alarm alarm AND restores AND restores the MGP system to normal range monitoring.

NAPS 2010 NAPS NRC RO 2010 NRC RO ExamExam 55.

55.

Per 1-FR-Cl, Response Per 1-FR-C.1, Response to Inadequate Core to Inadequate Core Cooling, Cooling, SGs SGs areare depressurized depressurized at at the the maximum maximum rate rate to to (ultimately) atmospheric (ultimately) atmospheric pressure pressure inin order order to to _ _ _ _ __

A.

A. reduce RCS reduce temperature to RCS temperature collapse steam to collapse steam voids voids in in the reactor vessel the reactor vessel head.

head.

B.

B. reduce SG reduce SG pressure to enable pressure to low-pressure sources enable low-pressure sources of of SG SG feedwater feedwater toto restore restore RCS RCS heat heat sink.

sink.

c. reduce RCS C. reduce RCS temperature temperature to increase thermal to increase thermal driving driving head head for for natural natural circulation.

circulation.

D.

D. reduce RCS reduce RCS pressure pressure to allow allow the the SI SI accumulators accumulators and LHSI pumps and LHSI pumps to inject inject water to the the RCS.

RCS.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 56.

56.

Which ONE Which of the ONE of the following following identifies identifies the the normal normal and and backup backup cooling cooling water water sources sources to to the the Control Control Room Room Chillers?

Chillers?

A.

A. Bearing Cooling Bearing Cooling normally normally supplies supplies both both Units Units Control Control Room Room Chillers; Chillers; either Unit either Unit can can bebe supplied supplied from from Service Service Water Water as as aa backup.

backup.

B.

B. Bearing Cooling Bearing Cooling normally normally supplies supplies both both Units Units Control Control Room Room Chillers; Chillers; ONLY Unit ONLY Unit 11 can can be be supplied supplied from from Service Service Water Water as as aa backup.

backup.

C.

C. Service Water normally Service normally supplies supplies both both Units Units Control Control Room Room Chillers; Chillers; either Unit can be either Unit be supplied from Bearing Bearing Cooling as a backup.

backup.

D. Service Water normally supplies both Units Control Room Chillers; ONLY Unit 11 can be supplied from Bearing Cooling as a backup.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 57.

57.

Which ONE Which ONE of ofthe the following following parameters by itself parameters by itselfcan can be be used used to to discriminate discriminate between between aa voltage voltage regulator regulator malfunction and a grid disturbance?

malfunction and a grid disturbance?

A. Generator A. Generator Megawatts.

Megawatts.

B. Generator B. Generator Megavars.

Megavars.

C. Generator C. Generator Output Output Voltage.

Voltage.

D. Exciter D. Exciter Field Field Current.

Current.

NAPS 2010 NAPS 2010 NRCNRC RO RD Exam Exam 58.

58.

Which ONE Which ONE ofof the the following following identifies identifies the the power power supplies supplies to the Unit to the Unit 11 and and Unit Unit 22 Instrument Instrument Air Air compressors, 1-IA-C-1 compressors, 1-IA-C-i andand 2-IA-C-1, 2-IA-C-i, respectively?

respectively?

1-IA-C-i is 1-IA-C-1 is powered powered fromfrom _ _ _ _ _ , and and 2-IA-C-1 2-IA-C-i is is powered powered fromfrom _ _ _ __

A.

A. 11H Emergency Bus; H Emergency Bus ; 2H 2H Emergency Emergency Bus Bus B.

B. 11H Emergency Bus; H Emergency Bus; 2J2J Emergency Emergency Bus Bus C.

C. 1iJ Emergency Bus; J Emergency Bus ; 2H 2H Emergency Emergency Bus Bus D.

D. 1J Emergency 1J Emergency Bus; Bus; 2J Emergency Emergency Bus Bus

NAPS 2010 NAPS 2010 NRC NRC RO Exam RO Exam 59.

59.

IfIf aa Main Main Transformer Transformer deluge inadvertently actuated, deluge isis inadvertently actuated, the the Electric Electric Fire Fire Pump Pump isis started started by by

______ , and and the the associated associated Main Main Transformer Transformer will will _ _ _ _ __

A.

A. aa limit limit switch switch on on the deluge valve; the deluge valve; de-energize de-energize B.

B. aa limit limit switch switch on on the deluge valve; the deluge valve; remain remain energized energized C. aa pressure C. pressure switch switch on on the fire main; the fire main ; de-energize de-energize D.

D. aa pressure pressure switch on on the fire main; main ; remain remain energized

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 60.

60.

The crew The crew isis preparing preparing for for Unit Unit 11 core core off-load.

off-load.

Which ONE Which ONE of of the following describes the following describes thethe method method specified specified in in 1-PT-91, 1-PT-91, Containment Containment Penetrations, Penetrations, to to control containment control containment penetrations, penetrations, ANDAND includes includes the the approval approval required required to to breach breach aa penetration penetration during during fuel fuel movement?

movement?

Containment penetrations Containment penetrations shallshall be be tagged tagged with with _ _ __

A. Danger tags, Danger and an tags, and SRO or an SRO Shift Manager or Shift Manager may may approve approve breaching breaching aa penetration.

penetration.

B.

B. Danger tags, Danger tags, and and FSRC FSRC approval approval is is required required for for breaching breaching aa penetration.

penetration.

C. Caution/Information tags, and an SRO or Shift Manager may approve breaching a penetration.

Cautionllnformation D.

D. Caution/Information tags, and Caution/Information and FSRC approval is is required for breaching a penetration.

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 61.

61.

InIn accordance accordance with 1-OP-2.1 Unit with 1-0P-2.1, Unit Startup Startup from from Mode Mode 22 to to Mode Mode 1,I during during aa Unit Unit ramp, ramp, all all of of the the following following indications should indications should be be used used to monitor real to monitor real power power EXCEPT EXCEPT _ _ __

A. U0980, A. U0980, Power, Power, Calorimetric Calorimetric B.

B. U1201, Power, U1201, Power, 11 Min MinAvg STM Avg STM C.

C. U 1203, Power, U1203, Power, 11 Min Mm Avg Avg FW FW D.

D. U1231, Power, U1231, Power, 11 Min Avg UFM Mm Avg UFM

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 62.

62.

With Unit 11 at With Unit at 100% power, the 100% power, following conditions the following conditions exist:

exist:

• 1-CW-MOV-1O1D, "D" 1-CW-MOV-101D, D Waterbox Waterbox Inlet Inlet MOV, MOV, indicates indicates mid-position.

mid-position.

• Condenser pressure Condenser pressure isis 2.2 inches Hg 2.2 inches Hg abs.

abs. and and degrading.

degrading.

Which ONE Which ONE of the following of the following identifies identifies thethe immediate immediate operator operator action, action, AND AND includes includes the the action action required required by by i-AP-14, Low Condenser 1-AP-14, Low Condenser Vacuum,Vacuum, to to mitigate mitigate this this event?

event?

A.

A. least two Circulating Water pumps Verify at least running; pumps running; Close 1-VP-18, 1-VP-i 8, Air Ejector Ejector suction valve for 'D' D water box.

box.

B.

B. Verify condenser pressure is is 3.5 inches inches Hg abs or less and stable; Close 1-VP-18, Air Ejector suction valve for 'D' D water box.

C. Verify at least two Circulating Water pumps running; i-CW-MOV-100D, "D" Open 1-CW-MOV-100D, D CW pump Discharge MOV.

D. Verify condenser pressure is 3.5 inches Hg abs or less and stable; Open 1-CW-MOV-100D, 1-CW-MOV-100D, "D" D CW pump Discharge MOV.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 63.

63.

The Backboards The Backboards operator operator isis conducting conducting anan infrequently infrequently performed performed PT.

PT.

One of One of the the steps steps ofof the the procedure procedure is is designated designated IVIV (Independent (Independent Verification).

Verification).

The Backboards The Backboards operator operator feels feels that that CV CV (Concurrent (Concurrent Verification)

Verification) would would be be aa more more appropriate appropriate method method of of verification for the verification for the step.

step.

As the As the OATC, OATC, you review the you review the procedure procedure and concur with and concur with the the Backboards Backboards operator's operators assessment.

assessment.

Which ONEONE of of the the following describes describes the guidance provided provided by by PI-AA-500, Pl-AA-500, Verification Verification Practices, Practices, to to address this issue?

issue?

A. An inactive SRO on shift performing reactivation duties may authorize the use of CV in lieu of IV. IV.

B. A procedure change is is the ONLY acceptable method of changing the type of verification.

C. The Operations Manager MUST grant approval anytime CV is used in lieu of IV.

D. The Shift Manager or SRO may authorize the use of CV in lieu of IV.

NAPS 2010 NAPS NRC RO 2010 NRC Exam RO Exam 64.

64.

Unit 11 was Unit was initially initially at at 100%

100% power.

power.

1-AP-2.2, Fast 1-AP-2.2, Load Reduction, Fast Load Reduction, has has been been entered.

entered.

Which ONE Which ONE of of the following describes the following describes the the sequence sequence of actions that of actions that must must be be performed performed when when aa fast fast load load reduction is reduction required in is required in accordance accordance with with 1-AP-2.2?

1-AP-2.2?

A.

A. 1)

1) Bypass AMSAC Bypass AM SAC 2)

2) Transfer Transfer Rod Rod Control Control to MANUAL MANUAL 3)

3) Feedwater Control Transfer Feedwater Control to to Bypass Bypass FCVs FCVs B.

B. 1)

1) Bypass AMSAC Bypass AMSAC

2) Transfer Feedwater Control to Bypass FCVs

3) Transfer Rod Control to MANUAL C. 1) Transfer Feedwater Control to Bypass FCVs

2) Bypass AMSAC

3) Transfer Rod Control to MANUAL D. 1) Transfer Rod Control to MANUAL

2) Bypass AMSAC

3) Transfer Feedwater Control to Bypass FCVs

NAPS 2010 NAPS 2010 NRCNRC RO RD Exam Exam 65.

65.

Given the Given the following following conditions:

conditions:

• Unit 11 was Unit was initially initially at at 100%

100% power.

power.

• PRZR Pressure Control PRZR Pressure Control Transmitter, Transmitter, 1-RC-PT-1445, 1-RC-PT-1445, failed failed HIGH.

HIGH.

• The crew The crew placed placed thethe control control switch switch for for 1-RC-PCV-1456, 1-RC-PCV-1456, PRZR PORV, in PRZR PORV, in CLOSE.

CLOSE.

• RCS pressure subsequently RCS pressure subsequently returned returned to to 2235 psig.

2235 psig.

• PRT pressure PRT pressure andand temperature temperature havehave stabilized.

stabilized.

Which ONE of the Which the following identifies identifies the Technical Specification implications implications of these plant conditions?

1-RC-PCV-1456 _ _ _ _ _ , and 1-RC-PCV-1456 1-RC-MOV-1 535, PRZR and 1-RC-MOV-1535, PRZR PORV PORV Block Block Valve, _ _ _ __

A. is operable; MUST be closed to comply with Technical Specifications.

Specifications.

B. is operable; is NOT required to be closed to comply with Technical Specifications.

Specifications.

C. is NOT operable; Specifications.

MUST be closed to comply with Technical Specifications.

D. is NOT operable; Specifications.

is NOT required to be closed to comply with Technical Specifications.

NAPS NAPS 2010 2010 NRC NRC RO RO Exam Exam 66.

66.

Given the Given the following conditions:

following conditions:

• Unit 11 isis at Unit at 50%

50% power power and and ramping ramping up up at 0.3%/minute.

at 0.3%/minute.

• 1-CW-P-1D, "0" 1-CW-P-1D, D Circulating Circulating Water Water pump, pump, trips.

trips.

• The crew The crew enters enters 1-AP-13, 1-AP-13, Loss Loss of One or of One or More More Circulating Circulating Water Water Pumps.

Pumps.

Which ONE Which ONE of the following of the following identifies identifies the the guidance guidance provided provided byby 1-AP-13 1AP-13 for for controlling controlling Liquid Liquid Waste Waste releases?

releases?

A. Liquid Waste releases must be immediately secured, and Chemistry Department approval must be obtained prior to resuming them.

obtained B. Liquid Waste releases must be immediately secured, and Health Physics Department approval must be obtained prior to resuming them.

C. Inform Chemistry Department of Circulating Water Pumps status, and they will determine if Liquid Waste releases are required to be secured.

D. Inform Health Physics Department of Circulating Water Pumps status, and they will determine if Liquid Waste releases are required to be secured.

NAPS 2010 NAPS 2010 NRCNRC RO Exam RO Exam 67.

67.

Which ONE Which ONE of the following of the following identifies identifies the the posting posting requirements, requirements, AND AND includes includes the MINIMUM entry the MINIMUM entry requirements for an area accessible requirements for an area accessible to individuals, in to individuals, in which which radiation radiation levels levels could could result result in in an an individual individual receiving aa deep receiving deep dose dose equivalent equivalent in in excess excess of of 100 100 mrem mrem in in one one hour hour at at 30 30 centimeters centimeters from from the the source?

source?

A.

A. High Radiation High Radiation Area; alarming dosimetry Area alarming dosimetry (DAD)

(DAD) OR continuous continuous HP HP coverage coverage B.

B. High Radiation High Radiation Area; Area; alarming alarming dosimetry dosimetry (DAD)

(DAD) ANDAND continuous continuous HP HP coverage coverage C.

C. Locked High Locked Radiation Area; High Radiation Area ; alarming dosimetry (DAD) OR continuous HP HP coverage D.

D. Locked High Locked Radiation Area; High Radiation Area ; alarming alarming dosimetry dosimetry (DAD)

(DAD) AND continuous continuous HPHP coverage coverage

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 68.

68.

Which ONE Which ONE of of the the following following provides provides the correct value the correct value for for the the associated associated Federal Federal Annual Annual Exposure Exposure Limits?

Limits?

Extremities Extremities Skin Skin Lens of Lens of eye eye A.

A. 15 rem/yr 15 rem/yr 50 rem/yr 50 rem/yr 55 rem/yr rem/yr B.

B. 50 rem/yr 50 rem/yr 50 rem/yr 50 rem/yr 15 15 rem/yr rem/yr C.

c. 50 rem/yr 50 rem/yr 15 rem/yr 15 rem/yr 55 rem/yr rem/yr D.

D. 50 rem/yr 50 15 rem/yr 15 15 rem/yr

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 69.

69.

In accordance In accordance with with O-FCA-1, 0-FCA-1, Control Control Room Room Fire, Fire, RCS RCS cooldown cooldown rate rate shall shall be be _ _ _ _ _ _ , andand aa 29-hour hold is NOT required prior to depressurizin 29-hour hold is NOT required prior to depressurizing the RCS g the RCS provided __

provided___ __

A. less A. less than than 15°F/hr 15°F/hr;; at least one at least one CRDM CRDM fanfan isis running.

running.

B.

B. less than less 15°F/hr;; three than 15°F/hr three CRDM CRDM fansfans are are running.

running.

C. less C. less than 50°F/hr;; at than 50°F/hr least one at least CRDM fan one CRDM fan is is running.

running.

D.

D. less than 50°F/hr less 50°F/hr;; three CRDM fans are running.running.

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 70.

70.

Which ONE Which ONE of of the following would the following result inin an would result an emergency emergency event event classification classification inin accordance accordance with with the the EAL EAL Matrix?

Matrix?

A. RCS A. RCS identified identified leakage leakage isis determined determined to to be be 8.3 8.3 gpm.

gpm.

B.

B. Unit 11 enters Unit enters TS TS 3.0.3.

3.0.3.

C. An unconfirmed C. An unconfirmed security security threat threat is is received.

received.

D. Offsite power D. power was was lost lost one hour ago one hour and has ago and has not not been been restored.

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 71.

71.

Giventhe Given thefollowing followingconditions:

conditions:

• Unit 11 tripped Unit tripped from from 100%

100% power powerdue due toto aa spurious spurious safety safety injection.

injection.

• The crew The crew has has transitioned transitioned toto 1-ES-1.1, 1-ES-li, SI SI Termination.

Termination.

The OATC The OATC isis performing performing Step Step 1,1 Reset Reset Both Both Trains Trains of ofSI, SI, and and notes notes that that annunciator annunciator 11P-H2, P-H2, AUTO AUTO SISI BLKD TRNS A&B, is BLKD TRNS A&B, is FLASHING. FLASHING.

Which ONE Which ONE of of the the following following identifies identifies the the SSPS SSPS status, status, AND AND includes includes thethe action action the the crew crew should should take?

take?

A. BOTH A. BOTH trains trains of of SSPS SSPS havehave failed failed to RESET:

to RESET; reset both reset both trains trains by closing and by closing and then then opening opening Reactor Reactor Trip Trip Breakers Breakers to to clear clear the the seal-in.

seal-in.

B.

B. BOTH trains BOTH trains of of SSPS SSPS have have failed failed to to RESET; RESET:

place both trains of SSPS in place both trains of SSPS in TEST and and locally locally reset reset BOTH BOTH trains.

trains.

C.

C. ONE train ONE train of of SSPS SSPS has failed to RESET; RESET:

reset the affected reset the affected train by closing and then opening Reactor Trip Breakers Breakers to clear thethe seal-in.

seal-in.

D.

D. ONE train ONE train ofof SSPS SSPS has failed to RESET; place the place the affected affected train train of SSPS in TEST and locally reset the affected train.

NAPS NAPS 20102010 NRC NRC RO RO Exam Exam 72.

72.

Given the Given the following following conditions:

conditions:

• Unit 11 was Unit was initially initially at at 100%

100% power power with 1-FW-P-2 tagged with 1-FW-P-2 tagged out.

out.

• A Reactor A Reactor TripTrip occurred, occurred, and and multiple failures have multiple failures have resulted resulted inin aa loss loss of of all all AFW AFW pumps.

pumps.

• The crew The crew hashas transitioned transitioned to 1-FR-Hi, Response to 1-FR-H.1, Response to to Loss Loss of of Secondary Secondary Heat Heat Sink.

Sink.

Attempts to Attempts start aa MFW to start MEW pump pump proved proved unsuccessful, unsuccessful, andand the the crew crew is is attempting attempting to to establish establish SG SG feed feed flow flow from the from the Condensate Condensate system.system.

Which ONE of of the following following describes describes how how conditions conditions are are established established to feed from from the the Condensate Condensate system, AND includes system, AND includes thethe reason?

reason?

A.

A. Depressurize ONLY one SG to reduce the probability of a PTS condition.

B. Depressurize ONLY one SG to maximize time before bleed and feed criteria are met.

C. Depressurize ALL SGs to ensure even cooling of the RCS.

D. Depressurize ALL SGs to minimize the probability of an undesired SI actuation.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 73.

73.

Following aa large-break Following large-break LOCA, LOCA, thethe crew crew has has completed completed 1-ES-1.3, 1-ES-i .3, Transfer Transfer to to Cold Cold Leg Leg Recirculation, Recirculation, Step 9, Step Align SI 9, Align SI System System ForFor Cold Cold Leg Leg Recirculation.

Recirculation.

The following The following conditions conditions exist:

exist:

• Amps and Amps and flow flow are are oscillating oscillating on on both both Low-head Low-head SI SI pumps.

pumps.

• The ST The STA reports that A reports that aa RED RED path path exists exists on on heat heat sink.

sink.

Which ONE Which ONE of the following of the following describes describes thethe correct actions AND implementation correct actions implementation of of procedures procedures for for these these conditions?

conditions?

A.

A. Perform 1-ES-1.3, Perform i-ES-i.3, Attachment 3, Containment Sump Screen Blockage or Loss Loss of Suction; implement 1-FR-H.1, Do NOT implement 1-FR-Hi, Response to Loss of Secondary Heat Sink, Sink, until directed in 1-E-1, i-E-i, Loss of Reactor Loss Reactor or Secondary Secondary Coolant.

Coolant.

B. 1-ES-1.3, Attachment 3, Containment Sump Screen Blockage or Loss of Suction; Perform 1-ES-1.3, Do NOT implement 1-FR-H.1,i-FR-F-l.1, Response to Loss of Secondary Heat Sink, until directed in i-ECA-i.1, Loss of Emergency Coolant Recirculation.

Attachment 3 OR 1-ECA-1.1, Recirculation.

C.

C. Immediately transition to 1-FR-H.1, 1-FR-Hi, Response to Loss of Secondary Heat Sink.

D. Immediately transition to 1-ECA-1.1, Loss of Emergency Coolant Recirculation. Recirculation.

NAPS 2010 NAPS 2010 NRCNRC RO RO Exam Exam 74.

74.

Given the Given the following following conditions:

conditions:

• Unit was initially Unit 11 was initially at 100% power.

at 100% power.

• B SG "8" faulted inside SG faulted inside Containment.

Containment.

• The crew The crew isis unable unable to terminate SI, to terminate SI, and and have have determined determined that that "8" B SG SG isis also also ruptured.

ruptured.

The crew The crew hashas completed completed the the appropriate appropriate EOP EOP transitions, transitions, and and is is now now performing performing 1-ECA-3.1, 1 -ECA-3. 1, SGTR SGTR With With Loss of Loss Reactor Coolant of Reactor Coolant - Subcooled

- Subcooled Recovery Recovery Desired.

Desired.

The ST The STA reports the A reports following:

the following:

• RWST Level RWST Level is is 38%

38% and slowly decreasing.

• There is There is an an ORANGE ORANGE Path Path on on Containment Containment Sump Sump Level Level (sump (sump level level is is 11 11 feet feet and and slowly slowly increasing).

• There are no other RED or ORANGE paths.

Which ONE of the following identifies the appropriate procedure transitions for these conditions?

A.

A. DO NOT transition to 1-FR-Z.2, DO i-FR-Z.2, Response to High Containment Sump Level; remain remain in 1-ECA-3.1 i-ECA-3.i and continue recovery actions.

B.

8. DO DO NOT transition to i-FR-Z.2, 1-FR-Z.2, Response to High Containment Sump Level; transition transition to 1-ES-1.3, 1-ES-i .3, Transfer to Cold Leg Recirculation Recirculation..

C.

C. Transition Transition to i-FR-Z.2, 1-FR-Z.2, Response to High Containment Sump Level, to identify identify the source of of water:

then return to 1-ECA-3.1 1-ECA-3.1 and continue recovery actions.

D.

D. Transition Transition to 1-FR-Z.2, 1-FR-Z.2, Response to High High Containment Containment Sump Sump Level, Level, to to identify identify thethe source source of of water; transition to i-ES-i transition to 1-ES-1.3, .3, Transfer Transfer toto Cold Cold Leg Leg Recirculation Recirculation..

NAPS 2010 NAPS 2010 NRC NRC RO RO Exam Exam 75.

75.

Given the Given following conditions:

the following conditions:

• Unit 11 core Unit core off-load off-load is is in progress.

in progress.

• A recently-irradiated fuel A recently-irradiated fuel assembly assembly drops drops while while placing placing itit into into the the containment containment upender.

upender.

• Bubbles are Bubbles coming to are coming to the surface of the surface of the the reactor reactor cavity.

cavity.

The following The radiation monitors following radiation monitors are are in in alarm:

alarm:

• 1-RM-RMS-159, Containment 1-RM-RMS-159, Containment GaseousGaseous RIM.R/M.

• 1 -RM-RMS-1 60, Containment 1-RM-RMS-160, Containment Particulate Particulate RIM.

R/M.

• 1-RM-RMS-162, Manipulator 1-RM-RMS-162, Manipulator CraneCrane Area RIM. R/M.

Based on these conditions, which ONE of the following describes actions that will initially be required in accordance with O-AP-30, 0-AP-30, Fuel Failure During Handling?

A. Place Fuel Building ventilation in service through the charcoal filters; evacuate the Containment only.

B.

B. Place Fuel Building ventilation in service through the charcoal filters; evacuate the Fuel Building and Containment.

the Containment.

C. Manually initiate Control Room bottled air dump; evacuate the Containment only.

D. Manually initiate Control Room bottled air dump; evacuate the Fuel Building and the Containment. Containment.

AF j

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