Text

May, 05000369-08-301 & 05000370-08-301 Final As-Given RO Written Exam
	ML082680261
Person / Time
Site:	Mcguire, McGuire
Issue date:	09/24/2008
From:	; Duke Energy Carolinas
To:	; NRC/RGN-II
References
	50-369/08-301, 50-370/08-301, ES-401-7 50-369/08-301, 50-370/08-301
	Download: ML082680261 (84)
	v • d • e

Final Submittal (Blue Paper)

/i$-G-IV&J<-J FINAL RO WRITTEN EXAMINATION

l ~ij~

I Pearson NCS Test Sheet

-- 100 f~-

.J (

J Noo 106173

- it T F Reorder Form No. 106173 76 ©©

-~ 1-800-367-6627

-t:i -~ 77@© Fax 1-507-451-4513 valuebridge. ncspearson.com

-~

78 ©

-t:l -~ 79QD@©

-~

-~ 80 © ANSWER KEY INFO.

PERFORMANCE ASSESSMENT

-<: -~ c 8100 ©

OF KEYS ITEM

%OF TOTAL POINTS EARNED SCORE

-=w

'COUNT' 00=100%

82 © II

--- 83©©

<DCD,cpm E I-=-i-=+-=-+-=~".-f g

tCDffiCD([)ffi

--- 84 85©@

-- 86 ©

<ID x@

L@@

--- 87©© CDc=D

~(Z)m 0CD

--- 88©@@

AU rights reserved. Printed in U.S.A.

--- 9000 © 91©© 92©

--- 93 94

©

--- 95 ©©©

--- 96 97

©

<ID©©

--- 98 © 99 ©© 100©@

- it Ir COMBINED! II I '\

I

-~

POINTS

-0 -~ I EARNED I I L

-~ , COMBINED r 11 I

Ii

-~

PERCENT 7

-~ I CORRECT I I <-

-t:l

->; I -n- I I .J

~ ROSTER LETTER 'L"

-~

I Iii

-~c NUMBER GRADE I i~ SCORE )

---=w RESCORE MARKING I

I INSTRUCTIONS CDffiCDffiCDffiCDffim(D cv@cvcvm NAME Use a No.2 Pencil 0

--- SUBJECT (IS) ©© Fill oval completely mmCV@00m0 cvmCV0 CV<DCDillCD 0 PERIOD DATE ©© Erase cleanly recyclable paper

ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet u.s. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: Facility/Unit: McGuire 1 and 2 Region: II Reactor Type: Westinghouse 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after the examination begins.

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

Applicant's Signature Results Examination Value ----

Points Applicant's Score ----

Points Applicant's Grade Percent NUREG-1 021, Revision 9

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator

1. A B C 0 26. A B C 0

2. A B C 0 27. A B C 0

3. A B C 0 28. A B C 0

4. A B C 0 29. A B C 0

5. A B C 0 30. A B C 0

6. A B C 0 31. A B C 0

7. A B C 0 32. A B C 0

8. A B C 0 33. A B C 0

9. A B C 0 34. A B C 0

10. A B C 0 35. A B C 0

11. A B C 0 36. A B C 0

12. A B C 0 37. A B C 0

13. A B C 0 38. A B C 0

14. A B C 0 39. A B C 0

15. A B C 0 40. A B C 0

16. A B C 0 41. A B C 0

17. A B C 0 42. A B C 0

18. A B C 0 43. A B C 0

19. A B C 0 44. A B C 0

20. A B C 0 45. A B C 0

21. A B C 0 46. A B C 0

22. A B C 0 47. A B C 0

23. A B C 0 48. A B C 0

24. A B C 0 49. A B C 0

25. A B C 0 50. A B C 0 Page 2 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator

51. A B C D

52. A B C D

53. A B C D

54. A B C D

55. A B C D

56. A B C D

57. A B C D

58. A B C D

59. A B C D

60. A B C D

61. A B C D

62. A B C D

63. A B C D

64. A B C D

65. A B C D

66. A B C D

67. A B C D

68. A B C D

69. A B C D

70. A B C D

71. A B C D

72. A B C D

73. A B C D

74. A B C D

75. A B C D Page 3 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 001 With Unit 1 at 1000/0 power, the following occurs:

A leak in the Letdown Line develops outside Containment.

NC Pressure drops to 1825 psig and stabilizes.

All systems operate as designed.

Which ONE (1) of the following identifies the systems, if any, that have been isolated from the Reactor Coolant Pump (NCP)?

A. RN, KC and Seal Water Return.

B. Seal Water Return ONLY.

C. RN and KC flow ONLY.

D. No systems have been isolated.

Page 4 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 002 Unit 2 is collapsing the pzr steam bubble and placing the pzr in a water solid condition in accordance with OP/2/A/61 00/SO-8, Water Solid Operations.

Which ONE (1) of the following describes the reason for placing the pzr in a water-solid condition?

A. Facilitate placing LTOP in service.

B. Ensure a complete crud burst cleanup.

C. Maintain NC System cooldown rate within limits.

O. Facilitate degasification of the NC System.

Page 5 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 003 The following conditions exist on Unit 1:

Plant shutdown and cooldown to 100°F is in progress.

NC System temperature 180°F.

Both trains of NO are in service in accordance with station procedures.

The power supplies to 1ND-1 Band 1ND-2AC are 600V _ _1_ _ Load Centers and the status of their motor breakers are 2- - -

A. (1) Unit (2) OPEN B. (1) Unit (2) CLOSED C. (1) Essential (2) OPEN D. (1) Essential (2) CLOSED Page 6 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 004 While Unit 1 is at power, a Reactor Trip/Safety Injection occurs and all systems operate as designed. The following trend is observed over the next 15 minutes for NC System pressure:

Time after Trip/SI NC Pressure 1 minute 1800 psig 4 minutes 1600 psig 8 minutes 1400 psig 10 minutes 1200 psig Which ONE (1) of the following is an NI Pump first observable response in the Control Room?

A. Discharge pressure starts to DECREASE and motor amps start to INCREASE between 4-7 minutes.

B. Discharge flow starts to INCREASE and motor amps start to DECREASE between 4-7 minutes.

C. Discharge pressure starts to DECREASE and motor amps start to INCREASE between 8-10 minutes.

D. Discharge flow starts to INCREASE and motor amps start to DECREASE between 8-10 minutes.

Page 7 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 005 While Unit 1 is at 100 % power the Seal Water Return Filter becomes completely clogged.

Which ONE (1) of the following parameters is indicative of this failure?

A. Seal Water supply flow on all four NC Pumps increase.

B. Seal Water return flows on all four NC Pumps decrease to a gpm.

C. NC Pump number 2 seal leakoff flows decrease.

D. PRT level increase.

Page 8 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 006 With Unit 2 at 1000/0 power, the following conditions exist:

B Train equipment in operation.

The 2B1 KC Pump trips on overcurrent and is NOT available.

The operator implements the appropriate response procedures and restores the KC System to normal operation.

Which ONE (1) of the following identifies the electrical power source(s) supplying the operating Component Cooling (KC) Pump(s)?

A. 2ELXA and 2ELXB.

B. 2ETA and 2ETB.

C. 2ELXA ONLY.

D. 2ETA ONLY.

Page 9 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 007 Unit 1 is operating at 30% power with the following conditions:

Train B KG is in operation with both the 1B1 and 1B2 KG Pumps operating.

Train A KG is in standby with both the 1A1 and 1A2 KG Pumps off.

Which ONE (1) of the following events will automatically start the 1A1 KG Pump?

A. The 1B2 Pump trips on overcurrent OR an event causing containment pressure to increase to 1.5 psig.

B. An event causing containment pressure to increase to 1.5 psig ONLY.

G. The normal supply breaker to 1ETB opens OR a leak on the shell side of the 1B KG heat exchanger occurs.

G. The normal supply breaker to 1ETB opens ONLY.

Page 10 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 008 Unit 2 is operating at 1000/0 with the pzr Pressure Control Selector Switch in the 1-4 position.

Which ONE (1) of the following pzr Pressure Channel failure events would result in 2EMF 38, Containment Particulate Radiation Monitor, going into alarm?

(assume no operator action is taken)

A. Channel 1 failing low OR Channel 3 failing high.

B. Channel 1 failing low ONLY.

C. Channel 1 OR Channel 4 failing low.

D. Channel 4 failing low ONLY.

Page 11 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 009 Unit 2 is at 100 % power.

All SSPS Channel I bistable status lights simultaneously illuminate.

Power Range NI Channel N-41 indication is lost.

Intermediate Range Channel N-35 indication is lost.

Power Range Channels N-42, N-43, and N-44 indicate 100 %

Which ONE (1) of the following describes the failure that has occurred, AND the response of the Reactor Protection System?

A. Loss of DC Bus DCA; Train A SSPS General Warning Alarm is received.

B. Loss of DC Bus DCA; The PCS Power Supply Failure Protection Cabinet 1 & 2 alarms are received.

C. Loss of 120 VAC Bus EKVA; The SSPS Train A General Warning Alarm is received.

D. Loss of 120 VAC Bus EKVA; The PCS Power Supply Failure Protection Cabinet 1 & 2 alarms are received.

Page 12 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 010 Unit 1 is at 100 % power.

pzr Pressure Protection Channel III (1 NC-PT-5170) fails and is properly removed from service.

Which ONE (1) of the following identifies the Reactor Trip and Safety Injection actuation logic required (from the remaining in-service channels) on Low pzr Pressure?

Reactor Trip Safety Injection A. 1/2 1/2 B. 1/3 1/3 C 1/3 2/3 D. 2/3 2/3 Page 13 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 011 Which ONE (1) of the following automatic actuations requires an energized bistable and a Containment Pressure Control System signal for it to occur?

A. Startup of the Containment Spray System.

B. Startup of the Annulus Ventilation System.

C. Startup of the Hydrogen Skimmer Fans.

D. Startup of the Containment Air Return Fans.

Page 14 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 012 With Unit 1 in Mode 1 the following sequence of events occur:

0750 200 gpm RV System leak occurs inside Containment.

0751 MCB Annunciator 1AD-13/C-5, Containment Floor and Equipment Sump A High Level, - In Alarm.

MCB Annunciator 1AD-13/E-5, Containment Floor and Equipment Sump B High Level, - In Alarm.

0755 Operators manually close all RV Containment Isolation Valves in order to stop the leak.

0825 Operators have observed .1°F increase in both upper and lower Containment temperature since the RV System was isolated.

Upper level of Containment was initially at 88°F.

Lower level of Containment was initially at 104°F.

Assume that the RV System remains isolated and Containment heat-up rate remains constant.

Which ONE (1) of the following identifies the approximate time before a Technical Specification Containment Temperature limit will be exceeded, AND the procedure that must be used to restore Containment sump level?

A. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; OP/1/A/6500/001, Liquid Waste System.

B. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; AP/1/A/5500/44, Plant Flooding.

C. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; OP/1/A/6500/001, Liquid Waste System.

D. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; AP/1/A/5500/44, Plant Flooding.

Page 15 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 013 The following conditions exist on Unit 1:

The plant is starting up following a Refueling Outage.

An instantaneous double-ended shear of NC Loop C (Large Break LOCA) occurs.

Several Ice Condenser Upper and Lower doors fail to open.

Which ONE (1) of the following identifies a consequence of the failed doors?

A. The Hydrogen Skimmer and Containment Air Return (VX) System automatic actuation is delayed.

B. Water that accumulates in the Containment Sump will have a substantially lower Boron concentration.

C. Less water will accumulate in the Containment Sump within the first 15 minutes of the event.

D. FWST inventory will decrease at a faster rate.

Page 16 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 014 With Unit 1 at power the following Ice Condenser equipment status exists:

All NF Air Handling Units - On

1A and 1B NF Glycol Pumps - On

1A, 1B, 1C and 1G NF Chillers - On

Ice Machines/Ice Loading Equipment - Off Ice Condenser Aggregate Temperature is being maintained at 15°F.

Subsequently, one Chiller and one Glycol Pump are removed from service, and Ice Condenser Aggregate Temperature stabilizes at 25°F.

Which ONE (1) of the following describes a consequence of this event?

A. Sublimation of the ice will occur at a higher rate.

B. Containment Temperature will approach a Technical Specification limit.

C. Aggravation of the NF System Freeze/Thaw Cycle will be minimized.

D. The Technical Specification limit for Ice bed temperature will be exceeded.

Page 17 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 015 The following conditions exist on Unit 1:

A plant cooldown and depressurization is in progress.

NC System Temperature is 320°F.

NC System Pressure is 325 psig.

All plant components are aligned normally for the present plant conditions.

Subsequently, a fire in the breaker cubicle for the 1B NS Pump occurs.

Which ONE (1) of the following describes the impact on Technical Specification LCO 3.6.6, Containment Spray System?

A. LCO 3.6.6 MUST be entered with operability restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

B. LCO 3.6.6 MUST be entered with operability restored within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

C. LCO 3.6.6 will NOT be entered because the A Train of NS is operable.

D. LCO 3.6.6 will NOT be entered because it is NOT applicable in the present plant Mode of Operation.

Page 18 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 016 The following conditions exist on Unit 1:

Large Break LOCA in progress.

Train B NO aligned for CLR.

1NI-185A (RB Sump to Train A NO and NS) cannot be opened, and 1A NO Pump has been stopped.

FWST level is 30 inches.

Both 1A and 1B NS Pumps are stopped.

Which ONE (1) of the following identifies an action that must occur to avoid exceeding peak Containment pressure?

A. The 1A NS Pump must be restarted taking suction from the FWST until the 1B NS pump can be aligned for recirculation.

B. The 1A NO Pump must be restarted taking suction from the FWST until the 1B NS pump can be aligned for recirculation.

C. The 1B NS Pump must be restarted in the recirculation alignment and RN flow established to the 1B NS Heat Exchanger within 3 minutes.

O. The 1B NO Pump must be manually aligned to provide NS within 30 minutes.

Page 19 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 017 With Unit 2 at 100 % power the following occurs:

B Train equipment is in service.

The normal supply breaker to 2ETA opens.

Which ONE (1) of th~ following would be indicative of an expected response of the Unit 2 CA System?

A. The Unit 2 Turbine Driven CA Pump RPM is at 3600.

B. The 2SA-48ABC position status light is RED and the 2SA-49AB position status light is GREEN.

C. No Steam Pressure is indicated on 2SA-PT5000 (Steam to FWPT Pressure).

D. 2AD-5/F-3, CA Pump Turbine Stop Valve NOT Open, is ILLUMINATED.

Page 20 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 018 Unit 1 is in Mode 3 conducting a plant depressurization and cooldown in accordance with OP/1/A/6100/SD-2, Cooldown to 400°F.

The following conditions exist:

NC System pressure 1900 psig

NC System temperature 557°F

All Steam Generator pressures 1100 psig

Low Pressure SI and Low Pressure Steamline Isolation have been blocked.

The operator has just begun an 80°F/hour cooldown.

Which ONE (1) of the following conditions would automatically close all four Main Steam Isolation Valves?

A. NC Pressure increases to 2000 psig.

B. Containment Pressure increases to 1 psig.

C. 1A Steam Generator Pressure drops to 900 psig in 2 seconds.

D. 1B Steam Generator Pressure drops to 700 psig consistent with NC Cooldown.

Page 21 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 019 The following conditions exist on Unit 1:

The plant is at 41 % power.

AMSAC UNBLOCK Light - LIT

Power increase in progress.

A CF Pump running.

CF Main Control valves at 240/0 open.

Which ONE (1) of the following will result in an AMSAC actuation?

A. The C SG controlling Steam Flow channel fails low.

B. Power level is raised to 55% prior to starting B CF Pump.

C. The CF Control Valve bypasses are throttled in the closed direction.

D. Closure of 0 SG CF Containment Isolation valve.

Page 22 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 020 Unit 1 is operating at 100 % power.

After an automatic start of the 1TO CA Pump, a malfunction has occurred which has limited its flow to 300 gpm.

Which ONE (1) of the following identifies the event in which this malfunction will result in a loss of core cooling?

(Assume No operator action)

A. Total Loss of All AC Power.

B. Large Break LOCA.

C. Both CF Pumps simultaneously trip with a simultaneous ATWS.

D. Design Basis SGTR.

Page 23 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 021 The B Train of essential equipment is in operation on Unit 1.

While performing OP/1/A/6350/002 (Diesel Generator) with the 1A Diesel running in parallel to the grid, the following sequence of events occurs:

Load is reduced on the diesel to 200KW in anticipation of opening the Emergency Breaker.

The RO accidentally OPENS the Normal Feeder Breaker from 1ATC.

Which ONE (1) of the following completes the statement below?

The Blackout Sequencer Actuated Train A status light on SI-14 .....

A. lights and the Emergency Breaker trips open, then re-closes 8.5 seconds later.

B. remains dark and the Emergency Breaker trips open, then re-closes 8.5 seconds later.

C. lights and the 1A DG Load increases.

D. remains dark and the 1A DG Load increases.

Page 24 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 022 McGuire Station has experienced a Loss of Off-site power.,

The following timeline shows CXAlCXB voltage over the course of the event:

Time after LOOP CXA CXB 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 128v 123v 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 124v 116v 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 118v 114v 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 115v 113v 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 113v 112v 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 111v 111v Assuming the current trends continue, Battery CXA will be lost in _(1.1- hours.

Battery CXB will be lost in _(2)_ hours.

(1) (2)

A. 2 4 B. 2 6 C. 3 4 D. 3 6 Page 25 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 023 With Unit 1 at 100 % power the following conditions exist:

The 1A DG is in standby.

A fuel oil leak in 1A DG Fuel Oil Storage Tank is occurring.

Fuel Oil Storage Tank volume was 43,600 gallons at the start of the leak.

When the leak is contained, the Fuel Oil Storage Tank level was stabilized with a volume of 30,000 gallons.

The trend of the tank volume is as follows:

1030 39,900 gallons 1100 38,600 gallons 1130 31 ,200 gallons 1200 30,000 gallons Of the following choices, which ONE (1) of the following is the EARLIEST time that 1A DG parameters require entry into a Technical Specification action statement?

A. 1030 B. 1100

c. 1130 D. 1200 Page 26 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 024 With Unit 2 at 100 % power, the following conditions exist:

Train A equipment is in operation.

The power supply to 2EMF46A, Train A Component Cooling, has failed.

Which ONE (1) of the following describes the impact of this event, AND what procedure will be used to address the situation?

A. KC-122, Component Cooling Water Surge Tank Vent, will auto close; Address Annunciator Response for 2RAD-1/A-4 2EMF 46A Train A KC Hi Rad.

B. KC-122, Component Cooling Water Surge Tank Vent, will auto close; Address AP/2/A/5500/21, Loss of KC or KC System Leakage.

c. ONLY a Main Control Board alarm will occur; Address Annunciator Response for 2RAD-1/A-4 2EMF 46A Train A KC Hi Rad.

D. ONLY a Main Control Board alarm will occur; Address OP/2/A/6400/005, Component Cooling Water System, to swap KC Trains.

Page 27 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 025 Unit 1 is at 100 % power with Train B equipment in service when the following occurs:

The 1B RN pump trips.

AP-20, Loss of RN, is implemented.

Which ONE (1) of the following describes why the operator places the manual loader for 1RN-89A (RN to KC HX Control) to 10 % open prior to starting the 1A RN Pump?

A. To ensure a minimum flow is maintained from the 1A RN Pump.

B. To prevent runout of 1A RN Pump.

C. To prevent high temperatures on the KC System.

D. To prevent water hammer in the KC Heat Exchanger.

Page 28 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 026 Following ~ reactor trip from 100 % power the following conditions exist on Unit 2:

NC Pressure is 1400 psig.

Containment Pressure has risen slowly to 2.4 psig.

The 2A RN Pump failed to start.

Which ONE (1) of the following describes the impact of the 2A RN Pump failure?

A. ONLY the 2A NV Pump gear oil will overheat.

B. The 2A NS Pump Motor AND the 2A NV Pump gear oil will overheat.

C. The 2A1 and 2A2 DG VG Air Compressors AND the 2A NV Pump gear oil will overheat.

D. The 2A NS Pump Motor AND the 2A NV Pump gear oil will overheat.

Additionally, all Makeup capability is lost to the 2A DG KD Surge Tank.

Page 29 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 027 Given the following:

Unit 1 is at 100 0ib power.

The VI system is in a normal lineup.

The VS system is in a normal lineup.

A VI header rupture occurs.

VI system pressure is 80 psig and lowering.

The crew is performing actions of AP/22, Loss of VI.

The CRSRO dispatches an operator to perform Enclosure 2, Startup of 0, E and F VI Compressors.

Which ONE (1) of the following identifies the actions required to be performed to prepare 0, E, and F VI Compressors for starting?

A. RL Pumps must be verified running with adequate discharge pressure prior to startup of 0, E, and F VI compressors. Performance of Enclosure 6, 0, E and F VI Compressor Operation with Low Control Air, is NOT required.

B. RL Pumps must be verified running with adequate discharge pressure prior to startup of 0, E, and F VI compressors. Enclosure 6, 0, E and F VI Compressor Operation with Low Control Air, must also be performed to provide VB control air supply to VI compressors.

C. KR Pumps must be verified running with adequate discharge pressure prior to startup of 0, E, and F VI compressors. Performance of Enclosure 6, 0, E and F VI Compressor Operation with Low Control Air, is NOT required.

D. KR Pumps must be verified running with adequate discharge pressure prior to startup of 0, E, and F VI compressors. Enclosure 6, 0, E and F VI Compressor Operation with Low Control Air, must also be performed to provide VB control air supply to VI compressors.

Page 30 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 028 Which ONE (1) of the following describes how the following valves can be operated from the Control Room?

1VQ-3 (Containment Air Addition Inlet from Auxiliary Building Isolation Valve)

1VQ-4 (Containment Air Release to Unit Vent) 1VQ-3 1VQ-4 A. Operates automatically when Press open/close pushbuttons.

other system valves are opened manually.

B. Press open/close pushbuttons. Manually adjust the output of a pneumatic controller.

C. Press open/close push buttons. Operates automatically when other system valves are opened manually.

D. Operates automatically when Manually adjust the output of a other system valves are opened pneumatic controller.

manually.

Page 31 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 029 Unit 1 Reactor Startup is in progress:

Control Bank A is being withdrawn in MANUAL.

Control Bank A rods are currently at 180 steps.

'Assume proper rod withdrawal sequencing and bank overlap.

Subsequently, Control Bank B, rod F-2 drops fully into the core.

Which ONE (1) of the following completes the statement below?

Rod F-2 is displayed as a.....

A. Green bar with an Orange background, with a Green DRPI Rod Bottom (RB) light.

B. Green bar with an Orange background, with a Red DRPI Rod Bottom (RB) light.

C. Red bar with a Black background, with a Green DRPI Rod Bottom (RB) light.

D. Red bar with a Black background, with a Red DRPI Rod Bottom (RB) light.

Page 32 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 030 Concerning the Train A ICCM Subcooling Margin Monitor: Which ONE (1) of the following malfunctions will cause indicated subcooling margin to be greater than actual subcooling margin?

A. 1 of 3 Loop C NR Thot instruments fails low.

B. Loop 0 Wide Range Tcold fails low.

C. Loop 0 Wide Range Pressure fails high.

D. The controlling pzr Pressure instrument fails high.

Page 33 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 031 The following conditions exist on Unit 1:

A Reactor Startup is in progress.

Power level is 1 x 10-8 amps.

Subsequently, 120 Vital AC Bus EKVB is lost.

Which ONE (1) of the following identifies the plant response?

A reactor trip will occur due to the loss of _(1 )_. And _(2)_.

A. (1) IR NI-35 (2) SR N1-32 will energize B. (1) IR NI-35 (2) SR N1-32 will NOT energize C. (1) IR NI-36 (2) SR NI-31 will energize D. (1) IR NI-36 (2) SR NI-31 will NOT energize Page 34 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 032 A Large Break LOCA has occurred on Unit 2, and the Technical Support Center has recommended the startup of the H2 Purge System.

The crew places the system in service in accordance with OP/1/A/6450101 0, Operation of the Hydrogen Skimmer, Containment Air Return and Hydrogen Purge System.

Based on this action, which ONE (1) of the following describes the initial effect on annulus pressure, and the annulus pressure range that must be maintained?

A. Increase; Maintained at -1.2" to -4.2" H2 0.

B. Increase; Maintained at -5.5" to -7.0" H2 0.

C. Decrease; Maintained at -1.2" to -4.2" H2 0.

D. Decrease; Maintained at -5.5" to -7.0" H2 0.

Page 35 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 033 Unit 1 is in Mode 6 conducting Refueling Operations.

Communications have been established between the Refueling SRO and the OATC in the Control Room.

AUTOMATIC actuation of the Containment Evacuation alarm has failed.

Due to the AUTOMATIC actuation failure, which ONE (1) of the following will require manual actuation of the Containment Evacuation Alarm?

A. Trip 2 on 1EMF-38 (Containment Particulate Monitor)

Trip 2 on 1EMF-16 (Containment Refueling Bridge).

B. Trip 2 on 1EMF-16 (Containment Refueling Bridge)

Excore SR monitors Hi Flux at Shutdown alarm.

C. Gammametrics Shutdown Monitor A HI CPS Alarm Trip 2 on 1EMF-16 (Containment Refueling Bridge).

D. Containment Fire Zone alarms on EDA Computer Excore SR monitors Hi Flux at Shutdown alarm.

Page 36 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 034 Unit 1 is in Mode 5 with the following conditions:

Spent Fuel Pool fuel handling operations was secured 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago.

1ETB and related equipment has been just removed from service.

VF System is operating normally in accordance with OP/1/A/6450/004, Fuel Pool Ventilation System.

Subsequently:

The 1A KF Pump trips.

SPENT FUEL POOL TEMP HI OAC alarm occurs.

EMF-42, Fuel Building Ventilation Radiation Monitor, is in Trip 2.

Which ONE (1) of the following describes the AUTOMATIC response of the Fuel Handling Building Ventilation System (VF)?

A. The Outside Air Damper (D-1) will close.

B. The Exhaust Filter Bypass Damper (D-5) will close.

C. The Filter Isolation Dampers (D-3 & D-4) will close.

D. The Supply Fan will stop.

Page 37 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 035 Unit 1 is operating at 100 % power and aligned normally when the following event occurs:

1SMLP5080 (1A SG Steam Pressure Channel 1) fails high.

Which ONE (1) of the following describes the actual impact on ~he 1A Steam Generator and the procedure that would be used to respond to the event?

A. Steam flow increases, AP/1/A/5500/001 (Steam Leak)

B. Steam flow decreases, AP/1/A/5500/001 (Steam Leak)

C. Feed flow increases, AP/1/A/5500/006 (SG Feedwater Malfunction)

D. Feed flow decreases, AP/1/A/5500/006 (SG Feedwater Malfunction)

Page 38 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 036 With Unit 2 at 100 % power the following conditions exist:

A Loss of Off-site Power occurs.

Tavg is 564°F and decreasing.

Which ONE (1) of the following completes the statement below?

Steam Dump valves will indicate _1_, and _2_.

A. closed NO steam flow is indicated on ANY SG B. closed steam flow is indicated on ALL SGs C. open steam flow is indicated on ALL SGs D. open and closed steam flow is indicated on ALL SGs Page 39 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 037 Both Units are at 100 % power:

The VA System is operating normally, with the 1A/1B AHU, Filtered Exhaust Fans, and Unfiltered Exhaust fans all running.

The Filtered Exhaust Filter is bypassed.

While operating a valve associated with Waste Gas Compressor A, a leak develops and releases approximately 500 ft 3 of radioactive gas into the Auxiliary Building over a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period.

Which ONE (1) of the following could detect this leak AND cause an automatic response by the VA System?

A. 1EMF-36 (Unit Vent Gas) ONLY B. 1EMF-41 (Aux Building Ventilation) ONLY C. EITHER 1EMF-36 (Unit Vent Gas) OR 1EMF-37 (Unit Vent Iodine)

D. EITHER 1EMF-41 (Aux Building Ventilation) OR 1EMF-37 (Unit Vent Iodine)

Page 40 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 038 Which ONE (1) of the following describes the primary fire suppression system used in the Unit 2 Cable Spreading Room, and the reason for this type of system?

A. A manually operated Mulsifyre system, because water spray is an effective means for extinguishing deep-seated Class C fires.

B. An automatically operated Mulsifyre system, because water spray reduces the risk of electrical explosion as opposed to deluge systems.

C. A manually operated Halon 1301 system, because halon provides effective extinguishing properties for electrical components with minimal spread of hazardous material.

D. An automatically operated Halon 1301 system, because water spray is NOT an effective means for extinguishing deep-seated Class C fires.

Page 41 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 039 Unit 1 is operating at 100 %

The following Main Control Board indications exist:

Channel 1 Channel 2 Channel 3 Channel 4 NCP Bus Frequency (Hz) 55.0 56.0 57.0 58.0 Power Range (%) 107 108 108 109 S/G B NR Level (%) 18 18 19 16 pzr Pressure (psig) 2383 2384 2385 2386 Which ONE (1) of the following identifies the Annunciators that WILL be lit on 1FO-1?

A. F-6, NC Pump Bus Under Freq Rx Trip B-2, S/G B La-La Lvi Rx Trip B. B-7, P/R Hi Flux Hi Stpt Rx Trip B-5, pzr Hi Press Rx Trip C. B-2, S/G B La-La Lvi Rx Trip B-7, P/R Hi Flux Hi Stpt Rx Trip D. B-5, pzr Hi Press Rx Trip F-6, NC Pump Bus Under Freq Rx Trip Page 42 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 040 The following conditions exist on Unit 2 following a Reactor Trip from high power: '

A break in the pzr Steam Space has resulted in a Small Break LOCA.

The operating crew has entered ES-1.2, Post-LOCA Cooldown and Depressurization.

Steam Dumps have been placed in the Steam Pressure Mode, and the Steam Dump Cooldown valves are presently throttled open.

The Steam Dump Pressure Controller potentiometer is presently set at 6.9 Turns, and is operating in AUTO.

The P-12 Interlock has been defeated.

NC Temperature is stable.

Which ONE (1) of the following describes the action as stated in ES-1.2 that will be taken to initiate and maintain a constant NC System Cooldown rate of less than 100°F/hour?

A. Lower Steam Dump Pressure Controller potentiometer to 6.5 turns.

B. Raise Steam Dump Controller potentiometer to 7.4 turns.

C. Place the Steam Dump Pressure Controller in manual and raise output.

D. Place the Steam Dump Pressure Controller in manual and lower output.

Page 43 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 041 The following conditions exist on Unit 2 thirty (30) minutes after an automatic Reactor Trip due to a Loss of Offsite Power:

NC Pressure 1600 psig and going down slowly

Core Exit Temperature 582°F and stable

That indication 567°F and stable

Tcold indication 555°F and stable

pzr Level 8% and slowly going down

Containment Pressure 2.5 psig and rising

Steam Generator Pressures Normal post-trip pressure for plant conditions

.Total CA Flow 270 gpm Which ONE (1) of the following describes the relationship between the NC System and the Steam Generators, and what procedure would be entered to mitigate the event?

The Steam Generators are a Heat _(1)_ to the NC System, and _(2)_ will be implemented.

A. (1) SINK (2) ES-0.2, Natural Circulation B. (1) SINK (2) E-1, Loss of Reactor or Secondary Coolant

c. (1) SOURCE (2) ES-O.2, Natural Circulation D. (1) SOURCE (2) E-1, Loss of Reactor or Secondary Coolant Page 44 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 042 After a transient from 1000/0 power, the following conditions exist on Unit 1:

NC System pressure = Containment Pressure.

Containment Radiation Monitors in Alarm.

All systems operated as designed.

Which ONE (1) of the following is an expected response, AND the basis for the response, of the Containment Isolation System?

A. ONLY Phase A Containment Isolation has actuated to ensure that the NCPs will be available later to mitigate the consequences of this event.

B. ONLY Phase A Containment isolation has actuated to ensure that all penetrations that were open directly to the Containment Atmosphere are now isolated.

C. Both Phase A and Phase B Containment Isolation have actuated to ensure isolation of non-ESF related Containment piping penetrations ONLY.

D. Both Phase A and Phase B Containment Isolation have actuated to ensure isolation of ALL Containment piping penetrations.

Page 45 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 043 Unit 2 is in Mode 1 when the safety breaker to 2C NCP inadvertently opens.

The reactor did NOT trip.

The following Permissive Bistable Status light conditions are observed:

P-7 Lo Power Rx Trips Blocked - DARK

P-8 Hi Pwr Lo Flo Rx Trip Blocked - LIT

P-10 Nuclear At Power - LIT

P-13 Turbine Not At Power - LIT Which ONE (1) of the following identifies initial plant condition and identifies the expected plant response?

Initial reactor power was and A. less than 100/0 plant response is correct B. greater than 10 %

plant response is correct C. less than 10%

auto reactor trip has failed D. greater than 10%

auto reactor trip has failed Page 46 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 044 Unit 2 is at 100 % when:

All charging flow was lost.

Letdown was isolated.

The Standby Makeup Pump cannot be started.

Seal leakoff flow from #1 Seal on each NC Pump is 3 gpm.

Assuming no further operator action is taken, which ONE (1) of the following predicts the approximate time that Annunciator 2AD-6/E-7, pzr Lo Level Deviation, will alarm?

(Reference Provided)

A. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months C. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months D. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Page 47 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 045 Given the following events and conditions:

Unit 1 is approaching Mode 5.

NG Gooldown is in progress.

A Train NO is in the RHR mode.

A Train KG is in service at maximum design flow.

A Train RN is in service.

1A 1 KG Pump breaker trips.

Which ONE (1) of the following describes the effect on the KG and NG System temperatures?

A. KG is unaffected; NG heats up.

B. KG heats up; NG is unaffected.

G. KG heats up; NG cooldown rate decreases.

D. KG is unaffected; NG cooldown rate is unaffected.

Page 48 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 046 Unit 1 is operating at 50% power. Given the following conditions:

pzr pressure is 2235 psig.

pzr Relief Tank (PRT) pressure is 20 psig.

PRT temperature is 125°F.

PRT level is 81 %.

The PRT is being cooled by spraying from the RMWST.

A pzr code safety valve is leaking by its seat.

Which ONE (1) of the following identifies the temperature that would be indicated on the leaking safety valve discharge RTD?

(Reference Provided)

B. 227° - 231°F Page 49 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 047 With Unit 1 at 90% power the following conditions exist:

RPS Testing is in progress.

Reactor Trip Breaker A (RTA) is CLOSED.

Reactor Trip Breaker B (RTB) is OPEN.

Reactor Trip Bypass Breaker B (BYB) is Racked In and CLOSED.

During the testing the following occurs:

The A NC Pump Shaft seizes.

The Reactor fails to automatically trip.

Manual attempts to trip the Reactor are SUCCESSFUL.

Which ONE (1) of the following identifies the Reactor Trip/Bypass Breaker trip coil that has operated as designed throughout the event?

A. RTA Undervoltage Coil.

B. RTA Shunt Trip Coil.

C. BYB Undervoltage Coil.

D. BYB Shunt Trip Coil.

Page 50 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 048 As stated in ECA-O.O, Loss of all AC Power, which ONE (1) of the following is the basis for NOT depressurizing the S/Gs to less than 110 psig?

To avoid - - - - -

A. voiding in the head.

B. an inadvertent criticality accident.

C. nitrogen injection into the NC System.

D. the loss of S/G narrow range level.

Page 51 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 049 Unit 2 is operating at 100 % power when a loss of off-site power (LOOP) occurred.

Which ONE (1) of the following describes the expected operation of Containment Ventilation Systems ONE (1) minute after the event?

VU Ventilation Units VL Fans Pipe Tunnel Booster Fans A. Running Low Speed Running B. Running Low Speed Off C. Running High Speed Off D. Off High Speed Running Page 52 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 050 Unit 1 is at full power with all systems selected to automatic. Given the following event:

All Channel 1 Status lights are LIT.

Which ONE (1) of the following identifies why the crew would have to place Rod Control in Manual?

Because....

A. Power Range N41 has failed high.

B. Loop A Tavg has failed low.

C. Turbine Impulse Pressure Channel 1 has failed low.

D. Turbine Impulse Pressure Channel 1 has failed high.

Page 53 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 051 Unit 1 was operating at 1000/0 power when a total loss of onsite and offsite power occurred. Given the following events and conditions:

1EVDA is supplying normal full power loads.

NO battery charger is available.

Which ONE (1) of the following statements describes the MINIMUM length of time that bus 1EVDA is designed to sustain loads AND what action will protect the DC bus loads?

A. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; The vital battery bus breaker will open automatically when bus voltage falls to 105 volts.

B. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; The vital battery breaker must be manually opened when bus voltage falls to 105 volts.

C. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; The vital battery breaker will open automatically when bus voltage falls to 107 volts.

D. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; The vital battery breaker must be m-anually opened when bus voltage falls to 107 volts.

Page 54 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 052 With Unit 1 at 100 0/0 power, a total loss of RN occurs and cannot be restored.

The following pumps were running at the start of the event:

1A NV Pump

1A1 KG Pump

1A2 KG Pump Which ONE (1) of the following identifies the pump(s) that will reach an operating limit and the MINIMUM time frame within which the limit will be reached?

A. 1A NV Pump; 15-20 minutes.

B. 1A1 and 1A2 KG Pumps; 15-20 minutes.

G. 1A NV Pump;90-120 minutes.

D. 1A1 and 1A2 KG Pumps;90-120 minutes.

Page 55 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 053 Both Units are at 100 % power when:

MNS experiences a loss of VI.

VI Header pressure on both units is 30 psig and continues to decrease.

Which ONE (1) of the following will be FIRST to trip the reactor and its basis?

A. OT Delta T trip due to the MSIVs failing closed.

B. High-High SG level trip because the Feedwater Reg Valves fail open.

C. Turbine Trip due to Feed Pump Trip because the Feedwater Reg Valves fail closed.

D. High pzr Level trip due to the Charging Flow Control Valve failing open with Letdown isolated.

Page 56 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 054 Given the following:

Unit 1 has tripped.

A LOCA Inside AND Outside Containment is in progress.

NO relief valves are lifting and stuck open.

The PRT has ruptured.

Containment pressure is rising.

NS actuation has occurred.

The crew is performing ECA-1.2, LOCA Outside Containment.

The following conditions exist:

NO Pumps are secured.

The leak has NOT been isolated.

Containment pressure 8.5 psig.

BOTH trains of NS are operating, aligned to FWST.

Which ONE (1) of the following describes the action required for NS operation in accordance with ECA-1.2?

A. Both NS Pumps must be stopped to conserve FWST inventory.

B. ONLY ONE (1) NS pump must be stopped to minimize depletion rate of FWST.

C. Both NS Pumps must remain running as directed by FR-Z.1, Response to High Containment Pressure.

D. At least ONE (1) NS pump must remain running until no longer required after transition to E-1, Loss of Reactor or Secondary Coolant.

Page 57 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 055 Unit 1 has experienced a Large Break LOCA inside Containment.

The 1B NV Pump is NOT available.

The NO Pumps are NOT available.

The crew has implemented ECA-1.1, Loss of Emergency Coolant Recirc.

1A NV Pump is running at 400 gpm.

1A NI Pump is running at 400 gpm.

1B NI Pump is running at 400 gpm.

The Standby Makeup Pump is NOT available.

The Reactor Trip occurred 31 minutes ago.

You have been directed to determine minimum required SI flow per Enclosure 9, Flow Required to Match Decay Heat, of ECA-1.1 to minimize SI flow while maintaining greater than or equal to the required flow.

Which ONE (1) of the following will result in the LEAST number of running pumps which will satisfy the MINIMUM SI flow requirement?

(Reference Provided)

A. Stop both NI pumps.

B. Stop one NI pump ONLY.

C. Stop the NV pump AND one NI pump.

D. All available pumps must remain running.

Page 58 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 056 With Unit 2 at 100 % power the following events occur:

A steam line rupture has occurred on the common header downstream of the MSIVs.

All four MSIVs have failed to automatically or manually close from the Main Control Board.

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

Which ONE (1) of the following describes the NEXT action taken to attempt closure of the MSIVs?

Dispatch an operator to the .....

A. Battery Room to open the EVDA and EVDD breakers powering the MSIV control circuits.

B. Doghouse to isolate and bleed VI via the manual loader to the MSIVs.

c. Doghouse to RAISE VI pressure in the MSIV Air Assist Accumulator.

D. Doghouse to LOWER VI pressure in the MSIV Air Assist Accumulator.

Page 59 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 057 Unit 2 is operating at 1000/0 power when a runback occurs.

The Rod Control System responds as designed.

Rod M-12 in CIB 0 has stopped moving.

The OATC leaves rods in AUTO and allows the rest of the CIB 0 rods to respond.

A Rod Control Urgent Failure alarm is received due to a Regulation Failure on Rod M-12 in Power Cabinet 1BO.

The OATC places the CIR Bank Select Switch in MANUAL and attempts to insert Control Rods.

Which ONE (1) of the following describes the response of the Rod Control System and the effect of the Power Cabinet 1BO Rod Control Urgent Failure on the Rod Control System?

Rod motion - - - occur and - - - -

A. will; Bank 0, Group 2 rods ONLY will insert. Group 1 rods in CIB Bank 0 will not move.

B. will; rod motion for the affected Banks and Groups is ONLY affected in Auto.

C. will NOT; both Auto and Manual rod demand signals are blocked. Rods may ONLY be moved with the selector switch in the CIB 0 position.

O. will NOT; both Auto and Manual rod demand signals are blocked. Rod motion is ONLY possible if the alarm is manually reset.

Page 60 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 058 The following conditions exist on Unit 2:

Power is reduced to 300/0' using AP/2/A/5500/04, Rapid Downpower.

2AD-2/B-9, Rod Control Bank Lo-Lo Limit, is LIT.

A boration of 18 gpm is required to restore rods above RIL.

Which ONE (1) of the following identifies the number of turns from zero that the potentiomet~r setting on NVSS5450, Boric Acid Flow Controller, must be set to establish this boration rate AND what the Total Blender Flowrate would indicate?

A. 4.5 Turns; 90 gpm.

B. 4.5 Turns; 18 gpm.

C. 1.8 Turns; 90 gpm.

D. 1.8 Turns; 18 gpm.'

Page 61 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 059 Given the following:

A reactor startup is in progress.

Intermediate Range indication is coming on scale.

Proper NI detector overlap is observed.

With no rod motion in progress, Count Rate on N-31 is 103 CPS and lowering. All other NI indications remain normal.

Which ONE (1) of the following describes the possible reason(s) for the Source Range N-31 indication?

A. Pulse Height Discriminator fails low ONLY.

B. Pulse Height Discriminator fails high ONLY.

C. Either the Pulse Height Discriminator fails low OR the Source Range High Voltage power supply fails.

D. Either the Pulse Height Discriminator fails high OR the Source Range High Voltage power supply fails.

Page 62 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 060 Given the following:

A reactor startup is in progress.

11

IR power indicates 8 X 10- amps on both channels and stable.

SR High Flux Trip has NOT been blocked.

IR N-35 starts behaving erratically.

All other NI indications are normal.

The crew enters the appropriate AP and places N-35 Level Trip Bypass Switch in BYPASS. .

Which ONE (1) of the following describes the effect of placing the N-35 Level Trip Bypass Switch in the BYPASS position? In addition, if the _(1)_ power fuse fails, the reactor _(2)_ trip.

A. ONLY the Intermediate Range High Flux Trip is bypassed.

(1) Instrument (2) will B. The Intermediate Range High Flux Trip AND the Intermediate Range High Flux Rod Stop are bypassed.

(1) Instrument (2) will NOT C. ONLY the Intermediate Range High Flux Trip is bypassed.

(1) Control (2) will D. The Intermediate Range High Flux Trip AND the Intermediate Range High Flux Rod Stop are bypassed.

(1) Control (2) will NOT Page 63 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 061 Unit 1 is refueling, with Fuel Handling operations in progress in the Spent Fuel Pool, when the following occurs:

1KF-122 is OPEN.

1EMF-17, Spent Fuel Bldg Refuel Bridge, is in trip 2.

Spent Fuel Pool Level is (+) 0.4 feet and stable.

Spent Fuel Pool Temperature is gO°F and stable.

The 1A KF Pump is operating.

Which ONE (1) of the following is the most likely cause of these conditions?

A. Complete stoppage of air flow through a NAC-UMS dry storage cask within the last 30 minutes.

B. Damage to a Fuel Assembly while being lifted or lowered.

C. Failure of the KF System.

D. A Cavity Seal Failure.

Page 64 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 062 With Unit 1 at 100 % power the following occurs:

Zone 148 Alarm on EFA Computer, RCP 1B Motor.

After acknowledging this alarm, the operator notes the following:

Lower Containment Weighted Average Hourly is 100°F and slowly increasing.

Containment pressure is 0.11 psig and slowly increasing.

1B NC Pump Motor Stator Winding Temperature is 265°F.

1B NC Pump Motor Bearing Temperature is 140°F.

Which ONE (1) of the following identifies the REQUIRED plant procedure(s) that must be implemented to identify vital equipment that may be affected, and actions taken to protect this equipment?

A. AP/1/A/5500108, NC Pump Malfunction AND AP/1/A/5500/45, Plant Fire.

B. AP/1/A/5500/24, Loss of Plant Control Due to Fire or Sabotage ONLY.

C. AP/1/A/5500/45, Plant Fire ONLY.

D. AP/1/A/5500108, NC Pump Malfunction AND AP/1/A/5500/24, Loss of Plant Control Due to Fire or Sabotage.

Page 65 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 063 Which ONE (1) of the following Emergency Procedure actions is taken to MINIMIZE radiological releases?

A. Feeding a Ruptured Steam Generator until level is above the tubes and then stopping feedflow.

B. Stopping and isolating the NO pumps from the FWST during a LOCA outside containment.

C. Isolating steam flow from and feed into a Faulted Steam Generator.

O. Maintaining a minimum CA flow to a hot dry Steam Generator.

Page 66 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 064 Unit 2 was operating at 100 0/0 power when a loss of power to 2B NCP occurred and was compounded by an ATWS event.

Given the following events and conditions:

The Control rods were locally tripped two minutes after the NCP lost power.

Emergency boration has increased NC boron concentration by 15 ppm.

pzr pressure has stabilized at 1780 psig.

The 2B NCP has been restarted.

Containment radiation levels have doubled as indicated by:

2EMF-2, Rx Bldg Incore Inst Rm

2EMF-3, Rx Bldg Refuel Bridge

2EMF-5, NC FIt.2A Which ONE (1) of the following describes the most probable cause of the increase in containment radiation levels following the event?

NCS activity has increased due to ...

A. NCP cycling OR mechanical shock of ECCS actuation.

B. the boron concentration change OR NCP cycling.

C. the boron concentration change OR mechanical shock of ECCS actuation.

D. a loss of letdown flow through the NV Demineralizers OR reactor trip.

Page 67 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 065 Unit 1 is at 100 0/0 power when an inadvertent SI actuation occurred.

The crew is performing ES-1.1, SI Termination.

Normal Charging is aligned.

Nt Pumps are stopped.

NO Pumps are stopped.

pzr level is rising.

Normal Letdown is established.

Subsequently, during verification of NC Pump cooling in ES-1.1, the following occurs:

Seal Injection flow is lost to all NC Pumps.

Charging flow indicates 0 GPM.

pzr level is going down and results in letdown isolation.

pzr level stabilizes prior to reaching SI reinitiation criteria.

Which ONE (1) of the following describes the procedure usage required for these conditions?

A. Return to step 1 of ES-1.1 and reestablish Charging and Letdown.

B. Continue in ES-1.1 until completed, and then proceed to OP/1/A/61 00/002, Controlling Procedure for Unit Shutdown.

C. C-ontinue in ES-1.1 and concurrently attempt to restore Charging and Seal Injection in accordance with AP-12, Loss of Letdown, Charging, or Seal Injection.

O. Immediately suspend ES-1.1; GO TO AP-12 to restore Charging and Seal Injection. When Seal Injection is restored, return to ES-1.1, step in effect.

Page 68 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 066 After two hours into a shift on Unit 1, the OATC reviews the Control Room Unit Log and identifies the following:

A plant transient occurred on the previous shift.

A momentary entry into a Technical Specification Action Statement occurred.

The event was NOT logged.

No TSAIL entry was made.

Which ONE (1) of the following describes the MINIMUM required course of action?

A. The CRSRO makes a TSAIL entry, and then clears the entry because the condition no longer exists. The CRSRO makes the correction to the previous shift's log.

B. The OATC makes a follow-up entry in the current shift's log explaining the situation. A TSAIL entry is NOT required.

C. The CRSRO makes the correction to the previous shift's log. A TSAIL entry is NOT required.

D. The OATC makes the TSAIL entry, and then clears the entry because the condition no longer exists. The CRSRO follows up with an entry in the current log.

Page 69 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 067 A maintenance worker must enter a Vital Area to complete a task that will only take 5 minutes. He has unescorted access but his security badge is not coded to allow access to this area.

An operator is making rounds in the area. The maintenance worker asks the operator to open the CAD door and allow him access.

Which ONE (1) of the following identifies the correct response from the operator?

A. The worker may NOT enter the Vital Area. He must first go to the Security Badging Office and obtain approval for permanent change to include the Vital Area.

B. The operator can escort the worker provided he first calls Security Badging Office to obtain permission to assume visitor escort duties for the worker.

C. The operator is allowed to escort the worker into the area provided that he maintains the worker under his control at all times.

D. The operator can escort the worker provided they first go to the Security Badging Office and obtain an escorted visitor's badge.

Page 70 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 068 Unit 1 is in Mode 6:

Fuel movement is in progress.

A leak has developed which has caused Spent Fuel Pool level to drop.

The Spent Fuel Pool Level Low computer alarm is activated.

The SFP was initially at normal level and radiation level was 7 mr/hr.

After 20 minutes, Pool level has decreased by more than 12 inches and radiation level is now 18 mr/hr.

Which ONE (1) of the following will be the MINIMUM required action(s) to terminate the loss of level in the Spent Fuel Pool per AP- 41, Case 2, Loss of Spent Fuel Pool Level AND AP- 40, Loss of Refueling Cavity Level?

A. Direct the Fuel Handling Crew to move the fuel transfer cart to the reactor side and dispatch operators to close 1KF-122, Fuel Transfer Tube block valve ONLY.

B. Direct the Fuel Handling Crew to move the fuel transfer cart to the reactor side and dispatch operators to close 1KF-122, Fuel Transfer Tube block valve AND place the Weir Gate in position and inflate the seals.

C. Direct the Fuel Handling Crew to move the fuel transfer cart to the spent fuel pool side and dispatch operators to close 1KF-122, Fuel Transfer Tube block valve ONLY.

D. Direct the Fuel Handling Crew to move the fuel transfer cart to the spent fuel pool side and dispatch operators to close 1KF-122, Fuel Transfer Tube block valve AND place the Weir Gate in position and inflate the seals.

Page 71 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 069 While performing a cooldown on Unit 1 from Mode 3 to Mode 5 the following parameters were logged.

Time NC Press NC Temp pzr Liq Space Temp 0200 2200 psig 553°F 650°F 0230 1550 psig 527°F 606°F 0300 1135 psig 505°F 560°F 0330 765 psig 447°F 494°F 0400 400 psig 402°F 440°F Which ONE (1) of the following describes the Technical Specification/Selected License Commitment (TS/SLC) implications of these conditions?

A. NCS AND pzr cooldown rate limits were exceeded; TS/SLC action is required within a maximum of 30 minutes.

B. NCS AND pzr cooldown rate limits were exceeded; TS/SLC action is required within a maximum of 60 minutes.

C. ONLY NCS cooldown rate limits were exceeded; TS/SLC action is required within a maximum of 30 minutes.

D. ONLY NCS cooldown rate limits were exceeded; TS/SLC action is required within a maximum of 60 minutes.

Page 72 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 070 At the end of a shift, there is an outstanding Configuration Control Card (CCC), because a component could not be returned to its AS FOUND position.

Which ONE (1) of the following describes the correct disposition of the CCC?

A. Document the CCC as part of your turnover at shift relief.

B. Return the CCC to the CRSRO to determine whether it should be turned over, or if a procedure change will be required.

C. Return the CCC to the OSM. An R&R will be issued prior to shift turnover.

D. Return the CCC to the WCC SRO. The CCC will be tracked as open until the component can be repositioned to it's AS FOUND position.

Page 73 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 071 An NLO is performing a PT and he identifies that two steps need to be performed "out of sequence" in order to complete the PT.

After deliberation with the supervisor, it is determined that this deviation is necessary. This change will NOT alter the intent of the procedure.

Which ONE (1) of the following statements describes the action(s) required for performing these procedural steps out of sequence?

An explanation of the sequence deviation is documented within the ....

A. Remarks Section of the procedure cover sheet ONLY; and initialed by the NLO and supervisor ONLY, approving the change.

B. Remarks Section of the procedure cover sheet ONLY; and initialed by the NLO, the supervisor, and the OSM approving the change.

C. Procedure body OR the Remarks Section of the procedure cover sheet; and initialed by the NLO and supervisor ONLY, approving the change.

D. Procedure body OR the Remarks Section of the procedure cover sheet; and initialed by the NLO, the supervisor, and the OSM approving the change.

Page 74 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 073 Unit 1 has tripped from 100 % power and the following conditions exist:

Each of the following EMF instruments are in trip 2:

1EMF 71, S/G A Leakage Hi Rad.

1EMF 72, S/G B Leakage Hi Rad.

1EMF 73, S/G C Leakage Hi Rad.

1EMF 74, S/G D Leakage Hi Rad.

1EMF 33, Cond Air Eject Exh Hi Rad.

1EMF 24, 25, 26, 27; S/G A, B, C, 0 Steamline Hi Rad.

Both MD CA Pumps are running.

Steam Generator parameters are as follows:

SGA SG B SGC SGD NR Level 10% 20% 15% 150/0 (increasing) (decreasing) (increasing) (stable)

CA Flow 200 gpm o gpm o gpm 50 gpm Which ONE (1) of the following actions must be taken to minimize the radiation release?

A. Isolate the Steam Supply from the B SG to the TO CA Pump B. Isolate the Steam Supply from the C SG to the TO CA Pump.

C. Increase CA flow to the B SG.

O. Increase CA flow to the C SG.

Page 76 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 074 Which ONE (1) of the following events, followed by a failure of the Reactor Trip Breakers to open, would NOT be considered an Anticipated Transient Without Scram (ATWS)?

A. Trip of 1D NC Pump from 50% power; OR With Channel I pzr Pressure instrument out of service for maintenance, the Channel II pzr Pressure instrument fails LOW.

B. Trip of 1D NC Pump from 400/0 power; OR During a Reactor Startup with Intermediate Range Channels at 10-8 amps, Intermediate Range Channel N36 fails HIGH.

C. Trip of 1D NC Pump from 50% power; OR During a Reactor Startup with Intermediate Range Channels at 10-8 amps, Intermediate Range Channel N36 fails HIGH.

D. Trip of 1D NC Pump from 40% power; OR With Channel I pzr Pressure instrument out of service for maintenance, the Channel II pzr Pressure instrument fails LOW.

Page 77 of 78 Rev Final

U.S.N.R.C. Site-Specific Written Examination McGuire 1/2 Reactor Operator Question 075 Reactor trip and safety injection have occurred on Unit 2.

Off-Site power is lost subsequent to a safety injection actuation.

Equipment failures during performance of E-1, Loss of Reactor or Secondary Coolant, resulted in the following conditions:

CSF Status Trees indicate as follows:

o Subcriticality GREEN o Core Cooling ORANGE o Heat Sink YELLOW o Integrity YELLOW o Containment ORANGE o Inventory YELLOW Which ONE (1) of the following describes the requirement for Critical Safety Function Status Tree Monitoring in accordance with OMP-4.3, Use of Abnormal and Emergency Procedures?

A. Monitor for Information ONLY.

B. Continuous Monitoring Required.

C. Monitor every 10 - 20 minutes using Control Board indications OR OAC SPDS unless a change in plant status occurs.

D. Monitor every 10 - 20 minutes using Control Board indications ONLY unless a change in plant status occurs.

Page 78 of 78 Rev Final

2008 RO License Exam References Table of Contents The following references are provided:

MNS V-I Data Book Curve 7.38

Copy of the Steam Tables

EP/I/A/5000/ECA-I.I Enc. 9

O.p11/AI61 00/22*

UNIT 1 E*NCLOSURE 4.~

.CURVE ., .38 PRESSURIZER 16000 (VOLUME vs.TANK lEVEL)

-rrt-rM-+-+-1-++-J-+.-L-..L-J'_., a.

J ",' r .. ** *.. ** ' .. ,\', ~' ** .,.

~~~-I---+---I---I--~-.I--~""""""'-+--~~-4-~-+--~' TOTAL TAN KVOlUME =13777 GALLONS't 1400.0 '+-~""''~~-I- ....+-....,.~~+-+-+-~+-t~-'+-~'-'+-+--+-!-+--+-';-;'-+-~~-;-~~~~~~~~

m1 :

12000 I I I

' - l I .,

I I

'. I '" '.

,Y ,

" *****~r -,'",. "',""

I I.A~***

~7' 1/

=vr.......J/r"~

~

~.

I I ~.

I~~_IIII ~I 00

~-!- I I I I I L--<'1 ~I I II I ' /. I '/I 1,1 I I I* t

~ I%:

'I I I I I I. . I. .I .' 1.

LJ H-+'~' ~~__ I I I

,.,.... 100 I I '. I L....-*...-. . ....., .. "'. I I I I I I I 9 U')

- - . .-,.- ., " I I, I I I I I I,' '" . . ., . ,. ""'1 LJ

-' I -,.- .......,vI ./ I I I I I I, I I I I .I ,'I 'I 1../,.1 l, ., ....' .l-J .,

~-<~ ~- - ..... . l~

Z I

'II

'[ ""I -~-~

I. ,,-f-f-I--.;.' I I I I II 1,1 I,' III",

8000 - I I . I '-'" -""----f- IJ L_ I I I I I '/ I, I I I 'I I" I I. I' I I 'I I I I 11 -I,~

II I I I I .... J'" I II .I I I I I I I I.

1

3.c.. r -I; - I I I ,I orI 'ir I

I r I' o> 6000 r IT lI I'I II I 'I I : : I I I I I I I 1 11k

-I-I I I I I I I I I I I 1 , l l i H

~~E!jf:+/-1+/-i'~I~Ii'~1+1~'~t~2*~~t~:t~~B:ffE:t!:D:t+/-~:t+PH++:H:f+t=FfIE L4000 .[

fl~-"t-t--' -r-t'--t-t-t---t-t-t-+--t-t-t-t-t-t-~-+-+-+-+-I--+-~~~

2000 p . ..

I I "

7 '

~;/.' 1"'1"'1 '1' ' ' ' 1' J'

1 I l I. I r1 I I l:;t1 ,,-""--<.... ---,,"-,-_... -" -'-c-~~--'- ._-, II I I I I I

. II, I I I , ...

0.t=IIIJ:J-l- 1 I. I I I I I I. I I I I I I I -' I ! I.' 1 ! I I ! ! I '. I J .1... !.**!.~*I****L. L,.L*..J.. l*z.JI. odmJ;LI 50 60 70 8',0' ,90, 'lO,O, o 10 20 . 30 40 lEVEL (PERCENT)

"I;N\'+'1 : ::I~~'"

"'~ ,','

',i

- ,:. . . . I

,:;1:.... *

1'"

3 data, is olso available on the OAC.

MNS LOSS OF EMERGENCY COOLANT RECIRC PAGE NO.

EP/1/A/500*0/ECA-1.1 80 of 104 Enclosure 9 - Page 1 of 1 Rev. 10 UNITl Flow R~quired to Match Decay Heat 600 i\.

\.

M 500 \.

I \.

N \.

\.

I \.

M \..

U \.

\

M 400 ~

\.

S ~

I ~

I r :, \

F L

300 .,,

""".* ~

"-'\.

.0 W ,

R A

T 200 " ~

~,-.

~

'- r--.

E G ~ ....

p ~

M 100 "'" ............

'~ ...... ~

o 3456789 3 456789 3 4 56789 10 100 1000 10000 TIME AFTER REACTOR TRIP (MINUTES)

May 2,2008 To Whom It May Concern Pursuant to 10 CFR 55.40(b)(3), an authorized representative of the facility licensee must approve the examination outline(s) and the proposed examination(s) before they are submitted to the NRC regional office for review and approval. The outline(s) and examinations(s) must be forwarded to the NRC regional office with a cover letter signed by the facility representative.

As the McGuire facility representative, I have reviewed and approved the enclosed examination material for the NRC examination to be administered in May 2008. I have determined that the material is accurate, operationally valid and ready for NRC review.

~~

FredEiKirWr~

McGuire Operations

ML082680261

Text

Navigation menu

Search