ML102110192
| ML102110192 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/16/2010 |
| From: | Division of Nuclear Materials Safety II |
| To: | |
| References | |
| Download: ML102110192 (105) | |
Text
FAC FAC! ,- AME:E: North North Anna Anna Section 9 REP 1
REP UMBER: ER: 05000338/2010301 AND 05000339/2010301 05000338/2010301 AND 05000339/2010301 flNAL I L SRO WRITTEN EXAM CONS CON Vinal SRO V::inal as given' RO Written Exam (25 'as given questions with changes made uring ring administration annotated)
R2ference Handouts Provided To Applicants R::ference VA-swer
-/ A swer Key Loca Loca' f ectronic FHes:
'ectroni Files:
Submi Submi: v: _ _ _ _ _ _ _ Verified By: By: _ _ _ _ _ _ _ __
ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet US. Nuclear Regulatory Commission U.S.
Site-Specific SRO Written Examination Applicant Information Name:
Date: 06/16/10 Facility/Unit: North Anna Units 11 &
&2 Region: 10 I LI ii [I II[{] 1110 Ill LI IVL]
IVO Reactor Type: WI1 W[{] CE 0LI BW 0LI GEO GELI Start Time: Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO SRQ portion.
Applicant Certification All work done on this examination is my own. II have neither given nor received aid.
Applicants Applicant's Signature Results 75 25 100 100 RO/SRO-Only/Total Examination Values - - I/ - - / - - Points Applicants Applicant's Scores -- / -- / -- Points Applicants Applicant's Grade -- / -- / -- Percent ES-401, Page 31 of 33
Given the following conditions:
- Unit 1us is at MOL, starting up following a forced outage.
- The crew has just completed taking critical data.
- The OATC pulls rods to establish a positive startup rate.
When the OATC releases the IN-HOLD-OUT switch, rods continue to step outward.
Assuming NO operator actions are taken, which ONE of the following identifies the plant response to this event?
Power will increase to _ _ _ _ _ . The power increase is terminated by the _ _ _ __
A. 30%; Intermediate Range rod stop signal.
B. 30%; Power Range rod stop signal.
C. 25%; Intermediate Range reactor trip signal.
D. 25%; Power Range reactor trip signal.
NAPS 2010 NRC NAPS NRC SRO Exam Exam 2.
Plant conditions are as follows:
Plant
- The crew is preparing to roll Unit 1I turbine.
- Reactor power is 8%.
- Turbine power is 0%.
- RCS TAVG is 551°F.
RCSTAVGi5551°F.
Based on these conditions, PRZR program level is _ _ _ _ , and letdown will automatically isolate if PRZR level decreases to _ _ __
A. 28.4%; 15%
B. 28.4% ; 23.4%
28.4%;
C. 32.7%; 15%
D. 32.7% ; 27.7%
32.7%;
Given the following conditions:
- 1 is starting up following a mid-cycle forced outage.
Unit 1
- The crew has commenced slowly raising power in preparations for rolling the turbine.
At approximately 4% power, "B" B RCP trips.
Which ONE of the following identifies the effect of the RCP trip on the Departure from Nucleate Boiling Ratio (DNBR), AND includes the procedurally required action the crew will take to mitigate this event?
A. DNBR has decreased; 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 />.
B. DNBR has decreased; decreased ; trip the reactor.
C. 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 />.
DNBR has increased; D. increased ; trip the reactor.
DNBR has increased;
NAPS 2010 NRC NAPS NRC SROSRO Exam Exam 4.
1-CH-P-1A, seems to be making The Auxiliary Building Operator reports that the running charging pump, 1-CH-P-1A, some unusual noises.
Which ONE of the following identifies the PCS parameter that can be trended by the OATCs to evaluate 1-CH-P-1A?
the status of 1-CH-P-1A?
A. Cubicle Temperature.
B. Inboard Pump Bearing Temperature.
C. Gear Box Cooler Outlet Service Water Temperature.
D. Lube Oil Cooler Service Water Outlet Flow.
Unit 1I is at 100% power with the following charging pump configuration:
- 1-CH-P-1A is running.
- 1-CH-P-1B is in AUTO.
- 1-OH-P-iC is tagged out for breaker inspections.
1-CH-P-1C The OATC notes the following indications:
- 1-CH-Pl-1121, Discharge Header Pressure - erratic.
1-CH-PI-1121, -
- 1-CH-Fl-1 122, Charging Flow - erratic.
1-CH-FI-1122, -
- 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 and 1-CH-P-1A place 1-CH-P-1B 1-OH-P-IA in PTL, then vent and start 1-CH-P-1B.
1-OH-P-i B.
B. 1-OH-P-IA; Gas binding of 1-CH-P-1A; i-OH-P-lB and stop 1-CH-P-1A, start 1-CH-P-1B 1-OH-P-iA, then vent 1-CH-P-1A.
1-OH-P-IA.
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-OH-P-IA discharge MOVs, then start 1-CH-P-1 1-CH-P-IB.
B.
D. 1-OH-P-IA; Relief valve stuck open on 1-CH-P-1A; 1-OH-P-IB, then stop 1-CH-P-1Aand start 1-CH-P-1B, 1-OH-P-lA and close 1-CH-P-1Adischarge 1-CH-P-IA discharge MOVs.
Given the following conditions:
- RCS temperature is 175°F.
- RCS pressure is 305 psig.
- The PRZR is solid.
- Charging flow control is in manual.
- 1-RH-FCV-1605, RHR H/X HIX bypass, is in AUTO.
A RHR heat exchanger suddenly develops a 150 gpm tube leak.
The "A" Which ONE of the following identifies the effect of this malfunction on RHR Q.!d!JJ.Q 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; RCS pressure decreases C. RHR pump flow increases; RCS pressure remains the same D. RHR pump flow increases; RCS pressure decreases
Unit 11 was at 100% power when a small-break LOCA occurred. The crew is currently performing 1-E-1, Loss of Reactor or Secondary Coolant.
Be Terminated.
The Unit Supervisor is at step 6, Check if SI Can 8e The following conditions exist:
- Containment pressure is 22 psia and slowly decreasing.
- RCS pressure is 1085 psig and slowly increasing.
- PRZR level is 30% and slowly increasing.
- CETCs are 490°F and stable.
- RCS loop hot-leg temperatures are 475°F and stable.
- 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 is indicating correctly; are NOT met "A"
C. B ICCM is indicating correctly; are met "8"
D. B ICCM is indicating correctly; are NOT met "8"
Given the following conditions:
- Unit 11 is at 50% power.
- B and "c" "B" C MFW pumps are tagged out.
- A MFW "A" MEW pump trips.
The OATC attempted to trip the reactor, but the reactor trip breakers did NOT open.
Assuming NO additional operator actions are taken, which ONE of the following identifies how the AMSAC System will function to mitigate this event?
AMSAC will open the Rod Drive MG Set _ _ _ __
A. supply breakers immediately after level in 2/3 SGs reaches 13% narrow-range.
B. supply breakers 27 seconds after level in 2/3 SGs reaches 13% narrow-range.
C. output breakers immediately after level in 2/3 SGs reaches 13% narrow-range.
D. output breakers 27 seconds after level in 2/3 SGs reaches 13% narrow-range.
NAPS 2010 NRC NAPS NRC SRO Exam Exam 9.
Unit 11 is at 100%
100% power when annunciator 1lB-Hi, PRZ RELIEF TK HI TEMP, is received.
B-H1, PRZ The OATC confirms the alarm is valid, and notes that PRT level, pressure, and temperature have been slowly increasing since assuming the watch.
Which ONE of the following identifies the source of PRT inleakage that has caused these plant conditions AND includes the flowpath used to drain the heated water from the PRT?
A. Letdown Relief Valve 1-CH-RV-1203 leaking by; PDTT and the POTT PRT is drained to the POTT PDTT is pumped directly to the in-service Boron Recovery Tank.
B. i-CH-RV-1203 leaking by; Letdown Relief Valve 1-CH-RV-1203 PRT is drained to the POTT PDTT and the POTT PDTT is pumped directly to the Gas Stripper.
C. 0-ring leakage; Reactor Vessel Flange O-ring PDTT and the POTT PRT is drained to the POTT PDTT is pumped directly to the in-service Boron Recovery Tank.
D.
O. 0-ring leakage; Reactor Vessel Flange O-ring PDTT and the POTT PRT is drained to the POTT PDTT is pumped directly to the Gas Stripper.
1-OP-li, Unit Startup from Mode 5 Operators are performing 1-0P-1.1, 5 at Less Than 140°F to Mode 5 at Less Than 200°F, in order to establish a steam bubble in the PRZR.
Which ONE of the following identifies the PRZR temperature that operators should expect the steam i-Op-i .i, AND includes the action to be taken once bubble formation begins?
bubble to form as stated in 1-0P-1.1, A. 425°F; throttle closed 1-CH-PCV-1145, i-CH-PCV-1i45, Letdown Pressure Control Valve.
B. 1-CH-PCV-1145, Letdown Pressure Control Valve.
425°F; throttle open 1-CH-PCV-1145, C. i-CH-PCV-i145, Letdown Pressure Control Valve.
450°F; throttle closed 1-CH-PCV-1145, D. i-CH-PCV-1 145, Letdown Pressure Control Valve.
450°F; throttle open 1-CH-PCV-1145,
Both Units are at 100% power.
1-CC-PCV-1 10, Component Clg 1-CC-PCV-110, Cig Pps Recirc Hdr Pressure Control Vv, is 50% open and controlling CC system pressure.
Due to a tagging error, the instrument air supply to 1-CC-PCV-110 is inadvertently closed.
I -CC-PCV-1 10, indicated pressure on 1-CC-PI-100, When instrument air is isolated to 1-CC-PCV-110, 1 -CC-Pl-1 00, CC HX Outlet Pressure, will Pressure, will and 2-CC-PCV-210 will _ _ _ _ _ _ _ __
A. decrease ; throttle closed.
decrease; B. decrease; NOT change position.
C. increase ; throttle open.
increase; D. increase; NOT change position.
Unit 11 is at 100% power.
A PRZR safety valve has indications of leakage.
The following conditions exist:
- PRZR pressure is 2220 psig and slowly increasing.
- PRT pressure is 10 psig and slowly increasing.
Which ONE of the following identifies the expected temperature indication downstream of the safety valve, AND includes the reason for the indication?
A. Approximately 240°F 240° F because this is an isenthalpic process.
B. Approximately 240°F because this is an isentropic process.
c.
C. Approximately 650°F because this is an isenthalpic process.
D. Approximately 650°F 650° F because this is an isentropic process.
Both Units are at 100% power.
1-CC-P-lA and 2-CC-P-1A Component Cooling pumps 1-CC-P-1A 2-CC-P-IA are running.
The following Unit 11 alarms are received:
- lA-B-C THERM BARR CC HI/LO FLOW.
1C-C4, RCP 1A-B-C ALL other 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; manually start 1-CC-P-1 1 -CC-P-I B.
B. 15H12, Breaker 15H 12, Stub Bus Supply Breaker, inadvertently opened; 1-CC-P-I B verify 1-CC-P-1 B automatically starts after 20 seconds.
C. I-CC-P-lA Supply Breaker, overcurrent trip; Breaker 15H13, 1-CC-P-1A 1 -CC-P-l B.
manually start 1-CC-P-1 D. 1-CC-P-lA Supply Breaker, overcurrent trip; Breaker 15H13, 1-CC-P-1A verify 1-CC-P-1 I-CC-P-I BB automatically starts after 20 seconds.
Given the following conditions:
- Unit 11 was initially at 100% power.
- The crew tripped the Unit and initiated safety injection.
Plant conditions degraded, and COA CDA automatically actuated several minutes later.
Based on the above sequence of events, the RSHX SW Outlet Radiation Monitor Sample Pumps, 1-SW-P-5, 6, 7, and 8, started _ _ _ __
A. immediately after SI was initiated.
B. 2 minutes after SI was initiated.
C. CDA actuated.
immediately after COA D.
O. CDA actuated.
2 minutes after COA
Unit 11 is at 100% power.
The OATC notes that all of the PRZR Backup Heater white status lights on the vertical board are ON, and PRZR pressure is 2260 psig and slowly increasing.
Assuming no operator action is taken, which ONE of the following identifies the failed channel, AND includes the system response to this failure?
A. failed ; the PRZR spray valves will modulate open.
1-RC-PT-1444 failed; B. failed ; one PRZR PORV will open.
1-RC-PT-1444 failed; C. 1-RC-PT-1445 failed; failed the PRZR spray valves will modulate open.
D. failed ; one PRZR PORV will open.
1-RC-PT-1445 failed;
Unit 11 was initially at 100% power.
A LOCA occurred, and operators have transitioned to 1-E-1, Loss of Reactor or Secondary Coolant.
The following conditions exist:
- RCS pressure is 450 psig and decreasing slowly.
- SG pressures are 800 psig and decreasing slowly.
- CETCs are 580°F and decreasing.
- RCS loop cold-leg temperatures are 290°F and 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.
C. ONLY High Head SI flow; natural circulation is occurring D. ONLY High Head SI flow; natural circulation is NOT occurring
The Solid State Protection System slave relays are powered from 120VAC 12OVAC Vital busses.
A is powered from Train "A" , and Train "8"
, B is powered from _ _ _ __
A. busses II and IIII;; busses III and IV B.
- 8. busses II and III Ill;; busses II and IV C. bus II ONLY; bus III ONLY D. bus II ONLY; bus IV ONLY
Which ONE of the following reactor trips is designed to protect the core from a Departure from Nucleate Boiling condition?
A. Overpower Delta T B. Overtemperature Delta T c.
C. Pressurizer High Level D. Steam Generator Low-Low Water Level
NAPS 2010 NRC SRO Exam NAPS 19.
19.
Which ONE of the following identifies the source of control power for the breaker for 1-SI-P-1A, 1-SI-P-lA, "A" A Low Low Injection Pump?
Head Safety Injection A. 12OVAC Vital bus 1-1 120VAC 1-I 8.
B. 12OVAC Vital bus 1-111 120VAC 1-Ill C. 125VDC Vital bus 1-1 125VDC 1-I D. 125VDC Vital bus 1-111 1-Ill
NAPS 2010 NRC NAPS NRC SRO Exam Exam 20.
Given the following conditions:
- Unit 1I was initially at 100%
100% power.
- Reactor trip and SI occurred due to a large-break LOCA.
- A loss of inventory outside containment is occurring and the crew is unable to isolate it.
- RWST level is continuing to decrease.
Which ONE of the following identifies the RWST level setpoint at which automatic swapover to Containment Sump will occur AND ffl includes the actions that will prevent the automatic swapover?
A. 16%; reset COACDA and push both SI Recirc Mode Reset Pushbuttons B. 16% ; reset SI and push both SI Recirc Mode Reset Push 16%; Pushbuttons buttons C. 23%; reset COA CDA and push both SI Recirc Mode Reset Push Pushbuttons buttons D. 23% ; reset SI and push both SI Recirc Mode Reset Push 23%; Pushbuttons buttons
NAPS 2010 NAPS 2010 NRC NRC SRO SRO ExamExam 21.
21.
Which ONE Which ONE of the following of the following identifies identifies the normal power the normal power source to Unit source to Unit 11 Individual Individual Rod Rod Position Position Indication Indication (IRPI) System, (IRPI) System, ANDAND includes includes the the system system response response inin the the event event of of aa loss loss of of that power supply?
that power supply?
A. MCC A. MCC1H1-1; 1H1-1; The Unit 11 IRPI The Unit System will IRPI System have power will have power for for an an indefinite indefinite period period of of time.
time.
B.
B. MCC1H1-1; MCC 1H1-1; The Unit 11 IRPI The Unit IRPI System System will will have have power for aa limited power for limited period of time.
period of time.
C. MCC1J1-1; MCC 1J1-1; The Unit Unit 11 IRPI IRPI System System will have have power power for an indefinite period an indefinite period of of time.
time.
D. MCC1J1-1; MCC 1J1-1; IRPI System will have power for a limited period of time.
The Unit 11 IRPI
NAPS 2010 NRC NAPS 2010 NRC SRO SRO Exam Exam 22.
22.
Unit 11 is Unit is at at 100% power.
100% power.
A loss of CC A total loss CC flow has occurred, and has occurred, and the crew entered the crew 1-AP-15, Loss entered 1-AP-15, Loss of of Component Component Cooling.
Cooling.
Which ONE of the following identifies the component that will reach its temperature limit limit the soonest for this event, AND f+/-Q includes the maximum temperature that is allowed by 1-AP-15 1-AP-15 before a reactor trip is required?
required?
A. RCP pump RCP pump radial bearing; 195°F bearing ; 195°F B. bearing ; 225°F RCP pump radial bearing; C. RCP motor bearings; 195°F D. RCP motor bearings; 225°F
NAPS 2010 NAPS 2010 NRC NRC SRO SRO ExamExam 23.
23.
Given the Given the following conditions:
following conditions:
- Unit 11 is Unit is in in mode mode 3.
3.
- Power Range Power Range channel N-44 is channel N-44 is tagged tagged out.
out.
- 12OVAC Vital bus 1-111 A loss of 120VAC 1-Ill occurs.
Based on these conditions, Based conditions, which ONE ONE of the following identifies identifies the response response of the Source-range Nls, NIs, AND includes the reason?
Source-range channel(s) _ _ _ _ _ _ __
A. Qjy will be de-energized due to the P-10 N-31 only 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 jjy 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 NRC NRC SRO Exam 24.
Given the following conditions:
- 100% power with 11H Unit 11 was initially at 100% H EDG tagged out.
- A loss of offsite power occurred, and 1J EDG locked out.
- Operators implemented 1-ECA-0.0, Loss of All AC Power.
- Power was restored to one emergency bus from the SBO Diesel.
The crew transitioned to 1-ECA-0.2, Loss of All AC Power Recovery with SI Required, Step 1.
The following conditions exist:
- Containment pressure is 18 psia and slowly increasing.
- RCS pressure is 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. 1-FR-Cl, Response to Inadequate Core Cooling; Immediately transition to 1-FR-C.1, once the core cooling function is restored, return to 1-ECA-0.2, Step 1.
B. Immediately transition to 1-FR-C.2, Response to Degraded Core Cooling; once the core cooling function is restored, return to 1-ECA-0.2, Step 1.
C. Continue performing 1-ECA-0.2; 1-ECA-0.2.
transition to 1-FR-C.1 when directed by 1-ECA-0.2.
D. 1 -ECA-0.2; Continue performing 1-ECA-0.2; transition to 1-FR-C.2 1-FR-C.2 when directed by 1-ECA-0.2.
1-ECA-0.2.
NAPS 2010 NRC NAPS NRC SRO Exam Exam 25.
IfIf a loss of chilled water occurs, CAREs in order to prevent must be aligned to the CARFs containment temperature from exceeding the Technical Specification limit of _ _ __
A. Component Cooling Water; 105°F B. Component Cooling Water; 115°F C. Service Water; 105°F D. Service Water; 115°F
Given the following conditions:
- Unit 11 is on RHR, and has just entered Mode 5 for a scheduled refueling outage.
- Unit 2 is at 100% power.
- All Service Water spray arrays are in service.
Unit 2 experiences a catastrophic failure of the "A" A Main Steamline inside Containment.
iitial effect of this event on Unit 11 RHR temperature, AND Which ONE of the following describes the initial includes the reason?
RHR temperature will _ _ _ __
A. increase due to the decrease in total CC flow.
B. increase due to the decrease in total SW flow.
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 SRO SRO Exam Exam 27.
27.
Given the Given the following conditions:
following conditions:
- Unit 11 was Unit was initially initially at at 100%
100% power power with with Quench Quench Spray Spray pump pump 1-QS-P-1 1-QS-P-1 BB tagged tagged out.
out.
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 ofof Phase Phase BB Isolation.
Isolation.
The crew The crew notes notes the the following indications:
following indications:
- 1-QS-MOV-102A, Chemical Addition Tank Outlet 1-QS-MOV-102A, Outlet Valve, GREEN GREEN and RED RED lights lights both both OFF.
OFF.
- 1-QS-MOV-102B, Chemical 1-QS-MOV-102B, Chemical Addition Addition Tank Tank Outlet Outlet Valve, Valve, GREEN GREEN light light ON, ON, RED RED light light OFF.
OFF.
- 1-QS-Ll-101, 1-QS-Ll-1 01, Chemical Addition Tank Level, 90% and stable.
Which ONE of the following describes the action required by 1-E-0, Attachment 2, AND includes the Which consequence if the above malfunction is not corrected?
consequence A.
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-1 1-QS-MOV-102B, 02B, Chemical Addition Tank Outlet Valve; reduced boron concentration of containment sump water.
D.
D. Manually open 1-QS-MOV-102B, Chemical Addition Tank Outlet Valve; reduced effectiveness of containment Iodine removal.
NAPS 2010 NAPS 2010 NRCNRC SROSRO Exam Exam 28.
28.
In the In the event event that that CC CC is is lost lost and and cannot cannot be be readily readily restored, restored, 1-AP-15, 1-AP-1 5, Loss Loss of of Component Component Cooling, Cooling, will direct the operator operator to align align to the to Fuel Pit the Fuel Pit Coolers.
Coolers.
A. Chilled A Water Chilled Water B. Protection Water Fire Protection C.
C. Primary Grade Primary Grade Water D. Service Water
Given the following conditions:
- Unit 11 is at 30% power and holding for chemistry.
- 1-RC-PCV-1455C, PRZR PORV, is closed.
The block valve for 1-RC-PCV-1455C, 1-RC-PC-1444J, PRZR Master Pressure Controller, fails to 100% demand and will not swap to MANUAL.
In response to this event, the crew will _ _ _ _ __
A. manually open spray valves to prevent cycling a PRZR PORV.
B. manually open spray valves to prevent a reactor trip.
C. manually close spray valves to prevent a turbine runback.
D. manually close spray valves to prevent a reactor trip.
NAPS 2010 NRC NAPS NRC SRO Exam Exam 30.
Purge is in service on Unit Containment Purge Unit 1.
1.
Purge?
Which ONE of the following identifies conditions that will automatically isolate Containment Purge?
A. 1-RM-RMS-159, Containment Particulate Radiation Monitor, Hi-Hi alarm.
1-RM-RMS-159, 1-VG-Rl-179-1, MGP Vent Stack 1-VG-RI-179-1, StackARad A Rad monitor, Hi alarm.
B. 1-RM-RMS-162, Manipulator Crane Radiation Monitor, Hi-Hi alarm.
1-VG-RI-180-1, MGP Vent Stack BRad B Rad monitor, Hi alarm.
C. 1-RM-RMS-159, Containment Particulate Radiation Monitor, Hi-Hi alarm.
I -RM-RMS-l 62, Manipulator Crane Radiation Monitor, Hi-Hi alarm.
1-RM-RMS-162, D. l-RM-RMS-160, Containment Gaseous Radiation Monitor, Hi-Hi alarm.
1-RM-RMS-160, l-VG-Rl-180-l, MGP Vent Stack BRad 1-VG-RI-180-1, B Rad monitor, Hi alarm.
NAPS 2010 NRC NAPS NRC SROSRO ExamExam 31.
Plant Computer System (PCS) is unavailable.
The Plant In the event that the Main Control Room is evacuated, which ONE of the following identifies the instrument used to monitor reactor status, AND includes the location of the indicator?
A. Excore Neutron Flux Monitor System Ch. II;; Emergency Switchgear Room B. Excore Neutron Flux Monitor System Ch. II;; Fuel Building C. Source Range Channel N-31 ;; Emergency Switchgear Room D. Source Range Channel N-31 ; Fuel Building
Unit 11 is in Mode 2.
A CONTROL POWER fuse blows on Intermediate Range Channel N-35.
Which ONE of the following identifies the plant response for this event?
A. N-35 detector will indicate downscale and the reactor will trip.
B. N-35 detector will indicate normally and the reactor will trip.
C. N-35 detector will indicate downscale and the reactor will NOT trip.
D. N-35 detector will indicate normally and the reactor will NOT trip.
NAPS 2010 NAPS 2010 NRCNRC SROSRO Exam Exam 33.
33.
Given the Given the following conditions:
following conditions:
- Unit 11 has Unit has been been shutdown shutdown for for 66 days.
days.
- Containment purge Containment purge isis in service on in service on Unit Unit 1.
1.
- A containment air recirc fan (CARF)
"A" (CARF) is is running.
running.
- Core off-load is in in progress.
The "A" The A CARF CARE trips, trips, and and the the crew crew is is unable unable toto restart restart any any CARF.
CARE.
Which ONE of the following describes impacts of this failure on the Radiation Monitoring System, AND on the core off-load in accordance with 1-0P-4.1, 1-OP-4.1, Controlling Procedure for Refueling?
A. 1-RM-RMS-159 and -160, Containment Particulate and Gaseous monitors, are BOTH inoperable; Station Management approval is required in order to continue core off-load.
B. 1-RM-RMS-160, Containment Gaseous monitor ONLY is inoperable; Station Management approval is required in order to continue core off-load.
C. 1-RM-RMS-159 and -160, Containment Particulate and Gaseous monitors, are BOTH inoperable; Nuclear Analysis and Fuels approval is required in order to continue core off-load.
D. 1-RM-RMS-160, Containment Gaseous monitor ONLY is inoperable; Nuclear Analysis and Fuels approval is required in order to continue core off-load.
NAPS 2010 NAPS 2010 NRCNRC SROSRO Exam Exam 34.
34.
Unit 22 is Unit is in in aa refueling refueling outage outage with with core core on-load on-load in progress.
in progress.
Given the Given the below below instruments, instruments, which which ONE ONE of of the following identifies the following identifies ALL of of the the instruments instruments that that can can cause cause AUTOMATIC actuation AUTOMATIC actuation of of the Containment Containment Evacuation Evacuation alarm?
alarm?
- 1) Source
- 1) Source Range Channel N-31 Range Channel N-31
- 2) Manipulator Manipulator Crane Crane Radiation Radiation Monitor, Monitor, 2-RM-RMS-262 Containment Gaseous
- 3) Containment Gaseous Radiation Radiation Monitor, Monitor, 2-RM-RMS-260 A. 1&3 B. 22&3
&3 C. I only 1
D. 2 only
NAPS 2010 NAPS 2010 NRCNRC SROSRO ExamExam 35.
35.
Given the Given the following conditions:
following conditions:
- Unit 11 was Unit was atat 100%
100% power power when when aa 50 gpm tube 50 gpm tube leak leak was was identified identified in in "B" B SG.
SG.
- The crew is The crew is performing performing 1-AP-24, 1-AP-24, Steam Generator Tube Steam Generator Tube Leak.
Leak.
The Unit Supervisor is Unit Supervisor is at at Step Step 18, 18, Verify Flow Flow from Affected SGsSGs - ISOLATED.
- ISOLATED.
BOP reports The BOP reports that Attachment Attachment 3, MSVH Steam 3, MSVH Steam Generator Generator Isolation Isolation Local Local Actions, Actions, has been been initiated, initiated, but has but has NOT NOT been been completed.
completed.
Which ONE of the following identifies identifies the crew response, response, AND includes includes the reason?
reason?
A. Continue with Step 19 and initiate RCS cooldown without delay; precludes overfill of "B"B SG.
B. Continue with Step 19 and initiate RCS cooldown 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.
D. Do NOT continue with Step 19, RCS cooldown can not be initiated until Attachment 3 is complete; ensures "B"B SG PORV remains available.
following conditions:
Given the followinci
- 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.
1-E-3,
- 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 accordance with 1-E-3?
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 NRC NAPS NRC SRO Exam Exam 37.
In accordance with 1-0P-28.3, 1-OP-28.3, Startup of the Moisture Separator Reheaters, Reheaters, when placing the Reheat Reheat Steam System in service, the total rate of change of the LP Turbine Inlet Inlet (Reheater Outlet) temperature should NOT exceed . This heatup rate is initially controlled by _ _ _ _ _ _ _ __
A. 100°F per hour; throttling the MSR FCVs from the Benchboard 100°F B. 100°F per hour; throttling the 3-inch bypass valves locally 100°F C. 150°F per hour; throttling the MSR FCVs from the Benchboard D. 150°F per hour; throttling the 3-inch bypass valves locally
NAPS 2010 NRC SRO Exam NAPS 38.
An unisolable steamline break has led to an excessive cooldown of the RCS and an ORANGE path on Integrity.
RCS Integrity.
Which ONE of the following describes the area of most concern for the propagation of an existing flaw in the RCS during this event?
A. reactor vessel upper head area.
Plastic deformation due to tensile stresses in the reactor B. Brittle fracture due to compressive stresses in the reactor vessel hot leg area.
C. Plastic deformation due to compressive stresses in the reactor vessel cold leg area.
D. Brittle fracture due to tensile stresses in the reactor vessel downcomer beltline beitline area.
NAPS 2010 NAPS 2010 NRCNRC SRO SRO ExamExam 39.
39.
Given the Given the following conditions:
following conditions:
- Unit 11 was Unit was initially initially stable stable at 50% power.
at 50% power.
- RCS TTAVG RCS AVG & & TTREE were initially REF were initially matched matched and and on on program.
program.
An event occurs, which causes rods rods toto begin begin stepping IN.
IN.
The crew The crew observes observes thethe following indications:
indications:
- AVG is 568°F.
TAVG T
- T REF is TREF is 560°F.
- Power Range Power Range Channel N-44 N-44 is 48%.
Which ONE of the following identifies the correct response to this event AND JQ includes the reason for this response?
A. Place rods in MANUAL because they are moving in response to a N-44 failure.
B. Place rods in MANUAL because they are moving in response to a T REF failure.
TREE C. Leave rods in AUTO because they are moving in response to an increase in steam demand due to a 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 a malfunction in the turbine control system.
NAPS 2010 NAPS 2010 NRC NRC SRO Exam Exam 40.
Given the following conditions:
- 1-ECA-O.0, Loss of All AC Power, is in progress.
1-ECA-0.0,
- Intact SGs to 290 psig.
The crew is performing step 22, Depressurize all Intact
- 180 psig before the depressurization is stopped.
Pressure in all SGs reaches 180 What is the potential operational implication that could result from the excessive SG depressurization?
A. Nitrogen injection from the accumulators may occur, causing natural circulation flow in the RCS to be interrupted.
B. Excessive RCS cooldown, which could require transition to 1-FR-P.1, Response to Imminent Pressurized Thermal Shock.
C. Voiding may occur in the reactor vessel, causing the upper portion of the core to become uncovered and potentially causing core damage.
D. An undesired automatic Safety Injection signal may occur, complicating other recovery actions that are in progress.
NAPS 2010 NAPS 2010 NRC NRC SROSRO ExamExam 41.
41.
Which ONE Which ONE of of the the following following identifies identifies the the post-accident post-accident instrument instrument required required byby TR TR 3.3.9, 3.3.9, Regulatory Regulatory Guide (RG)
Guide (RG) 1.97 1.97 Instrumentation, Instrumentation, AND includes includes the the TR 3.3.9 3.3.9 Mode(s)
Mode(s) of of Applicability?
Applicability?
A. 1-MS-RM-170, A Steamline 1-MS-RM-170, Steamline Radiation Radiation Monitor; Monitor; Mode Mode 11 ONLY.
ONLY.
B. 1-MS-RM-170, A Steamline Radiation 1-MS-RM-170, Radiation Monitor; Modes 1, Monitor; Modes 1, 2, or 3.
3.
C. 1-SV-RM-121, Condenser Air Ejector 1-SV-RM-121, Ejector Radiation Radiation Monitor; Mode Mode 11 ONLY.
D. 1-SV-RM-121, Condenser Air Ejector Radiation Monitor; Modes 1,2, 1, 2, or 3.
NAPS NAPS 2010 2010 NRC NRC SRO SRO ExamExam 42.
42.
Given the Given the following conditions:
following conditions:
- Unit 11 RCS Unit RCS cooldown cooldown isis inin progress progress due due to leakage from to leakage from aa PRZR manway.
PRZR manway.
service.
rate.
A loss A loss of of "F" transfer bus F transfer bus occurs.
occurs.
In accordance with 1-AP-11, 1-AP-1 1, Loss of RHR, in order to re-establish RHR cooling after the EDG energizes the bus, the crew is directed to _ _ _ _ _ _ _ _ _ _ _ __
A. A RHR verify "A" RHR pump pump running, and manually manually adjust 1-CC-MOV-100A 1-CC-MOV-100A & B, CC HX HX Outlet Isolation 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 startA "A" RHR pump, and manually adjust 1-RH-HCV-1758, RHR HX Outlet Valve.
D. manually start "A"A RHR pump, and manually adjust 1-CC-MOV-1 1-CC-MOV-100A OOA &
& B, CC HX Outlet Isolation Valves.
NAPS 2010 NAPS 2010 NRC NRC SRO SRO ExamExam 43.
Unit 11 is Unit is at 100% power at 100% power when when several several Unit Unit 11 annunciators annunciators are are received.
received.
The OATC The OATC verifies all critical parameters all critical parameters are are stable stable and and on on program.
program.
crew notes The crew notes thethe following:
following:
- All status lights on "L" L Panel Panel are OFF.
- Annunciator 11 P-E4, P-E4, C-7 C-7 PERM PERM STM STM DUMP DUMP ARMED FROM FROM LOSS LOSS OF LOAD, is is LIT.
LIT.
Which ONE of the following identifies the 120VAC I2OVAC Vital bus that has lost power, AND includes the action needed to reset (clear) 11 P-E4 once power is restored?
A. I-Ill;; momentarily place the Steam Dump Mode Selector in the RESET position.
Vital bus I-III B. I-Ill ; place both Steam Dump INTLK switches to OFF/RESET and return to ON.
Vital bus I-III C. l-IV; momentarily place the Steam Dump Mode Selector in the RESET position.
Vital bus I-IV; D. Vital bus I-IV; -IV; place both Steam Dump INTLK switches to OFF/RESET and return to ON.
NAPS 2010 NAPS 2010 NRC NRC SRO SRO Exam Exam
- 44. Given
- 44. Given the the following following conditions:
conditions:
- Unit 11 is Unit is at at 70%
70% power power
(MEW) pump pump is is tagged tagged out out C MFW The "C" MFW pump pump trips.
Which ONE ONE of of the following describes the plant plant response?
response?
(Assume no operator action.) actionS)
A. MFRVs modulate open; open: SG levels continue to decrease.
B. MFRVs modulate open; open: SG levels are maintained on program.
C. MFRVs and bypass valves fully open; open: SG levels continue to decrease.
D. MFRVs and bypass valves modulate open; open: SG levels are maintained on program.
NAPS 2010 NAPS 2010 NRC SRO Exam NRC SRO Exam 45.
45.
Given the Given the following conditions:
following conditions:
- Unit 1I is Unit is at 25% power at 25% power and and ramping ramping up.
up.
- Unit 22 is Unit in aa refueling is in refueling outage.
outage.
- Unit 11 SGWLC channels are All Unit are selected selected to Channel III Ill (Slue (Blue channel).
An I&C An l&C Tech inadvertently equalizes Tech inadvertently and isolates equalizes and isolates 1-FW-FT-1487.
1-FW-FT-1487, Unit Unit 11 "S" B SG SC Feed Feed Flow Flow Transmitter Transmitter (Blue channel).
(Slue channel).
Which ONE of the following describes the result of the I&C l&C technicians error? (assume NO operator action is taken)
A. B SG level decreases until the turbine automatically trips.
"S" B.
S. B SG "S" SC level decreases until the reactor automatically trips.
C. B SG "S" SC level increases until the turbine automatically trips.
D. B SG "S" SC level increases until the reactor automatically trips.
Given the following conditions:
- Unit 11 experiences a reactor trip and safety injection.
- 1-FW-P-2, Turbine Driven AFW pump, will not operate.
The crew performs 1-AP-22.1, Loss of 1-FW-P-2 Turbine Driven AFW Pump, to feed all three SG's.
SGs.
Which ONE of the following identifies the AFW alignment once 1-AP-22.1 has been performed?
A. 1-FW-P-3A and 1-FW-P-3B feeding 1-FW-P-38 A SG thru 1-FW-HCV-100A "A" 1-FW-HCV-IOOA 1-FW-P-3A and 1-FW-P-3B feeding 1-FW-P-38 B SG thru 1-FW-HCV-1008 "8" 1-FW-HCV-IOOB 1-FW-P-3A and 1-FW-P-3B feeding 1-FW-P-38 "c" C SG thru 1-FW-HCV-100C 1-FW-HCV-IOOC B. 1-FW-P-3A and 1-FW-P-3B feeding "A" 1-FW-P-38 A SG thru 1-FW-HCV-100A 1-FW-P-3A and 1-FW-P-3B feeding "8" 1-FW-P-38 B SG thru 1-FW-MOV-1008 1-FW-MOV-100B 1-FW-P-3A and 1-FW-P-3B feeding "c" 1-FW-P-38 C SG thru 1-FW-HCV-100C C. 1-FW-P-3B feeding "A" 1-FW-P-38 A SG thru 1-FW-MOV-100A 1-FW-P-3B feeding "8" 1-FW-P-38 B SG thru 1-FW-MOV-1008 1-FW-MOV-1 COB 1-FW-P-3A feeding "c" 1-FW-HCV-1 OOC C SG thru 1-FW-HCV-100C D. 1-FW-P-3A feeding "A" A SG thru 1-FW-MOV-100D 1-FW-P-3B feeding "8" 1-FW-P-38 B SG thru 1-FW-MOV-1008 1-FW-MOV-1 COB 1-FW-P-3A feeding "c" 1-FW-HCV-1 OOC C SG thru 1-FW-HCV-100C
NAPS 2010 NAPS 2010 NRCNRC SRO SRO Exam Exam 47.
47.
Unit 11 is Unit is at 100% power.
at 100% power.
Which ONE Which ONE of the following of the following identifies identifies the the response response ifif Vital Vital Bus Bus Inverter Inverter 1-11 1-Il fails, AND includes fails, AND includes the the Technical Specification Technical Specification implications implications of of this this malfunction?
malfunction?
12OVAC Vital bus 120VAC 1-Il will be powered bus 1-11 powered automatically from _ _ __
A. MCC 11H1-1 MCC 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. MCC 1H1-11H1-1 via a constant voltage transformer; Unit 11 is in a limiting action.
C. MCC 1J1-1 MCC IJ1-1 via a constant voltage transformer; Unit Unit 11 is in an info-only action.
D. MCC 1J1-1 MCC 1JI-1 via a constant voltage transformer; Unit Unit 11 is in a limiting action.
NAPS 2010 NAPS 2010 NRC NRC SRO Exam SRO Exam 48.
48.
Given the Given the following conditions:
following conditions:
- Both Units Both Units are are at 100% power.
at 100% power.
- Service Water (SW)
Service Water (SW) isis throttled.
throttled.
- Service Water pumps 1-SW-P-lA and pumps 1-SW-P-1A and 1-SW-P-1B 1-SW-P-lB are are running.
running.
notes that SW reservoir The crew notes reservoir level level has has been been decreasing slowly, and currently currently indicates indicates 312 feet.
The following conditions exist:
- 1-SW-P-lA discharge pressure is 45psig.
1-SW-P-1A
- 1-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 Service Water Header; operable "A"
B. A Service Water Header; inoperable "A"
C. B Service Water Header; operable "B"
D. B "B" Service Water Header; inoperable
NAPS 2010 NRC NRC SRO Exam Exam 49.
100% power.
Units are at 100%
Both Units An electrical fault results in a loss of "c" C RSST.
Which ONE of the following will occur as a result of this event?
A. 1H and 2J EDGs will start and load; breaker 15G10 1H 15G10 will remain open B. 11H and 2J EDGs will start and load; breaker 15G Hand 15G10 10 will close C. ONLY 2H EDG will start and load; breaker 15G1 15G100 will remain open D. ONLY 2H EDG will start and load; breaker 15G1 15G100 will close
NAPS 2010 NAPS 2010 NRCNRC SRO SRO Exam Exam 50.
50.
Which ONE Which ONE ofof the the following describes the following describes operation of the operation of the I25VDC Vital the 125VDC Vital bus bus battery battery chargers?
chargers?
The battery The battery chargers chargers have have an adjustable current an adjustable 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 reaches reaches 275 275 amps.
B. limits the maximum AC AC input current to 275 275 amps.
C.
C. opens the DCDC output breaker ifif DC output breaker DC output output current current reaches reaches 275 275 amps.
amps.
D. limits the maximum DC output current to 275 amps.
NAPS 2010 NAPS 2010 NRCNRC SROSRO ExamExam 51.
51.
With Unit With Unit 11 at 100% power, at 100% power, the the 11H 4160V bus H 4160V bus normal normal feeder 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 of Electrical Electrical Power, Power, configuring configuring 11 H H bus loads is bus loads is done as aa high done as high priority priority inin order order to _ _ _ _ _ _ _ _ __
to A.
A. prevent EDG prevent EDG overload overload in the event in the event of of an Sl/CDA.
an SI/CDA.
B.
B. facilitate restoration facilitate restoration of the emergency bus bus from the normal normal feeder.
C. ensure loads that may have automatically started are returned to their pre-event (standby) status.
D. ensure that 11 H bus loads will trip selectively in the event of an SI/CDA.
SIICDA.
NAPS 2010 NAPS 2010 NRC NRC SRO SRO Exam Exam 52.
52.
Given the Given the following conditions:
following conditions:
- A loss A of Instrument loss of Instrument Air Air (IA)
(IA) occurs.
occurs.
psig.
identifies ALL of the Auxiliary Feedwater Which ONE of the following identifies Feedwater System components that can be operated for operated limited period for aa limited period of of time?
time?
A. AFW Pump 1-FW-P-2 steam supply valves (1-MS-TV-111A Pump 1-FW-P-2 (1-MS-TV-il 1A &
& B)
B) ONLY.
ONLY.
B. AFW HCVs (1-FW-HCV-100A, B, & C) AND AFW PCVs (1-FW-PCV-159A & B) ONLY.
C. AFW Pump 1-FW-P-2i-FW-P-2 steam supply valves (1-MS-TV-111A (1-MS-TV-Il 1A &
& B) AND (l-FW-HCV-100A, B, &
AFW HCVs (1-FW-HCV-100A, & C) ONLY.
D. (1-FW-HCV-l0OA, B, & C) AND AFW PCVs (1-FW-PCV-159A & B) AND AFW HCVs (1-FW-HCV-100A, AFW Pump 1-FW-P-2l-FW-P-2 steam supply valves (1-MS-TV-111A (i-MS-TV-il 1A & B).
NAPS 2010 NAPS 2010 NRC NRC SRO Exam SRO Exam 53.
53.
Which ONE Which ONE ofof the the following following describes describes the the impact impact of of aa failure failure of of 1-RM-LW-110, 1-RM-LW-11O, Clarifier Clarifier Inlet Inlet Radiation Radiation Monitor, and Monitor, and 1-RM-L 1 -RM-LW-1 11, Clarifier W-111, Clarifier Outlet Radiation Monitor, Outlet Radiation Monitor, onon the the following following valves?
valves?
1-LW-PCV-115, 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 Influent A failure (HIGH)
(HIGH) of of _ __
A.
A. either 1-RM-LW-110 either 1-RM-LW-11O or or 1-RM-LW-111 1-RM-LW-111 will close close 1-LW-PCV-115 1-LW-PCV-115 ONLY.
B.
B. either 1-RM-LW-110 1-RM-LW-11O or 1-RM-LW-111 will close 1-LW-PCV-115 and 1-LW-FCV-100.
C. 1-RM-LW-111 will close 1-LW-PCV-115 only 1-RM-LW-111 1-LW-PCV-115 ONLY.
D. jjy 1-RM-LW-111 will close 1-LW-PCV-115 only 1LW-PCV-115 and 1-LW-FCV-100.
NAPS 2010 NAPS 2010 NRC SRO Exam NRC SRO Exam 54.
54.
Given the Given the following conditions:
following conditions:
- A WGDT A WGDT release release isis in in progress.
progress.
- HI and HI HI-HI alarms and HI-HI alarms are received on are received on 1-GW-RM-178-1, 1-GW-RM-178-1, Process Process Vent Vent RM RM Noble Noble Gas Gas Normal.
Normal.
- The cause of of the alarm was determined to be be the detector spiking.
- 1-GW-RM-178-1 indication 1-GW-RM-178-1 indication is is trending back to normal.
Which ONE Which ONE of of the the following describes describes the the automatic automatic action action that the the OATC will verify, OATC will verify, AND includes includes the procedural direction given to re-establish the WGDT release once the detector is operating normally?
A. Verity 1-GW-FCV-101, Verify 1-GW-FCV-1O1, WGDT WGDTto Process Vents, CLOSED; to Process re-established once the OATC verifies the HI the WGDT release can be re-established HI alarm clears.
B. 1-GW-FCV-1O1, WGDT to Process Vents, CLOSED; Verify 1-GW-FCV-101, the WGDT release can be re-established once the Instrument Department resets the HI-HI alarm AND restores the MGP system to normal range monitoring.
C. 1-GW-TV-106, Verify 1-GW-TV-1 06, Equipment Vents, CLOSED; the WGDT release can be re-established once the OATC verifies the HI alarm clears.
D. Verify 1-GW-TV-106, Equipment Vents, CLOSED; the WGDT release can be re-established once the Instrument Department resets the HI-HI alarm AND restores the MGP system to normal range monitoring.
NAPS 2010 NAPS 2010 NRC NRC SRO SRO ExamExam 55.
55.
Per 1-FR-C.1, Per 1-FR-Cl, Response Response to Inadequate Core to Inadequate Core Cooling, Cooling, SGs SGs are are depressurized depressurized at at the the maximum maximum rate rate to to (ultimately) atmospheric pressure (ultimately) atmospheric pressure inin order order to to _ _ _ _ __
A.
A. reduce RCS reduce RCS temperature temperature to to collapse collapse steam voids in steam voids in the the reactor reactor vessel vessel head.
head.
B. enable low-pressure sources of reduce SG pressure to enable of SG SG feedwater to restore RCS heat sink.
C.
C. reduce RCS reduce RCS temperature temperature to increase increase thermal thermal driving driving head head for natural natural circulation.
circulation.
D. reduce RCS pressure to allow the SI accumulators and LHSI pumps to inject water to the RCS.
NAPS 2010 NRC NAPS NRC SROSRO Exam Exam 56.
Which ONE of the following identifies the normal and backup cooling water sources to the Control Room Chillers?
A. Bearing Cooling normally supplies both Units Control Room Chillers; either Unit can be supplied from Service Water as a backup.
B. Bearing Cooling normally supplies both Units Control Room Chillers; ONLY Unit 11 can be supplied from Service Water as a backup.
C. Service Water normally supplies both Units Control Room Chillers; either Unit can be supplied from Bearing Cooling as a 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 SROSRO Exam Exam 57.
57.
Which ONE Which ONE ofof the the following parameters by following parameters by itself itself can can be used to be used discriminate between to discriminate between aa voltage voltage regulator regulator malfunction and a grid disturbance?
malfunction and a grid disturbance?
A.
A. Generator Megawatts.
Generator Megawatts.
B.
B. Generator Megavars.
Generator Megavars.
C.
C. Generator Output Generator Voltage.
Output Voltage.
D.
D. Exciter Field Exciter Field Current.
Current.
NAPS 2010 NAPS 2010 NRC NRC SROSRO Exam Exam 58.
58.
Which ONE Which ONE of the following of the following identifies identifies the the power power supplies supplies to to the the Unit Unit 11 and and Unit Unit 22 Instrument Instrument Air Air compressors, 1-IA-C-1 compressors, 1-IA-C-i and 2-IA-C-i, respectively?
and 2-IA-C-1, respectively?
i-IA-C-i is 1-IA-C-1 powered from is powered from _ _ _ _ _ , and and 2-IA-C-1 2-IA-C-i is is powered powered from from _ _ _ __
A. 1iH Emergency Bus; H Emergency Bus ; 2H Emergency Emergency Bus Bus B.
B. 1iH Emergency Bus; H Emergency Bus; 2J 2J Emergency Emergency BusBus C. 11J Emergency Bus; J Emergency Bus; 2H Emergency Emergency BusBus D. iJ Emergency Bus; 2J Emergency Bus 1J
NAPS 2010 NAPS 2010 NRC NRC SRO SRO Exam Exam 59.
59.
IfIf aa Main Main Transformer Transformer deluge deluge isis inadvertently actuated, the inadvertently actuated, the Electric Electric Fire Fire Pump Pump is is started started by by
_ _ _ _ _ , and and the associated associated Main Main Transformer will _ _ _ __
A.
A. limit switch aa limit switch on on the the deluge deluge valve; valve; de-energize de-energize B. a limit switch on the deluge valve; remain energized C. aa pressure C. pressure switch on on the fire main; main ; de-energize D. a pressure switch on the fire main;main ; remain energized
NAPS 2010 NAPS 2010 NRC NRC SROSRO ExamExam 60.
60.
The crew The crew is is preparing preparing for for Unit Unit 1I core core off-load.
off-load.
Which ONE Which ONE of the following of the describes the following describes method specified the method specified in in 1-PT-91, 1-PT-91, Containment Containment Penetrations, Penetrations, to to control containment penetrations, control containment penetrations, ANDfjQ includes includes the the approval required required to breach breach a penetration during fuel movement?
Containment penetrations Containment penetrations shall be be tagged with _ _ __
A. Danger tags, and an SRO or Shift Manager may approve breaching a penetration.
B. Danger tags, and FSRC approval is required for breaching a penetration.
C. Caution/Information tags, and an SRO or Shift Manager may approve breaching a penetration.
Caution/lnformation D. Caution/Information tags, and FSRC approval is required for breaching a penetration.
1-OP-2. 1, Unit Startup from Mode 2 to Mode 1, during a Unit ramp, all of the following In accordance with 1-0P-2.1, indications should be used to monitor real power EXCEPT _ _ __
A. U0980, Power, Calorimetric B. U1201, Power, 11 Min Mm Avg STM C. Mm Avg FW U1203, Power, 11 Min D. Mm Avg UFM U1231, Power, 11 Min
NAPS 2010 NRC NAPS NRC SRO Exam Exam 62 62.
100% power, Unit 11 at 100%
With Unit power, the following conditions exist:
1-CW-MOV-IOID, "D" 1-CW-MOV-101D, D Waterbox Inlet MOV, indicates mid-position.
- Condenser pressure is 2.2 inches Hg abs. and degrading.
Which ONE of the following identifies the immediate operator action, AND includes the action required by 1-AP-14, Low Condenser Vacuum, to mitigate this event?
1-AP-14, event?
A. Verify at least two Circulating Water pumps running; 1-VP-i 8, Air Ejector suction valve for 'D' Close 1-VP-18, D water box.
B. Verify condenser pressure is 3.5 inches Hg abs or less and stable; i-VP-i 8, Air Ejector suction valve for 'D' Close 1-VP-18, D water box.
C. Verify at least two Circulating Water pumps running; Open 1-CW-MOV-100D, "D" D CW pump Discharge MOV.
D. Verify condenser pressure is 3.5 inches Hg abs or less and stable; i-CW-MOV-100D, "D" Open 1-CW-MOV-100D, D CW pump Discharge MOV.
NAPS 2010 NAPS 2010 NRCNRC SRO SRO ExamExam 63.
63.
The Backboards The Backboards operator operator is is conducting conducting an an infrequently infrequently performed performed PT.
PT.
One of One of the the steps of the steps of the procedure procedure is designated IV is designated IV (Independent (Independent Verification).
Verification).
The Backboards The operator feels Backboards operator feels that CV (Concurrent that CV (Concurrent Verification)
Verification) would be more appropriate method be a more method of verification for the step.
OATC, you review the As the OATC, the procedure andand concur concur with the Backboards Backboards operator's operators assessment.
assessment.
Which ONE of the following describes the guidance provided by PI-AA-500, Verification Practices, to address this issue?
A. An inactive SRO on shift performing reactivation duties may authorize the use of CV in in lieu of IV.
IV.
B. A procedure change 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 NRC SRO Exam Exam 64.
Unit 11 was initially at 100%
Unit 100% power.
1-AP-2.2, Fast Load Reduction, has been entered.
1-AP-2.2, Which ONE of the following describes the sequence of actions that must be performed when a fast load 1-AP-2.2?
reduction is required in accordance with 1-AP-2.2?
- 2) Transfer Rod Control to MANUAL
- 2) Bypass AMSAC
- 3) Transfer Rod Control to MANUAL D. 1) Transfer Rod Control to MANUAL
- 2) Bypass AMSAC
NAPS 2010 NAPS NRC SRO 2010 NRC SRO Exam Exam 65.
65.
Given the Given the following conditions:
followinQ 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 placed placed the control switch switch for 1-RC-PCV-1456, 1-RC-PCV-1456, PRZR PRZR PORV, PORV, inin CLOSE.
CLOSE.
psig.
stabilized.
Which ONE of the following identifies the Technical Specification implications of these plant conditions?
1-.RC-PCV-1456 _ _ _ _ _, and 1-RC-MOV-1535, 1-RC-PCV-1456 1-RC-MOV-1 535, PRZRPRZR PORV PORV Block Block Valve, _ _ _ __
A. is operable; Specifications.
MUST be closed to comply with Technical Specifications.
B. is operable; Specifications.
is NOT required to be closed to comply with Technical Specifications.
C. is NOT operable; MUST be closed to comply with Technical Specifications.
Specifications.
D. is NOT operable; is NOT required to be closed to comply with Technical Specifications.
Specifications.
NAPS 2010 NAPS 2010 NRCNRC SRO SRO Exam Exam 66.
66.
Given the Given the following conditions:
following conditions:
- Unit 11 is Unit is at at 50%
50% power power and and ramping ramping up up at 0.3%/minute.
at 0.3%/minute.
- 1-CW-P-ID, 1-CW-P-1 D Circulating D, "D" Circulating Water Water pump, pump, trips.
trips.
- 1-AP-13, Loss The crew enters 1-AP-13, Loss of One or More More Circulating Water Pumps.
Pumps.
Which ONE Which ONE of the following identifies of the identifies the guidance guidance provided provided by by 1-AP-13 1-AP-13 for for controlling controlling Liquid Liquid Waste releases?
releases?
A. Liquid Waste releases must be immediately secured, and Chemistry Department approval must be obtained prior to resuming resuming them.
B. Liquid Waste releases must be immediately secured, and Health Liquid 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 SRO SRO ExamExam 67.
67.
Which ONE Which ONE of the following of the following identifies identifies the the posting posting requirements, requirements, ANDAND includes includes the the MINIMUM MINIMUM entry entry requirements for requirements for an an area area accessible accessible to individuals, in to individuals, in which which radiation radiation levels could result levels could result in in an an individual individual receiving aa deep receiving deep dose equivalent in dose equivalent excess of in excess of 100 100 mrem mrem in in one one hour hour at at 30 centimeters from 30 centimeters from thethe source?
source?
A. High Radiation High Radiation Area; alarming dosimetry (DAD) OR OR continuous HP HP coverage B.
B. High Radiation High Radiation Area; Area; alarming alarming dosimetry dosimetry (DAD)
(DAD) AND continuous continuous HPHP coverage coverage c.
C. Locked High Radiation Area; Area ; alarming dosimetry (DAD) OR continuous HP coverage D. Locked High Radiation Area;Area ; alarming dosimetry (DAD) AN[}continuous AN D continuous HP coverage
NAPS 2010 NAPS 2010 NRCNRC SROSRO ExamExam 68.
68.
Which ONE Which ONE of of the following provides the following provides the the correct correct value for the value for the associated associated Federal Federal Annual Annual Exposure Exposure Lim its?
Limits?
Extremities Extremities Sk Skin Lens Lens of of eye eye A. 15 rem/yr 15 rem/yr 50 rem/yr 5 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 15 rem/yr 5 rem/yr D.
D. 50 rem/yr 15 rem/yr 15 rem/yr
NAPS 2010 NAPS 2010 NRC NRC SROSRO Exam Exam 69.
69.
IIn accordance with n accordance with O-FCA-1, 0-FCA-1, Control Room Fire, Control Room Fire, RCS cooldown rate RCS cooldown rate shall be _ _ _ _ _ _ , and shall be and aa 29-hour hold 29-hour hold is is NOT required prior NOT required prior to depressurizing the to depressurizing the RCS RCS provided _ _ __
provided___________
A.
A. less than less 15°F/hr;; at than 15°F/hr least one at least CRDM fan one CRDM fan is running.
is running.
B.
B. less than 15°F/hr less 15°F/hr;; three three CRDM CRDM fans are are running.
running.
C.
C. less than 50°F/hr less 50°F/hr;; at least one at least one CRDM fan is running.
running.
D. 50°F/hr;; three CRDM fans are running.
less than 50°F/hr
NAPS 2010 NAPS 2010 NRCNRC SROSRO Exam Exam 70.
70.
Which ONE Which ONE of of the the following following would would result result inin an an emergency emergency event event classification classification in in accordance accordance with with the the EAL EAL Matrix?
Matrix?
A.
A. RCS identified RCS identified leakage leakage isis determined determined to to be be 8.3 8.3 gpm.
gpm.
B. Unit 1I enters TS 3.0.3.
Unit C. unconfirmed security C. An unconfirmed security threat threat is is received.
received.
D. Offsite power was lost one hour ago and has not been restored.
NAPS 2010 NAPS 2010 NRC NRC SROSRO ExamExam 71.
71.
Given the Given the following conditions:
following conditions:
- Unit 11 tripped Unit tripped from from 100%
100% power power due due to to aa spurious spurious safety safety injection.
injection.
Termination.
The OATC is performing Step 1, 1, Reset Reset Both Trains of of SI, and notes that annunciator annunciator 11 P-H2, P-H2, AUTO SI TRNS A&B, BLKD TRNS FLASHING.
A&B, is FLASHING.
Which ONE of the following identifies the SSPS status, AND includes the action action the crew should take?
A. BOTH trains of SSPS have failed to RESET; reset both trains by closing and then opening Reactor Reactor Trip Breakers to clear the seal-in.
B. BOTH trains of SSPS have failed to RESET; place both trains of SSPS in TEST and locally reset BOTH trains.
C. ONE train of SSPS has failed to RESET; reset the affected train by closing and then opening Reactor Trip Breakers to clear the seal-in.
D. ONE train of SSPS has failed to RESET; place the affected train of SSPS in TEST and locally reset the affected train.
NAPS 2010 NRC NAPS NRC SRO SRO Exam Exam 72.
Given the following conditions:
- Unit 11 was initially at 100%
100% power with 1-FW-P-2 1-FW-P-2 tagged out.
- A Reactor Trip occurred, and multiple failures have resulted in a loss of all AFW pumps.
- 1-FR-Hi, Response to Loss of Secondary Heat Sink.
The crew has transitioned to 1-FR-H.1, Attempts to start a MFW MEW pump proved unsuccessful, and the crew is attempting to establish SG feed flow from the Condensate system.
Which ONE of the following describes how conditions are established to feed from the Condensate system, AND includes the reason?
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 Sl SI actuation.
NAPS 2010 NRC SRO Exam Exam 73 73.
1-ES-1.3, Transfer to Cold Leg Recirculation, Following a large-break LOCA, the crew has completed 1-ES-1.3, Step 9, Align SI System For Cold Leg Recirculation.
The following conditions exist:
- Amps and flow are oscillating on both Low-head SI pumps.
- The STA reports that a RED path exists on heat sink.
Which ONE of the following describes the correct actions AND implementation of procedures for these conditions?
A. l-ES-l.3, Attachment 3, Containment Sump Screen Blockage or Loss of Suction; Perform 1-ES-1.3, 1-FR-Hi, Response to Loss of Secondary Heat Sink, until directed in 1-E-1, Do NOT implement 1-FR-H.1, Loss of Reactor or Secondary Coolant.
B. Perform 1-ES-1.3, 1-ES-I .3, Attachment 3, Containment Sump Screen Blockage or Loss of Suction; i-FR-H. 1, Response to Loss of Secondary Heat Sink, until directed in Do NOT implement 1-FR-H.1, i-ECA-I.I, Loss of Emergency Coolant Recirculation.
Attachment 3 OR 1-ECA-1.1, C. 1-FR-Hi, Response to Loss of Secondary Heat Sink.
Immediately transition to 1-FR-H.1, D. 1-ECA-i.i, Loss of Emergency Coolant Recirculation.
Immediately transition to 1-ECA-1.1,
NAPS 2010 NRC NAPS NRC SRO Exam Exam 74.
Given the following conditions:
- Unit 11 was initially at 100%
100% power. -
- B SG faulted inside Containment.
"B"
- B SG is also ruptured.
The crew is unable to terminate SI, and have determined that "B" The crew has completed the appropriate EOP transitions, and is now performing 1-ECA-3.1, SGTR With Loss of Reactor Coolant - Subcooled Recovery Desired.
The STSTA A reports the following:
- RWST Level is 38% and slowly decreasing.
- There are no other RED or ORANGE paths.
Which ONE of the following identifies the appropriate procedure transitions for these conditions?
A. DO NOT transition to 1-FR-Z.2, Response to High Containment Sump Level; remain in 1-ECA-3.1 and continue recovery actions.
B. DO NOT transition to 1-FR-Z.2, Response to High Containment Sump Level; transition to 1-ES-1.3, 1-ES-I .3, Transfer to Cold Leg Recirculation.
C. Transition to 1-FR-Z.2, 1 -FR-Z.2, Response to High Containment Sump Level, to identify the source of water:
then return to 1-ECA-3.1 1-ECA-3.l and continue recovery actions.
D. Transition to I-FR-Z.2, 1-FR-Z.2, Response to High Containment Sump Level, to identify the source of water; transition to l-ES-I.3, 1-ES-1.3, Transfer to Cold Leg Recirculation.
NAPS 2010 NRC NAPS NRC SRO Exam Exam 75.
Given the following conditions:
- Unit 1I core off-load is in progress.
- A recently-irradiated fuel assembly drops while placing it into the containment upender.
- Bubbles are coming to the surface of the reactor cavity.
The following radiation monitors are in alarm:
- 1-RM-RMS-159, Containment Gaseous RIM. R/M.
- I-RM-RMS-160, Containment Particulate RIM.
1-RM-RMS-160, R/M.
- 1-RM-RMS-162, Manipulator Crane 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, Fuel Failure During Handling?
A. Place Fuel Building ventilation in service through the charcoal filters; evacuate the Containment only.
B. Place Fuel Building ventilation in service through the charcoal filters; evacuate the Fuel Building and the Containment.
C. Manually initiate Control Room bottled air dump; evacuate the Containment 2Jjy.only.
D. Manually initiate Control Room bottled air dump; evacuate the Fuel Building and the Containment.
Given the following conditions:
- Unit 11 is at 75% power and ramping up at 0.3% per minute.
- The crew notes that rods are withdrawing at maximum speed.
- The OATC places rods in MANUAL and reports that rods have stopped moving.
The following alarms are LIT:
- 1A-Di, ROD CONTROL URGENT FAILURE.
- 1 D-E4, NIS PWR RGE HI FLUX RATE RX TRIP.
1D-E4, The OATC reports that Reactor Trip breakers are closed.
Which ONE of the following identifies the procedure flowpathto mitigate this event, AND includes the action required if the crew is unable to verify adequate 1-FR-Si, adeguate negative reactivity insertion per 1-FR-S.1, Response to Nuclear Power Generation/ATWS?
A. Enter 1-FR-S.1 directly; manually align Charging Pump suction to RWST and inject the BIT.
B. Enter 1-FR-S.1 directly; initiate boration at greater than 10 gpm with the blender in BORATE mode.
C. i-E-0, Reactor Trip or Safety Injection, then transition to 1-FR-S.1; Enter 1-E-0, 1-FR-SI; manually align Charging Pump suction to RWST and inject the BIT.
D. 1-FR-Si; Enter 1-E-0, Reactor Trip or Safety Injection, then transition to 1-FR-S.1; initiate boration at greater than 10 gpm with the blender in BORATE mode.
NAPS 2010 NRC NAPS NRC SRO Exam Exam 77.
Unit 1I is at 100%
Unit 100% power.
Which ONE of the following places the Unit in a one hour Technical Specification required action, AND includes the Bases?
A. 10,950 ppm; BIT boron concentration is 10,950 ensures adequate negative reactivity insertion in the injection phase of a design-basis LOCA.
B. BIT boron concentration is 10,950 ppm; ensures adequate negative reactivity insertion in the injection phase of a design-basis MSLB.
C. 1-SW-P-lA trips; Service Water pump 1-SW-P-1A ensures the system can perform its design function during a DBA with NO additional failures.
D. 1-SW-P-lA trips; Service Water pump 1-SW-P-1A ensures the system can perform its design function during a DBA with ONE additional failure.
NAPS 2010 NRC NAPS NRC SROSRO Exam Exam 78.
Given the following conditions:
- Unit 1I is at 100%
100% power.
- A Reactor Coolant System pressure transient causes a PRZR safety valve to open prematurely.
- The safety valve then sticks in the fully open position.
Which ONE of the following identifies the plant response to this event, AND includes the proper prioritization of the procedures listed below?
1-AP-16, Increasing Primary Plant Leakage 1-AP-44, Loss of RCS Pressure 1-E-0, Reactor Trip or Safety Injection 1-ES-0.1, Reactor Trip Response I -E-1, Loss of Reactor or Secondary Coolant 1-E-1, RCS pressure will decrease requiring a reactor trip, and the rate of inventory loss will _ _ _ _ __
A. exceed the capacity of maximum normal charging flow - safety injection will be required; the crew should respond with 1-AP-16, then 1-E-0, followed by 1-E-1.
B. exceed the capacity of maximum normal charging flow - safety injection will be required; the crew should respond with 1-AP-44, then 1-E-0, followed by 1-E-1.
C. be within the capacity of maximum normal charging flow - safety injection will NOT be required; the crew should respond with 1-AP-16, then 1-E-0, followed by 1-ES-0.1.
1-ES-al.
D. be within the capacity of maximum normal charging flow - safety injection will NOT be required; the crew should respond with 1-AP-44, 1 -AP-44, then 1-E-0, 1 -E-0, followed by 1-ES-0.1.
1 -ES-0. 1.
NAPS 2010 NRC NAPS NRC SRO Exam Exam 79.
Given the following conditions:
- The crew has just completed synchronizing Unit 11 Main Generator to the grid.
- 1-RC-PT-1444, PRZR Pressure Control transmitter, fails HIGH.
1-RC-PT-1444,
- The crew performs the immediate actions of 1-AP-44, Loss of Reactor Coolant System Pressure.
The OATC reports that PRZR spray valve 1-RC-PCV-1455A indicates fully open, even after placing 1-RC-SOV-1455A, 1-RC-PCV-1455A Remote Close SOY, SOV, in CLOSE.
Which ONE of the following describes how the crew will mitigate this event?
A. Suspend performance of 1-AP-44, and perform 1-E-O, Reactor Trip or Safety Injection; A RCP when directed by 1-E-O.
stop the "A" B. Suspend performance of 1-AP-44, and perform 1-E-O, Reactor Trip or Safety Injection; stop the "c" C RCP when directed by 1-E-O.
C. Perform 1-E-O, Reactor Trip or Safety Injection, while continuing with 1-AP-44; after 1-E-O Immediate Actions are complete, stop the "A"A RCP.
D. Perform 1-E-O, Reactor Trip or Safety Injection, while continuing with 1-AP-44; after 1-E-O Immediate Actions are complete, stop the "c"C RCP.
Unit 11 is at 75% power ramping up to 100% at 0.3% per minute.
AFD is currently indicating zero (0) on all channels.
Which ONE of the following conditions would place the unit closest to an AFD limit, AND ffl includes the reason for the Technical Specification limits on AFD?
A. Allowing AFD to drift up to a value of +5 during the ramp; ensures that the Heat Flux Hot Channel Factor (FQ(Z)) is not exceeded during operation.
B. Allowing AFD to drift down to a value of -5 during the ramp; ensures that the Heat Flux Hot Channel Factor (FQ(Z)) is not exceeded during operation.
C. Allowing AFD to drift up to a value of +5 during the ramp; ensures that the gross radial power distribution remains consistent with the design values used in the Safety Analyses.
D. Allowing AFD to drift down to a value ofof-S
-5 during the ramp; ensures that the gross radial power distribution remains consistent with the design values used in the Safety Analyses.
NAPS 2010 NRC NAPS NRC SRO SRO Exam Exam 81.
Given the following conditions:
- Unit 11 is at 100%
100% power.
- Channel I, 1-P-LM-100A, Containment Pressure Protection Channell, 1-P-LM-100A, loses power.
- 1-AP-3, Loss of Vital Instrumentation.
The crew has completed 1-AP-3,
- The crew has NOT yet performed any actions of the applicable MOP.
Which ONE of the following identifies the Technical Specification required action, AND includes the plant response if Containment Pressure Protection Channel II subsequently fails HIGH prior to any actions being taken?
Place 1-P-LM-100A in BYPASS within _ __
A. 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />; an ESF actuation will occur B. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; an ESF actuation will occur C. 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />; an ESF actuation will NOT occur D. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; an ESF actuation will NOT occur
NAPS 2010 NRC NAPS NRC SRO Exam Exam 82.
Given the following conditions:
- Unit 11 core on-load is in progress.
- 28910.
Reactor cavity water level is 289' 10".
- A RHR pump is in operation.
"A"
- B RHR pump is tagged for seal repairs.
"B" Electrical Maintenance requests to perform a work order to locally observe operation of breaker 15H14 for "A" A RHR pump. The work requires the breaker to be opened, and then re-closed, using the control room switch. No test equipment will be attached to the breaker, and the entire operation should take no more than 30 minutes.
Which ONE of the following identifies how the SRO should respond to the Electrical Maintenance request, AND includes the Bases for this response?
A. Allow the activity. Tech Specs permit this since a duration time of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for an inoperable pump has been previously evaluated and determined to be safe; therefore the activity is acceptable per TS 3.9.5.
B. Allow the activity. Tech Specs provide an allowance which permits removing the required operating RHR loop from operation for up to 1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period to accomodate maintenance on the RHR loop; therefore the activity is acceptable per TS 3.9.5.
c.
C. DO NOT allow the activity. The bases for allowing the required RHR loop to be removed from service does NOT apply since cavity water level is not sufficient to remove decay heat during the proposed time period; therefore the activity is NOT acceptable per TS 3.9.5, D. DO NOT allow the activity. The bases for allowing the required RHR loop to be removed from service does NOT apply since it is to permit operations (e.g. fuel movement, core mapping, etc.) in the vicinity of the Hot Leg nozzles; therefore the activity is NOT acceptable per TS 3.9.5.
NAPS 2010 NRC NAPS NRC SRO Exam Exam 83.
Unit 11 experiences a large-break LOCA. The crew was unable to align a flowpath from the containment sump, and has transitioned to 1-ECA-1.1, 1 -ECA-1 .1, Loss of Emergency Coolant Recirculation.
Recirculation.
The following conditions exist:
- RWST level is 12% and slowly decreasing.
- Containment sump level is 5 foot 10 inches.
Given these conditions, 1-ECA-1.1 will direct the crew to start _ _ _ _ _ , and cautions the crew that Quench Spray pumps must be stopped when RWST level decreases to _ _ _ __
A. ONLY the Outside Recirc Spray pumps; 3%
B. pumps ; 8%
ONLY the Outside Recirc Spray pumps; C. ALL available Recirc Spray pumps; pumps ; 3%
D. ALL available Recirc Spray pumps; 8%
NAPS 2010 NAPS 2010 NRC NRC SRO SRO Exam Exam 84.
84.
Given the Given the following conditions:
following conditions:
- A cavity A cavity seal ring failure seal ring failure causes causes a loss loss of of reactor reactor cavity cavity water water level level during during core off-load.
core off-load.
- Fuel failures during Fuel failures during the previous cycle the previous cycle result result in in high high airborne airborne iodine iodine concentration.
concentration.
- basement stabilizes at four feet deep after the cavity drains.
Water level in the Containment basement
- Painting was recently completed completed inside Containment.
Which ONE of the following identifies identifies the appropriate actions to reduce reduce containment airborne iodine iodine concentration, AND includes the Technical Specification implications?
A. Place Containment Purge in service through one Auxiliary Building Iodine Filter; enter TS 3.7.15 action for Fuel Building Ventilation System inoperable.
B. Place Iodine Filtration Fans 1-HV-F-3A and 3B 38 in service; enter TS 3.7.15 action for Fuel Building Ventilation System inoperable.
C. Place Containment Purge in service through one Auxiliary Building Iodine Filter; enter TS 3.7.12 action for one PREACS train inoperable.
D. Place Iodine Filtration Fans 1-HV-F-3A and 3B in service; enterTS enter TS 3.7.12 action for one PREACS train inoperable.
Unit 11 is at 100% power with the PRZR Level Channel Defeat Switch selected to position 461/460.
An instrument malfunction causes the following plant response:
Letdown automatically isolated.
- Normal charging flow control valve 1-CH-FCV-1122 fully open.
Which ONE of the following identifies the failed channel, AND includes the protection function described by the Technical Specification Bases that is impacted by this failure?
A. failed ; primary protection against RCS overpressurization.
1-RC-LT-1460 is failed; B. 1-RC-LT-1460 1-RC-L failed ; protection against water relief through the PRZR Safety Valves.
T-1460 is failed; C. 1-RC-LT-1461 1-RC-L T-1461 is failed; primary protection against RCS overpressurization.
D. 1-RC-LT-1461 1-RC-L T-1461 is failed; protection against water relief through the PRZR Safety Valves.
NAPS 2010 NRC NAPS NRC SROSRO Exam Exam 86.
Given the following conditions:
- Unit 11 was initially at 100%
100% power.
- A loss of offsite power occurs.
- 1-MS-PCV-101A The crew was able to locally override 1-MS-PCV-1 01A closed.
The plant has been stabilized, and the crew is continuing recovery actions in accordance with 1-ES-C. 1, Reactor Trip Response.
1-ES-0.1, 1-MS-PCV-1OIA AND Which ONE of the following identifies the current status of 1-MS-PCV-101A Jfl the LCO for TS 3.7.4, Steam Generator Power Operated Relief Valves?
A. 1-MS-PCV-1OIA is operable and LCO 3.7.4 is met.
1-MS-PCV-101A B. 1-MS-PC\/-1O1A 1-MS-PCV-1 01A is inoperable and must be restored to operable prior to startup.
C. 1-MS-PCV-1O1A is inoperable and must be restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1-MS-PCV-101A D. 1-MS-PCV-1OIA is inoperable and must be restored to operable status within 7 days.
1-MS-PCV-101A
Given the following conditions:
- Unit 2 is at 100% power with Unit 11 core off-load in progress.
- A fuel assembly separates from its top nozzle while being withdrawn from the core.
- The crew enters 0-AP-30, Fuel Failure During Handling.
While the crew is performing time-critical actions of 0-AP-30, the Unit 2 reactor trips due to accidental jarring of a reactor trip breaker.
Which ONE of the following identifies the requirements for prioritization of 0-AP-30 and Unit 2 EOPs (2-E-0, Reactor Trip or Safety Injection, and 2-ES-0.1, 2-ES-0.1 Reactor Trip Response)?
A. Regardless of manpower availability, the crew should suspend performance of 0-AP-30 while performing the immediate actions of 2-E-0, and then perform 0-AP-30 in parallel with Unit 2 EOPs.
B. Regardless of manpower availability, the crew should suspend performance of 0-AP-30 while performing 2-E-0, and should not resume performing 0-AP-30 until Unit 2 is stable per 2-ES-0.1.
c.
C. The crew should complete the time-critical actions of 0-AP-30 prior to entering 2-E-0, and then perform Unit 2 EOPs in parallel with 0-AP-30.
D. If manpower permits, the crew should continue performing the time-critical actions of 0-AP-30 while performing the immediate actions of 2-E-0, and then perform 0-AP-30 in parallel with Unit 2 EOPs
The crew is performing 1-ECA-0.0, Loss of ALL AC Power, and has NOT yet been able to restore Emergency Bus power.
Thirty (30) minutes have elapsed since the emergency busses were lost, and the crew is briefing an operator to perform 1-ECA-0.0, Attachment 2, Turbine Building Operations.
In order to ensure adequate 125V DC bus voltage, which ONE of the following identifies the actions required, AND includes the associated time frame per 1-ECA-0.0?
Within the next _ _ _ _ , stop the DC Turbine Oil Pump and the DC Air Side Seal Oil Pump.
A. 30 minutes, verify the turbine is stopped and generator hydrogen is vented, then B. 60 minutes, verify the turbine is stopped and generator hydrogen is vented, then C. 30 minutes, verify turbine speed is < 1000 rpm and generator hydrogen is vented, then D. 60 minutes, verify turbine speed is << 1000 rpm and generator hydrogen is vented, then
While attempting to synchronize and load the 1HIH EOG EDG per 1-PT-82H, 1H Emergency Diesel Generator Slow Start Test, the operator reported that EDG speed is oscillating and he is unable to sychronize the IH EOG.
1H EDG.
The 1IH EDG is running with the output breaker open and speed is oscillating between 900 and 940 rpm.
H EOG Maintenance personnel at the EDG have requested to leave the EDG running to allow them to take some data prior to shutting it down.
1 -PT-82H, the 1I H EOG In accordance with 1-PT-82H, EDG should not be run unloaded for greater than _ _ minutes AND in accordance with Technical Specifications, a determination that 1J ANO IJ EOG EDG is NOT inoperable due to common cause failure is required to be completed within hours.
A. 5;44 5;
B. 5;24 5; 24
- c. 30;4 C. 30; 4 D. 30;24 30; 24
NAPS 2010 NRC SRO SRQ Exam Exam 90.
Given the following conditions:
- 100% power.
Unit 11 is at 100%
- The team has entered 1-AP-28, Loss of Instrument Air.
- The crew has completed the immediate actions of 1-AP-28.
The OATC reports that Instrument Air pressure is 95 psig and lowering.
Which ONE of the following identifies the MINIMUM instrument air pressure allowed by 1-AP-28 before a 1 -ES-0. 1, Reactor Trip Response, following the trip is required AND includes the AFW flow required by 1-ES-0.1, trip (assuming RCPs are running)?
A. psig;; 340 gpm 70 psig B. 70 psig ; 400 gpm C. 75 psig ;; 340 gpm D. 75 psig ; 400 gpm
NAPS 2010 NAPS 2010 NRC NRC SRO SRO Exam Exam 91.
91.
Which ONE Which ONE of the following of the identifies the following identifies the component component whose whose isolation isolation switch switch is is required required by by TR 7.5, TR 7.5, Appendix R Shutdown Equipment, R Alternate Shutdown Equipment, AND JQ includes includes the the required required action action and and completion completion time ifif the minimum minimum requirement requirement is is not not met?
met?
A. 1-CH-TV-1204A, Letdown 1-CH-TV-1204A, Letdown Isol lsol Valve; Implement hourly fire watch within 14 Implement 14 days.
B.
B. 1-CH-TV-1204A, Letdown 1-CH-TV-1204A, Letdown Isol Isol Valve; Restore equipment to functional status within 14 Restore 14 days be in days or be in Mode Mode 33 within the next next 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br />.
hours.
C. 1-RC-LCV-1460A, Letdown Isol Valve; Implement hourly fire watch within 14 days.
D. 1-RC-LCV-1460A, Letdown Isol Valve; Restore equipment to functional status within 14 days or be in Mode 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Unit 1I experienced a loss of offsite power followed by a small-break LOCA.
Operators are implementing 1-ES-1.2, 1-ES-i .2, Post-LOCA Cooldown and Depressurization.
The following conditions exist:
- Containment pressure is 21 psia and slowly increasing.
- 3.5RIhr and stable.
Containment radiation is 3.5R/hr Assuming these plant conditions remain unchanged, which ONE of the following identifies how the CRDM 1-ES-i .2, AND includes the reason?
Fans are operated in accordance with 1-ES-1.2, A. CRDM fans are left running to provide additional containment cooling.
B. CRDM fans are stopped to reduce emergency bus loading.
C. CRDM fans are stopped to prevent sump blockage due to degradation of the aluminum fan blading.
D. CRDM fans are stopped because of motor overload concerns.
Unit 11 is in Mode 6 with control rod unlatching in progress.
1-OP-4.15, Manipulator Crane, which ONE of the following identifies the ONLY In accordance with 1-0P-4.15, individual (by title) who is allowed to approve the use of crane interlock bypasses?
A. Refueling SRO.
B. Fuel Handling Supervisor.
C. Supervisor of Operations Support.
D. Operations Manager on Call.
/
NAPS 2010 NRC NAPS NRC SRO Exam Exam 94.
Given the following conditions:
- Unit 11 is at 100% power.
- Maintenance is preparing to troubleshoot an indicating light bulb issue with 1-QS-P-1A.
1-QS-P-1A.
- 1-QS-P-1A will need to be tagged out to support the troubleshooting.
1-QS-P-1A
lAW the Troubleshooting Sheet, the SRO must verify _ _ _ _ _ _ _ _ operable.
A. ONLYthe1HEDG ONLY the 1H EDG B.
B. BOTH 1IH 1-QS-P-1B H EDG and 1-QS-P-1 B C. ONLYthe1JEDG ONLY the 1J EDG D. BOTH 1J IJ EDG and 1-QS-P-1 1-QS-P-1B B
NAPS 2010 NRC NAPS NRC SRO SRD Exam Exam 95.
note which prohibits Technical Specifications have a note prohibits starting an RCP RCP with any RCS RCS Cold-leg temperature less than or equal to _ _ unless the secondary side water temperature of each SG is less than or equal to 50°F above each of the RCSRCS Cold-leg temperatures.
bases of this requirement is to _ _ _ __
The bases A. 180°F; limit rate of change of temperature to restrict stresses caused by thermal gradients.
180°F; B.
B. 180°F; prevent a low temperature overpressure event due to a thermal transient.
180°F; C. 280°F; limit rate of change of temperature to restrict stresses caused by thermal gradients.
D. 280°F; prevent a low temperature overpressure event due to a thermal transient.
NAPS 2010 NAPS 2010 NRCNRC SRO Exam SRO Exam 96.
96.
Unit 22 was Unit was initially initially at at 100% power.
100% power.
A large-break A large-break LOCALOCA hashas occurred occurred on Unit Unit 2.
2.
Emergency Ventilation fans can NOT be Which ONE of the following Emergency be used when placing placing the MCR/ESGR MCR/ESGR Emergency Ventilation system on Turbine Building Supply, AND Emergency AQ includes the Technical Specification restriction?
basis for this restriction?
A. 1-HV-F-41 due to the location 1-HV-F-41; location of the air intake B. 1-HV-F-41 ; this fan is not seismically qualified 1-HV-F-41; C. 2-HV-F-41 ; due to the location of the air intake 2-HV-F-41; D. 2-HV-F-41 ; this fan is not seismically qualified 2-HV-F-41;
The Waste Gas Decay Tanks (WGDT) were sampled to determine the quantity of radioactive material contained within each tank.
Confirmed sample results are as follows:
- A WGDT - 15,000 "A" - 15,000 curies of noble gas.
- B WGDT - 6,000 curies of noble gas.
"B" -
Based on these sample results, which ONE of the following identifies the implications per TR 3.1.3, Gas Storage Tanks, AND includes the associated TRM BASES?
The quantity of radioactive material in the WGDTs . The TRM bases for restricting the quantity of radioactive material is to limit dose at the exclusion boundary to _ _ _ __
A. required ; 0.5 rem.
is within limits, entry into TR 3.10.3 action is NOT required; B. required ; 0.1 rem.
is within limits, entry into TR 3.10.3 action is NOT required; c.
C. is NOT within limits, enter enterTR TR 3.10.3 action; 0.5 rem.
D. is NOT within limits, enter TR 3.10.3 action; 0.1 rem.
NAPS 2010 NAPS 2010 NRCNRC SRO SRO Exam Exam 98 98.
Both units Both units are are at 100% power at 100% power with with Operations Operations shift shift staffing staffing at at the the minimum required by minimum required by OP-AA-1 OP-AA-1 00,00, Conduct of Conduct of Operations.
Operations.
During the During the response response to fire, the to aa fire, scene leader the scene leader is is overcome overcome by by smoke, smoke, and is transported and is transported offsite offsite for for medical attention.
medical attention. The The only only other other qualified scene scene leader leader onon site is is aa licensed RO, who is licensed RO, is currently currently Backboards.
assigned Backboards.
Which ONEONE of the following of the following identifies identifies the the impact impact onon shift shift staffing, staffing, AND includes includes the the action action required required byby OP-AA-1 00?
A. Fire brigade minimum manning requirements are NOT met; met: immediately initiate action to restore the required fire brigade manning within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
B. brigade minimum Fire brigade minimum manning requirements requirements are NOT NOT met; immediately initiate action to restore the met: immediately required fire brigade manning within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
C. Fire brigade minimum manning requirements are NOT met; met: within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />, initiate action to restore the required fire brigade manning within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
D. Assign the licensed RO to assume scene leader duties, and reassign Backboards duties to a operator: Fire brigade and Shift minimum manning requirements are met.
non-licensed operator;
NAPS 2010 NRC NAPS NRC SRO Exam Exam 99.
Given the following conditions:
- Unit 11 was initially at 100% power.
- PRZR pressure and level began decreasing rapidly, and the crew manually tripped the reactor.
- Safety Injection automatically actuated.
The following conditions exist:
- Containment pressure - 11.1 psia and stable.
- Containment gaseous, particulate, and area radiation monitors - stable at pre-event values.
- 1-VG-RI-180-1, MGP Vent Stack BRad B Rad Monitor - HI alarm LIT.
- SG pressures - 1000 psig and stable.
The crew is performing 1-E-0, Reactor Trip or Safety Injection.
Which ONE of the following identifies the procedure the operators will transition to when leaving 1-E-0?
A. 1-E-1, Loss of Reactor or Secondary Coolant B. 1-ES-1.2, Post-LOCA Cooldown and Depressurization C. 1-ECA-1.1, Loss of Emergency Coolant Recirculation D. 1-ECA-1.2, LOCA Outside Containment
NAPS 2010 NAPS 2010 NRC NRC SRO SRO Exam Exam 100.
100.
Given the Given the following following conditions:
conditions:
- Unit 11 tripped Unit tripped from 100% power from 100% power due due to loss of to aa loss of offsite offsite power.
power.
- Multiple failures Multiple failures have have resulted resulted inin aa loss of all loss of all AFW AFW flow.
flow.
- Operators have Operators have implemented implemented 1-FR-H.1, 1-FR-H.1, Loss Loss of Secondary Heat of Secondary Heat Sink.
Sink.
The CAUTION The CAUTION prior prior to Step 22 of to Step of 1-FR-H.1 1-FR-H.1 reminds reminds the the crew crew that that RCS RCS bleed bleed and and feed feed should should be be initiated initiated immediately ifif wide-range immediately wide-range level level in in decreases to decreases to less less that that 14%
14% because because ofof aa loss loss of of heat heat sink. In sink. In accordance accordance with with the the 1-FR-H.1 1-FR-H.1 background background document, document, the the basis basis for for this this requirement requirement is is to A.
A. ANY SG ANY minimize core SG;; minimize core uncovery uncovery andand prevent prevent inadequate inadequate corecore cooling.
cooling.
B. ANY SG SG;; minimize challenges to SG tube integrity from creep rupture failure.
C. ANY 2 SGs SGs;; minimize core uncovery and prevent inadequate core cooling.
D. ANY 2 SGs SGs;; minimize challenges to SG tube integrity from creep rupture failure.
Af S ~2)
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- ID lD 1I
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OOIAK1.03 1I 001AKl.03 D 2 002K4.072 C 3 003K5.02 3 003K5.023 B 4 004G2.1.194 004G2.l.l9 4 B 5 004K6.155 A 6 005K6.03 6 005K6.036 D 7 006K6.187 B 8 007EK2.02 8 007EK2.028 B 9 007K4.01 9 B 10 007K5.02 10 B 11 008A3.10 11 008A3.l0 C 12 008AK3.02 12 A 13 008G2.4.45 13 A 14 009EA1.03 009EA 1.03 14 D 15 010A3.0.2 15 010A3.0.215 B 16 O11EK1.01 16 011EKl.01 D 17 012K2.01 17 C 18 012K5.01 18 B 19 0131<2.01 19 013K2.01 C 20 013K4.0620 B 21 014A2.0221 B 22 015AK2.0822 C 23 015K2.01 23 015K2.0123 B 24 017A1.01 24 017Al.0124 C 25 022A1.01 25 D 26 025AK2.03 26 A 27 026A2.05 27 026A2.0527 D 28 026AA1.0328 026AA 1.03 28 D 29 027AK3.01 027AK3.0129 29 D 30 029K1.03 029Kl.0330 30 C 31 032AA2.0631 032AA2.06 31 B 32 033AA1.01 033AAl.0132 32 B 33 034A4.01 33 A 34 036AK3.01 34 C 35 037AG2.1.2035 037 AG2.1.20 35 C 36 038EA2.1636 C 37 039A4.01 039A4.0137 37 B B
38 O4OAKI.0438 040AK1.0438 D D
39 045K3.01 045K3.0139 39 D 40 055EK1.0240 055EKl.0240 A 41 055G2.4.3 055G2.4.341 41 B 42 056AG2.4.9 056AG2.4.942 42 C C
43 057AG2.4.45 057 AG2.4.45 43 C C
44 059A1.0744 059Al.0744 A A
Answers Answers ------ ------------------
- ID 1 45 059K1.0445 C 46 061G2.1.2346 061 G2.1.23 46 A 47 062A1.03 47 062Al.0347 B B
48 062AA2.01 48 062AA2.0148 B 49 062K1.0449 062Kl.0449 B 50 063K4.04 50 063K4.0450 D 51 064A4.1051 064A4.10 51 A 52 065AG2.1.27 52 ~S 91 9 53 068K6.1053 068K6.10 53 D 54 073A2.02 54 073A2.0254 B 55 074EK1.03 55 D 56 076K1.0756 076Kl.0756 D 57 077AA1.0257 077AAl.0257 A 58 078K201 58 078K2.0158 A 59 086K5.03 59 086K5.0359 D 60 103K3.03 60 103K3.0360 C 61 G2.1.1961 A 62 G2.1.2062 G2.1.20 62 A 63 G2.1.963 D 64 G2.2.2 64 B 65 G2.2.37 65 G2.2.3765 B 66 G2.3.1166 D 67 G2.3.1367 G2.3.13 67 A 68 G2.3.4 68 B 69 G2.4.27 69 G2.4.2769 B B
70 G2.4.4 70 D 71 WEO2EK2.1 WE02EK2.1 71 D 72 WEO5EK3.3 WE05EK3.3 72 D 73 WEI1EA2.173 WEllEA2.173 B 74 WE15EK2.274 C C
75 WE16EG2.4.50 WEI6EG2.4.50 75 C 76 OO1AA2.03 001AA2.0376 76 C 77 006G2.2.39 77 B 78 008AA2.25 78 B B
79 010G2.4.31 79 D D
80 015A2.03 015A2.038080 A 81 81 016A2.01 016A2.018181 D 82 82 025AG2.2.36 025AG2.2.36 82 82 D D
83 83 026A2.02 026A2.028383 C C
84 84 027G2.4.30 8484 C C
85 85 028AA2.1285 028AA2.12 85 D 86 86 035A2.02 035A2.028686 A A
87 87 036AG2.4.8 8787 D D
88 88 058AA2.02 8888 A
Answers
- ID 1
==::::::;:::-'"~--===~~--==="-
89 064A2.06 89 064A2.0689 B 90 065AA2.06 90 B 91 068AG2.2.40 91 C 92 02.1.3192 G2.1.31 92 C 93 02.1.3593 G2.1.3593 A 94 02.2.20 94 G2.2.20 D 95 G2.2.39 95 G2.2.3995 D 96 02.3.1496 G2.3.1496 A 97 02.3.6 97 G2.3.697 A 98 02.4.26 98 G2.4.2698 B 99 WEO4EA2.1 99 WE04EA2.199 D 100 WEO5G2.4.20 100 WE05G2.4.20 C