Text

Initial Exam 2011-301 Final RO Written Exam
	ML112280599
Person / Time
Site:	McGuire
Issue date:	08/16/2011
From:	; NRC/RGN-II
To:	; Duke Energy Carolinas
References
	Download: ML112280599 (102)
	v • d • e

U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Date:

Facility/Unit: MCGUIRE Region:

I Ill IV Reactor Type:

CE BW GE Start Time:

Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days 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.

Applicants Signature Results Examination Value Points Applicants Score Points Applicants Grade Percent Name:

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

I 1 point)

Given the following conditions on Unit 1:

Unit is operating at 100% RTP Ops Test Group is performing a slave relay test and a procedural error results in the inadvertent closure of 1RN-277B (RB Non Ess Ret Cont Outside Isol)

At 1400, the following NC pumps indications are noted:

NC Pump IA lB IC ID Current Stator 275°F 260°F 266°F 270°F Winding Temp.

Temp. Increase 1.1°F/mm 1.6°F/mm 1.5°F/mm 1.35°F/mm Based on the conditions above, which ONE (1) of the following lists the FIRST NC pump that would have to be manually secured in accordance with AP-08, (Malfunction of NC Pump)?

A.

1A B.

lB C.

1C D.

1D Page 1 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

2 1 point)

Given the following conditions on Unit 1:

An NC pump is to be started for a unit heatup to normal operating temperature and pressure The 1A2 Oil Lift pump has been started in preparation for starting the 1A NCP Oil Lift pressure is 550 PSIG Based on the conditions above, the IA NCP (1) start.

The MINIMUM required #1 Seal differential pressure for starting the NC pump is (2)

PSID.

Which ONE (1) of the following completes the statements above?

A.

1. will

2. 200 B.

1. will

2. 350 C.

1. will not

2. 200 D.

1. will not

2. 350 Page 2 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

3 I point)

Given the following condition on Unit 1:

Unit is in Mode 3 recovering from a reactor trip.

Due to a PZR Pressure control malfunction, the crew had to establish NVAux Spray per Generic Enclosure G-l Enc 3 (Establishing NV Aux Spray) to facilitate repairs.

B/U PZR heaters A and B are energized and pressure is stable During repair activities, I NV-I 3B (NV Supply to A NC Loop) opens inadvertently.

Based on the conditions above, which ONE (1) of the following describes the effect on PZR pressure and what action is required per Gen Enc G-1 Enc 3 to control pressure?

A.

Pressure would INCREASE Manually throttle open 1NC-29C (B NC Loop Spray Control)

B.

Pressure would DECREASE Manually throttle open 1 NC-29C (B NC Loop Spray Control)

C.

Pressure would INCREASE Deenergize PZR heaters as required to control pressure D.

Pressure would DECREASE Energize additional PZR Heaters as required to control pressure Page 3 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

4 (1 point)

Given the following conditions on Unit 1:

The unit is in MODE 4 with the Afl Train of ND in service LTOP key switches for PORV5 are selected to NORM position Annunciator 1AD-9 I Al (1 ND-2A Open and NC Hi Press) has just come in alarm NC WR pressure is indicating 460 PSIG Which ONE (1) of the following describes the redundant indication which would be used to verify that this annunciator is valid?

A.

PRT Level increasing ONLY B.

CF&E sump level increasing ONLY C.

I ND-i B (C HL Suction to ND Isolation) would have auto closed D.

PORV5 NC-32B and NC-34A would be lifting Page 4 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

5 (1 point)

Unit I is shutdown with the following conditions:

IA and lB ND trains are in service providing shutdown cooling in accordance with SO-9 (ND System Parallel Heat Exchanger Operation)

The flow rate on each ND train is currently 1500 GPM 1 ND-34 (IA & 1 B ND Hx Byp Isol) is initially 50% OPEN NC system temperature is being maintained at 170°F The air line for I ND-34 breaks off Which ONE (1) of the following describes the indications that will be observed by the Operators in the Main Control Room over the next 15 minutes?

IA ND Train Total Flowrate lB ND HX Inlet Temperature A.

Increase Increase B.

Increase Decrease C.

Decrease Increase D.

Decrease Decrease PageS of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

6 (1 point)

Given the following conditions on Unit 1:

A Safety Injection has occurred due to a Small-Break LOCA Which ONE (1) of the following identifies the valves or groups of valves that will receive a signal to automatically open on the Safety Injection (S

5) Signal?

A.

1 ND-i4 and 1 ND-29 (A/B ND Heat Exchanger Outlets) AND I Nl-9A and 1 NI-i OB (CCP Pump Isolation to Cold Legs)

B.

1 ND-14 and 1 ND-29 (A/B ND Heat Exchanger Outlets) AND 1 NI-i 73A and I NI-i 78B (Train A/B ND to Loop C and D Cold Legs)

C.

1 NI-i 62A (NI Pump Discharge Common Isolation to Cold Legs) AND 1 NI-9A and I NI-I OB (CCP Pump Isolation to Cold Legs)

D.

1 NI-i 62A (NI Pump Discharge Common Isolation to Cold Legs) AND 1 NI-i 73A and I NI-I 78B (Train A/B ND to Loop C and D Cold Legs)

Page 6 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

7 (1 point)

Given the following conditions on Unit 1:

A LOCA has occurred inside Containment E-1 (Loss or Reactor or Secondary Coolant) has been implemented NC system pressure is 400 PSIG One of the Cold Leg Accumulators (CIA) injects N2 into the NC system prior to the crew reaching the step in E-1 which directs isolating the CLA5 Which ONE (1) of the following would result in the highest probability of N2 injection into the NC system?

Accumulator pressure was initially (1) than the Tech Spec limit and level was initially (2) than the Tech Spec limit.

A.

1. higher

2. higher B.

1. lower

2. higher C.

1. higher

2. lower D.

1. lower

2. lower Page 7 of 75

McGuire Nuclear Station 2011 MNS R0 NRC Examination Question:

8 1 point)

Given the following conditions on Unit 1:

The unit is operating at 100% RTP The following annunciators are received:

1AD-6 D-9 (PRT HI PRESS) 1AD-6 E-9 (PRT ABNORMAL LEVEL)

The following OAC Alarms are received:

Ui PZR RELIEF TANK LEVEL HI-HI Ui PZR RELIEF TANK PRESS HI PRT pressure is 9 PSIG and RISING SLOWLY PRT level is 95% and RISING SLOWLY The PRT rupture disc is designed to discharge to Containment when PRT pressure risestoaMAXiMUMof (1)

To prevent PRT rupture disc operation the operating crew must (2)

Which ONE (1) of the following completes the statements above?

A.

1. 85PSIG

2. drain the PRT to the NCDT B.

1. 100 PSIG

2. drain the PRTto the NCDT C.

1. 85PSIG

2. have Chemistry vent the PRT to the Waste Gas system D.

1. 100 PSIG

2. have Chemistry vent the PRT to the Waste Gas system Page 8 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

9 1 point)

Unit 1 was operating at 100%. Given the following conditions and sequence of events:

A plant transient results in a cooldown of the NC system causes the Backup Heaters to Energize and the C PZR heaters to be full ON Pressurizer Pressure Channel I fails offscale high Subsequently, the following events occur:

Pressurizer Pressure Channel 2 fails offscale low The following annunciators are received simultaneously with the second pressure channel failure:

o 1AD2 I E8 (DCS Trouble) o 1AD-2 I F8 (DCS Alternate Action)

The OATC notifies the rest of the crew that there is an Alternate Action on Pressurizer Pressure Select 1 and Select 2 Assuming no operator actions, what effect does this combination of channel failures have on the Pressurizer Pressure Control system?

A.

The Pressurizer Pressure Master swaps to manual.

Backup heaters deenergize.

B.

The Pressurizer Pressure Master swaps to manual.

Backup heaters remain energized.

C.

The Pressurizer Pressure Master remains in automatic.

Pressure is controlled based on the average of the 2 unaffected channels.

D.

The Pressurizer Pressure Master remains in automatic.

Pressure is controlled based on the highest of the 2 unaffected channels.

Page 9 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

10 (1 point)

If the indication for a Power Range Nuclear instrument fails low, it could be caused by alossof (1)

If either Instrument OR Control Power is lost to Power Range N-42 at 100% RTP, the crew will implement (2)

Which ONE (1) of the following completes the statements above?

A.

1. Instrument Power 2.

E-O (Reactor Trip or Safety Injection)

B.

1. Instrument Power

2. AP-16 (Malfunction of Nuclear Instrumentation)

C.

1. Control Power

2. E-0 (Reactor Trip or Safety Injection)

D.

1. Control Power

2. AP-16 (Malfunction of Nuclear Instrumentation)

Page 10 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

11 1 point)

Given the following on Unit 1:

Unit I is operating at 100% RTP The OTAT trip setpoint for N-41 will decrease if (1)

The OTAT reactor trip is design to protect against exceeding (2)

Which ONE (1) of the following completes the statements above?

A.

1. NC system pressure increases

2. DNB limits B.

1. NC system pressure increases

2. fuel heat generation rate limits C.

1. power is lost to N-41 lower detector

2. DNB limits D.

1. power is lost to N-41 lower detector

2. fuel heat generation rate limits Page 11 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

12 (1 point)

Given the following conditions on Unit 2:

The unit is at 100% RTP Pressurizer Pressure channel II is in test with all bistables in the tripped position for IAE testing 2EKVA develops a fault and is now de-energized Which ONE (1) of the following describes the effect on the plant due to the fault on 2EKVA?

A.

The reactor will automatically trip.

SI signal equipment on both trains will automatically start due to redundant power supplies.

B.

The reactor will automatically trip.

SI signal equipment on A train ONLY will not automatically start due to the loss of power to the SSPS output cabinet.

C.

The reactor will not automatically trip If an SI signal is received, equipment on both trains will automatically start due to redundant power supplies.

D.

The reactor will not automatically trip.

If an SI signal is received, equipment on A train ONLY will not automatically start due to the loss of power to the SSPS output cabinet.

Page 12 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

13 (1 point)

The normal logic for a High Containment pressure Safety Injection actuation is (1) channels.

If one of the Containment pressure channels that provides input to the Safety Injection logic is placed in BYPASS, then the logic becomes (2) channels.

Which ONE (1) of the following completes the statements above?

A.

1. 2of3

2. lof2 B.

1. 2of4

2. lof3 C.

1. 2of3

2. 2of2 D.

1. 2of4

2. 2of3 Page 13 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

14 (1 point)

Given the following conditions on Unit 1:

Unit was initially operating at 100% RTP

Train B components are initially in service

A LOCA occurs inside Containment

Containment pressure peaks at 3.2 PSIG and stabilizes at 1.5 PSIG Based on these conditions Lower Containment Ventilation Cooling is Which ONE (1) of the following completes the statement above?

A.

isolated B.

being supplied by the RV system ONLY C.

being supplied by the RN system ONLY D.

being supplied the RV AND RN systems Page 14 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

15 (1 point)

Given the following plant conditions:

Unit I was operating at 100% RTP Steam line Break INS IDE Containment occurs NS System CPCS Train A Inhibit status light, located on Status Indication Panel lSl-12, is (LIT)

Containment Pressure is 8 PSIG The Crew is performing FR Z.1 (Response to High Cont Press)

1) What effect would the condition described above have on the operation of the NS System?

2) What is the basis for the minimum temperature of the FWST as it relates to a LOCA Containment Spray actuation?

Which ONE (1) of the following answers the questions above?

A.

1. There would be no Train A Containment Spray Flow

2. To prevent exceeding the maximum external pressure load on the containment shell due to an internal vacuum caused by overcooling of the Post-Accident Containment atmosphere.

B.

1. There would be no Train A Containment Spray Flow

2. To prevent an excessive reduction in containment pressure, which could decrease the rate at which steam can be vented out the break and increases peak clad temperature.

C.

1. ONLY one of the two Train A NS Spray Headers will have flow

2. To prevent exceeding the maximum external pressure load on the containment shell due to an internal vacuum caused by overcooling of the Post-Accident Containment atmosphere.

D.

1. ONLY one of the two Train A NS Spray Headers will have flow

2. To prevent an excessive reduction in containment pressure, which could decrease the rate at which steam can be vented out the break and increases peak clad temperature.

Page 15 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

16 (1 point)

Given the following events and conditions on Unit 1:

Unit is holding at 30% RTP Control rods are in manual Turbine control is MW OUT One MSR 2nd stage relief valve fails open

1) What trends will occur for Tavg and reactor power 10 minutes after the leak starts?

2) Per AP-Ol (Steam Leak) what will be required to isolate the steam leak?

A.

1. Tavg is HIGHER

- reactor power is LOWER

2. Reactor Trip and Turbine Trip ONLY B.

1. Tavg is HIGHER

- reactor power is LOWER

2. Reactor Trip and closure of the MSIVs C.

1. Tavg is LOWER reactor power is HIGHER

2. Reactor Trip and Turbine Trip ONLY D.

1. Tavg is LOWER reactor power is HIGHER

2. Reactor Trip and closure of the MSIVs Page 16 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

17 (1 point)

Given the following conditions on Unit 1:

A LOCA has occurred inside Containment Containment pressure is 3.4 PSIG The crew is preparing to initiate a cooldown per ES 1.2 (Post LOCA Cooldown and Depressuration)

Which ONE (1) of the following must occur to allow reopening the MSIVs for the given conditions?

A.

Reset the Main Steam Isolation signal ONLY.

B.

Reset the Phase BAND Main Steam Isolation signals ONLY.

C.

Containment pressure must be reduced below 3 PSIG AND reset the Main Steam Isolation signal ONLY.

D.

Containment pressure must be reduced below 3 PSIG AND reset BOTH the Main Steam Isolation signal and Phase B Isolation signal.

Page 17 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

18 1 point)

Which ONE (1) of the following lists automatic actions that occur as a result of a P-14 (Feedwater lsoIaton) signal?

A.

Both Feedwater Pumps trip CF to CA Nozzle Isolations close B.

Both Feedwater Pumps trip Main Steam Isolation Valves close C.

Both Feedwater Pumps speed goes to 2800 RPM CF to CA Nozzle Isolations close D.

Both Feedwater Pumps speed goes to 2800 RPM Main Steam Isolation Valves close Page 18 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

19 1 point)

Given the following on Unit 1:

A reactor trip from 100% power has occurred Bus IETA locked out The TD CA Pump tripped on overspeed upon starting CA is being supplied to (1) at a maximum flow rate of (2)

?

Which ONE of the following completes the statement above?

A.

1.AandBSGs

2. 450 GPM B.

1. CandDSGs

2. 450 GPM C.

1.AandBSGs

2. 900 GPM D.

1. CandDSGs

2. 900 GPM Page 19 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

20 1 point)

Given the following conditions on Unit 1:

Bus IEVDA has lost power The breaker for IA NV pump Which ONE (1) of the following completes the statement above?

A.

automatically trips open but can be closed locally after manually charging the springs B.

can only be operated locally but the springs must be manually charged prior to each opening and closing operation C.

can only be operated locally but only closing operations require manually charging the springs D.

can be opened one time from the control room but all further operations must be performed locally Page 20 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

21 (1 point)

Given the following plant conditions:

Both Units are operating at 100% RTP Battery 1DP is aligned for equalizing charge The AC in put breaker for Charger I DP has tripped open Based on the conditions above, which ONE (1) of the following describes the current source(s) of power for Bus 1DP?

A.

Charger 1DS and Battery 1DP ONLY B.

Charger2DS and Battery 2DP ONLY C.

Charger 2DP and Battery 2DP ONLY D.

Charger 2DS, Charger 2DP, AND Battery 2DP Page 21 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

22 (1 point)

Given the following conditions on Unit 1:

. 125 VDC Control Power forthe lB DG has been lost Which ONE (1) of the following lists equipment associated wfth the lB DG that will no longer have power?

A.

DG Sump Pump AND Starting Air Solenoids B.

Electronic Governor AND Starting Air Solenoids C.

DG Sump Pump AND Diesel Building dampers D.

Electronic Governor AND Diesel Building dampers Page 22 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Given the following conditions on Unit 1:

. The 1A DG was started in MANUAL MODE at time 14:04 for surveillance The fol lowing trend of DG Crankcase Vacuum is observed:

Question:

23 (1 point)

DG 1A Crankcase Vacuum TIME 14:00 14:15 14:30 14:45 0

0 0,5 E

1 C) 1.5 4.)

c 2

4-2.5 Based on the trend above, the EARLIEST time that 1A DG will trip on Low Crankcase Vacuum is...

A.

14:10 B.

14:15 C.

14:20 D.

14:25 Page 23 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

24 (1 point)

Given the following conditions on Unit 1:

A MANUAL MODE start of the I B DG was performed for surveillance testing The DG is currently loaded to 4000 KW

1) Which ONE (1) of the following is a heat load that is currently being cooled by the DG Cooling Water (KD) System?

2) Which ONE (1) of the following is the MIMIMUM Surge Tank level that was required to perform the MANUAL MODE start?

A.

1. VG After Coolers

2. 11.5 inches B.

1. Air Intake System Intercooler

2. 25 inches C.

1. Air Intake System Intercooler

2. 11.5 inches D.

1. VGAfterCoolers

2. 25 inches Page 24 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

25 (1 point)

With Unit 1 at 100% RTP, a SIG tube leaks develops on the I B Steam Generator.

The following radiation monitors start to slowly increase:

1EMF33 (Unit 1 Condenser Air Ejector Monitor)

IEMF34(L) (Unit 1 Steam Generator Sample (Low Range))

IEMF34(H) (Unit 1 Steam Generator Sample (High Range))

IEMF72 (Unit 1 Steam Line lB Monitor)

Subsequently, both 1EMF33 and IEMF34(L) reach their TRIP 2 setpoints.

Assuming NO action is taken by the crew, which ONE (1) of the following identifies the monitor or monitors that are expected to DECREASE over the next several minutes?

A.

IEMF33 ONLY B.

I EMF34(L) ONLY C.

1 EMF34(L) and IEMF 34(H) ONLY D.

1EMF33, 1EMF34(L) and 1EMF34(H)

Page 25 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

26 (1 point)

Given the following conditions on Unit 2:

A loss of power had occurred on 2ETA and 2ETB The 2A and 2B DC started and aN loads sequenced normally Based on the conditions above, which ONE (1) of the following loads is currently being supplied by the Nuclear Service Water (RN) system?

A.

Safety Injection Pump motor cooler B.

Containment Spray heat exchanger C.

Auxiliary Feedwater Pump motor cooler D.

Residual Heat Removal Pump motor cooler Page 26 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

27 (1 point)

Given the following initial conditions on Unit 1:

A LOCA has occurred inside Containment NC pressure is 1700 PSIG With Containment pressure at 2.5 PSIG and increasing rapidly, the crew MANUALLY initiates Containment Spray.

Assuming all automatic and manual actions have functioned normally, which ONE (1) of the following lists the ESF actuation(s) that has/have occurred?

A.

PhaseAONLY B.

PhaseAand PhaseBONLY C.

Phase A and Containment Ventilation Isolation ONLY D.

Phase A, Phase B, and Containment Ventilation Isolation Page 27 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

28 (1 point)

In accordance with FR-Z.1 (Response to High Containment Pressure), to place ND Spray in service Containment pressure must be greater than a MINIMUM of (1)

AND the time since the Reactor Trip must be greater than a MINIMUM of (2)

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

A.

1. 3PSIG

2. 50 minutes B.

1. 1OPSIG

2. 50 minutes C.

1. 3PSIG

2. 60 minutes D.

1. 1OPSIG

2. 60 minutes Page 28 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

29 (1 point)

Given the following:

Unit 2 was initially operating at 100% RTP

Due to Main condenser cooling water issues, the Main Turbine controls are placed in manual and load reduced by 400 MW over a 5 minute period Which ONE (1) of the following describes the INITIAL effect on the pressurizer and the inherent response to the transient described above?

A.

PZR outsurge PZR Backup heaters would energize to limit the pressure decrease.

B.

PZR outsurge Some of the liquid in the PZR would flash to steam which will limit the pressure decrease.

C.

PZR insurge Some of the steam volume in the PZR would condense limiting the pressure increase.

D.

PZR insurge PZR Backup heaters would de-energize to limit the pressure increase.

Page 29 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

30 (1 point)

Given the following conditions on Unit 1:

A Loss of Offsite Power has occurred

1ETA and 1ETB are energized from their respective DGs Based on the conditions above, power can be restored to Pressurizer Heater Group(s)

(1)

If control is transferred to the Auxiliary Shutdown Panel (ASP), the Pressurizer Heaters operated from the ASP would trip on a (2)

Which ONE (1) of the following completes the statements above?

A.

1.A&BONLY

2. Safety Injection B.

1.A&BONLY

2. Pressurizer Low-Low Level C.

1.A,B,&D

2. Safety Injection D.

1.A,B,&D

2. Pressurizer Low-Low Level Page 30 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

31 (1 point)

Given the following indications:

Unit 1 is operating at 100% RTP An electrical fault occurred in the DRPI circuitry located in the CIR The fault has affected the DRPI programming causing Rod H-8 to indicate 200 steps with the remainder of Control Bank D at 216 steps The grayu code from the DRPI Data Panels has NOT been affected ACTUAL ROD position for Rod H-8 is 216 steps The RPI (1)

Failure annunciator would be in LIT.

The OAC Rods program (2) indicate the correct rod position for Rod H-8.

Based on the conditions described, which ONE (1) of the following completes the statements above?

A.

1. Non-Urgent

2. will B.

1.Non-Urgent

2. will not C.

1.Urgent

2. will D.

1.Urgent

2. will not Page 31 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

32 (1 point)

Given the following conditions on Unit 1:

The unit is operating at 100% RTP Rod Control is in AUTOMATIC Subsequently, rod control is placed in MANUAL due to a DCS Alternate Action.

1) Which ONE (1) of the following describes the MINIMUM number of Loop Tave detector failures required to cause a DCS Alternate Action on the Tavg Reactor Temperature Control unit?

2)

In accordance with OPIIIAI61 00/003 (Controlling Procedure for Unit Operation),

after DCS is repaired, what is the MAXIMUM deviation between Tavg and Tref prior to shifting CRD Select from MANUAL to AUTO?

Which ONE (1) of the following completes the statements above?

A.

1.2

2. +/-1°F B.

1.2

2. +/-3°F C.

1.3

2. +/-1°F D.

1.3

2. +/-3°F Page 32 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

33 1 point)

Given the following on Unit 1:

Unit is Mode 6

VP is in service and refueling is in progress

The CIR receives the following alarms and indications o

VP Supply Damper CLOSED o

VP Exhaust Damper CLOSED o

VP Supply Fans OFF o

VP Exhaust Fans OFF

The Containment evacuation alarm is reported to be sounding A Trip 2 alarm on which ONE (1) of the following would have caused ALL of the alarms and indications described above?

A.

1 EMF-35(L) (Unit Vent Particulate)

B.

I EMF-36(L) (Unit Vent Gas)

C.

1 EMF-38(L) (Containment Particulate)

D.

I EMF-39(L) (Containment Gas)

Page 33 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

34 (1 point)

Given the following conditions on Unit 2:

The unit is operating at 100% RTP

The SPENT FUEL POOL LEVEL LO alarm is received on the Unit 2 OAC 1)

Which ONE (1) of the following is the FIRST EMF that will alarm to confirm a leak on the Spent Fuel Pool Cooling system?

2)

Which ONE (1) of the following AUTOMATIC actions associated wfth Fuel Handling Building Ventilation (VF) system is caused by a Spent Fuel Pool radiation monitor?

A.

1. 2EMF-42 (Unit2FUEL BUILDING VENTILATION)

2. The VF Supply and Exhaust Fans will stop on a 2EMF-4 Trip 2.

B.

1. 2EMF-4 (SPENT FUEL BLDG REFUEL BRDG)

2. TheVF Supplyand Exhaust Fanswillstop on a2EMF-42Trip2.

C.

1. 2EMF-42 (Unit 2 FUEL BUILDING VENTILATION)

2. The Exhaust Filter Bypass Damper (D-5) will close on a 2EMF-4 Trip 2.

D.

1. 2EMF-4 (SPENT FUEL BLDG REFUEL BRDG)

2. The Exhaust Filter Bypass Damper (D-5) will close on a 2EMF-42 Trip 2.

Page 34 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

35 (1 point)

Which ONE (1) of the following combinations describes the MINIMUM ND requirements and additional License requirements for Fuel Movement?

ND Additional Requirements A.

One Loop OPERABLE and Reactor subcritical for a minimum of in operation 70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months B.

Two Loops OPERABLE and A minimum of one door in each airlock ONE in operation closed C.

One Loop OPERABLE and Equipment Hatch held in place by a in operation minimum of four bolts D.

Two Loops OPERABLE and One OPERABLE VCIYC train ONE in operation Page 35 of 75

McGuire Nuclear Station

=

2011 MNS RO NRC Examination Question:

36 (1 point)

Given the following conditions on Unit 2:

The unit was initially operating at 100% RTP A SGTR occurs on 2C SG The crew initiated a manual Reactor Trip and Safety Injection The 2C SG MSIV would NOT close during isolation E-3 (Steam Generator Tube Rupture) has been implemented The crew is preparing to cooldown to the target temperature of 520°F Which ONE (1) of the following describes how the plant cooldown to the target temperature will be accomplished?

A.

Steam Dumps B.

SM PORV5 from all intact S/Gs C.

SM PORVS from 2A and 2D SGs ONLY D.

Start the TDCA pump and align the steam line drains Page 36 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

37 (1 point)

Given the following related to Waste Gas (WG) Decay Tank A:

H2 concentration is 4.4%

Per station Selected License Commitment (SLC) 16.11.19 (Explosive Gas Mixture):

WG Decay tank 02 concentration must be maintained less than a MAXIMUM of (1) until H2 concentration is less than a MAXIMUM of (2)

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

A.

1.2%

2. 2%

B.

1.4%

2. 4%

C.

1.2%

2. 4%

D.

1.4%

2. 2%

Page 37 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

38 (1 point)

Given the following plant conditions:

A leak developed in the VS system VI pressure dropped to 80 PSIG before the leak was isolated VI pressure has returned to 100 PSIG Assuming NO operator action, 1VI-820 (VI Supply to VS Control) auto-closed when VI pressure reached a MINIMUM of (1)

AND currently is (2)

?

Which ONE (1) of the following statements completes the statement above?

A.

1. 85PSIG

2. open B.

1. 85PSIG

2. closed C.

1. 9OPSIG

2. open D.

1. 9OPSIG

2. closed Page 38 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

39 1 point)

Given the following conditions on Unit 1:

A Reactor Trip has occurred

E-O (Reactor Trip or Safety Injection) has been implemented The crew will FIRST determine if the turbine has automatically tripped by checking all (1) valves closed.

In accordance with E-O, if the turbine has not automatically tripped and can NOT be manually tripped, the crew will NEXT attempt to (2)

Which ONE (1) of the following completes the statements above?

A.

1. throttle

2. close the MSIVs AND MSIV bypasses B.

1. governor

2. place the turbine in MANUAL AND close the governor valves C.

1. throttle

2. place the turbine in MANUAL AND close the governor valves D.

1. governor

2. close the MSIV5 AND MSIV bypasses Page 39 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

40 (1 point)

Given the following conditions on Unit 1:

The unit is in MODE 3 with a plant cooldown in progress The crew has entered AP-1 1 (Pressurizer Pressure Anomalies) due to Pressurizer pressure decreasing very slowly Pressurizer pressure is 1185 PSIG PRT pressure is 5 PSIG Given the above conditions, determine which ONE (1) of the following would indicate a leaking PORV and the state of the fluid in the PORV discharge?

REFERENCE PROVIDED PORV Discharge Temperature State of the Effluent A.

280-300°F Wet Vapor B.

300-320°F Wet Vapor C.

280-300°F Superheated Steam D.

300-320°F Superheated Steam Page 40 of 75

Question:

41 (1 point)

McGuire Nuclear Station 2011 MNS RO NRC Examination Given the following conditions on Unit 1:

The unit has experienced a Reactor Trip and Safety Injection due to a Small-Break LOCA The crew has just completed the actions of E-0 (Reactor Trip or Safety Injection)

NV pump flow to the NC system Cold Legs is 390 GPM NC system pressure is 1300 PSIG and stable SG pressures are 1092 PSIG and stable NC system subcooling on the ICCM is 22°F and stable Which ONE (1) of the following describes plant conditions upon transition to E-1 (Loss of Reactor or Secondary Coolant)?

SGs NC Pumps Required for Running?

Heat Removal?

YES YES YES NO NO YES NO NO A.

B.

C.

D.

Page 41 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

42 (1 point)

Given the following conditions on Unit 2:

The unit has experienced a Large-Break LOCA The crew has implemented ECA-1.1 (Loss of Emergency Coolant Recirculation)

NCS subcooling is 0 degrees FWSTlevelis3%

NCPs are not running There is no indication of natural circulation The core is currently being cooled by steam entering the (1) of SIG U-tubes where the steam condenses and re-enters the core area via the SIG (2)

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

iI A.

hot leg cold leg B.

hot leg hot leg C.

cold leg hot leg D.

cold leg cold leg Page 42 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

43 (1 point)

Given the following initial conditions on Unit 2:

The unit is in MODE 3 with Shutdown Banks withdrawn

2B, 2C, and 2D NC pumps are in service

Bus 2TA is de-energized with its supply breaker racked out for maintenance Subsequently, the 2B NC pump 6.9KV NC pump feeder breaker trips.

Based on the conditions above, the 2C and 2D NC pumps SAFETY BREAKERS indicate (1)

The Unit 2 Reactor Trip breakers (2)

Which ONE (1) of the following completes the statements above?

A.

1. CLOSED

2. are TRIPPED B.

1. CLOSED

2. remain CLOSED C.

1. OPEN

2. are TRIPPED D.

1. OPEN

2. remain CLOSED Page 43 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

44 (1 point)

Given the following events and conditions:

Unit 1 was operating at 96% power INV-241 (Seal Water Injection Flow) failed shut The operators entered AP-12 (Loss of Charging)

Excess LID has been placed in service With I NV-26B (UI Excess LID Hx Outlet Cntrl) fully open maximum indicated flow would be (1) 1NV-94AC (NC Pump Seal Ret Cont Inside Isol) can be controlled from the CIR AND the (2)

Which ONE (1) of the following completes the statements above?

A.

1. 26GPM

2. SSF B.

1. 26GPM

2. AuxSID Panel C.

1. 35GPM

2. SSF D.

1. 35GPM

2. AuxSID Panel Page 44 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

45 (1 point)

Given the following initial conditions:

Unit 1 is in MODE 5 and drained to mid-loop for NC Pump seal repair ND Train 1A is in service ND system flow rate is 3200 GPM NC System level is +10 inches Current (amps) indication for the lAND pump begins to fluctuate ThelANDpumpis (1)

In accordance with AP-19 (Loss of ND or ND System Leakage) NC system subcooling is determined by monitoring (2)

Which ONE (1) of the following completes the statements above?

A.

1. cavitating

2. Core ExitT/Cs B.

1. cavitating

2. Wide Range T-hot C.

1. operating at a runout condition

2. Core ExitT/Cs D.

1. operating at a run out condition

2. Wide Range T-hot Page 45 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

46 (1 point)

Unit 1 was operating at 100% RTP when a pipe break occurred on the 1D SIG steam header.

The following sequence of events occurred:

The ID SIG is isolated Pzr level dropped to 0% and was restored to 20%

NC system pressure is 1900 PSIG The Safety Injection and Sequencers have been reset ES-I.1 (SI Termination) has been implemented Which ONE (1) of the following describes the correct MCB panel actions to re-energize the PZR Back-up Heater Bank B?

A.

Select MANUAL on the heater mode switch on IMC-5 (vertical section);

Select CLOSED on the heater breaker switch on 1MC-I0 (horizontal section);

Select ON for the heater control switch on I MC-5 (vertical section).

B.

Select MANUAL on the heater mode switch on 1MC-10 (horizontal section);

Select ON for the heater control switch on 1MC-10 (horizontal section).

C.

Select MANUAL on the heater mode switch on 1MC-5 (vertical section);

Select ON for the heater control switch on 1 MC-5 (vertical section).

D.

Select MANUAL on the heater mode switch on 1MC-10 (horizontal section);

Select CLOSED on the heater breaker switch on 1MC-5 (vertical section);

Select ON for the heater control switch on I MC-1 0 (horizontal section).

Page 46 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

47 1 point)

Given the following conditions on Unit 1:

The crew determines that a valid automatic Reactor Trip has failed to occur A manual Reactor Trip is attempted unsuccessfully FR-S.1 (Response to Nuclear Generation/ATWS) is implemented The crew manually trips the Main Turbine NC system pressure begins to increase rapidly In accordance with Tech Spec 2.1.2 (RCS Pressure Safety Limit):

NC system pressure shall be maintained less than or equal to a MAXIMUM pressure of (1)

PSIG.

In accordance with Tech Spec 2.1.2 Basis, the (2) are credited for preventing the RCS from exceeding the Design Pressure Safety Limit.

Which ONE (1) of the following completes the statements above?

A.

1. 2500

2. Main Steam Safety Valves B.

1. 2735

2. Main Steam Safety Valves C.

1. 2500

2. Condenser Steam Dumps D.

1. 2735

2. Condenser Steam Dumps Page 47 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

48 (1 point)

Given the following conditions on Unit 2:

A SGTR has occurred on the 2D SG A Steam Line break occurred on the 2B SG Containment pressure peaked at 3.1 PSIG and is now 0.9 PSIG and STABLE In accordance with E-3 (Steam Generator Tube Rupture):

2D SG NR level shall be maintained greater than a MINIMUM of (1)

During steps to depressurize the NC system, if it is determined that Pressurizer Sprays are ineffective at reducing NC system pressure, the crew shall FIRST attempt to depressurize the NC system using (2)

Which ONE (1) of the following completes the statements above?

A.

1. 11%

2. Auxiliary Spray B.

1. 32%

2. Auxiliary Spray C.

1. 11%

2. one PZR PORV D.

1. 32%

2. 0nePZRPORV Page 48 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

49 (1 point)

Given the following:

Unit 2 is in Mode 3 performing a plant cooldown NC System pressure is 1300 PSIG All S/G pressures are 800 PSIG Low Pressure SI and Low Pressure Steamline Isolation have been blocked Subsequently:

A steamline rupture occurs inside containment from the 2A S/G Containment pressure peaked at 1.5 PSIG All MSIVs indicate closed Based on the conditions above, the Main Steam Isolation Valves closed because SG pressure decreased a MINIMUM of 100 PSIG in (1)

In addition to the closure of the MSIVs, the (2) will also receive a signal to close.

Which ONE (1) of the following completes the statements above?

A.

1.

1 second

2. MSIV bypass valves ONLY B.

1.

1 second

2. MSIV bypass valves AND the S/G PORVs C.

1. 2seconds

2. MSlVbypass valves ONLY D.

1. 2seconds

2. MSIV bypass valves AND the S/G PORVs Page 49 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

50 (1 point)

Given the following conditions on Unit 1:

A unit shutdown is in progress 0200 both Main Feedwater pumps trip Subsequently, the following conditions are observed:

TIME CONDITION 0200 0205 0210 0215 NCS Temp (°F) 557 558 558 559 NCSPress(PSIG) 1965 1960 1976 1991 NRSGA(%)

19 18 19 19 NRSGB(%)

20 18 17 16 NRSGC(%)

20 19 18 16 NRSGD(%)

18 16 18 19 Based on the conditions above:

The EARLIEST time that the MD CA pumps will be running is (1)

The EARLIEST time that the TD CA pump will be running is (2)

Which ONE (1) of the following completes the statements above?

A.

1. 0200

2. 0205 B.

1. 0205

2. 0205 C.

1. 0200

2. 0215 D.

1. 0205

2. 0215 Page 50 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

51 (1 point)

Given the following initial conditions:

Unit 1 and 2 have been in a Loss of Offsite Power condition for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months BOTH Diesel VI compressors are unavailable ECA0.0 (Loss of All AC Power) was implemented on Unit 1 and the crew has transitioned to ECA-0.1 (Loss of All AC Power Recovery Without Sit Required)

Current conditions:

NC Th 0

ts are STABLE S1G pressures are STABLE at 775 PSIG S1G levels are decreasing and approaching 11% NR NC T-colds are 480°F VI header pressure is 0 PSIG Based on the indication above, which ONE (1) of the following describes the current state of Natural Circulation flow and the actions that must be taken per ECA-0.1?

REFERENCE PROVIDED A.

Natural Circulation flow has been established.

Increase CA flow using flow controllers in the control room.

B.

Natural Circulation flow has been established.

Increase CA flow by notifying NLO to throttle CA valves locally.

C.

Natural Circulation flow has NOT been established.

Increase dumping steam using SM PORV controller on main control board AND increase CA flow using flow controllers in the control room.

D.

Natural Circulation flow has NOT been established.

Dispatch an operator to locally increase flow from the SM PORV AND increase CA flow by notifying NLO to throttle CA valves locally.

Page 51 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

52 1 point)

Given the following initial conditions on Unit 1:

The unit is in MODE 3 preparing for a reactor startup

At 0400 on February 1, 1 B NV pump is tagged for maintenance Subsequently:

At 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months on February 1, a fault occurs on Main Transformer IA Bus ITA automatically transfers to Auxiliary Transformer IATB Based on the conditions above, which ONE (1) of the following describes the required actions in accordance with Tech Spec 3.8.1 (AC Sources

- Operating)?

REFERENCE PROVIDED A.

Declare the IA NV pump INOPERABLE by 0400 on February 2 ONLY.

B.

Declare the IA NV pump INOPERABLE by 0800 on February 2 ONLY.

C Restore Off-Site Power via the 1A Main Transformer by 0800 on February 4 AND Declare the 1A NV pump INOPERABLE by 0400 on February 2.

D.

Restore Off-Site Power via the 1A Main Transformer by 0800 on February 4 AND Declare the 1A NV pump INOPERABLE by 0800 on February 2.

Page 52 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

53 1 point)

Given the following initial conditions on Unit 1:

The unit was operating at 100% RTP A Loss of All AC Power occurs ECA-0.0 (Loss of All AC Power) has been implemented Subsequently, the following events occur:

Both DG5 have been started Power has been restored to 1ETA and IETB In accordance with ECA-0.0, the vital battery chargers must be re-started within a MAXIMUM0f (1) minutestoprevent (2)

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

A.

1. 40 minutes

2. failure of components supplied by the battery B.

1. 60 minutes

2. failure of components supplied by the battery C.

1. 40 minutes

2. complete loss of the vital battery D.

1. 60 minutes

2. complete loss of the vital battery Page 53 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

54 1 point)

Given the following indications on Unit 1:

The Unit is operating at 100% RTP IAD-8 D-l (Sump A Groundwater Drainage Hi Hi LVI) just came in alarm The crew is attempting to determine the source of the input to the sump An NEC sent to investigate reports that the sump is overflowing Which ONE (1) of the following describes the source of the flooding?

A.

1 B RN strainer basket shaft seal failure B.

2A RN Pump Suction piping weld failure C.

RF piping break in the Unit 2 CA pump Room D.

IA RN strainer automatic backwash valve has failed open Page 54 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

55 (1 point)

Given the following conditions on Unit 1:

VI pressure has been lost due to a pipe rupture AP-22 (Loss of VI) has been implemented Which ONE (1) of the following describes the RN alignment directed by AP-22 and the reason for those actions?

A.

The B Train is aligned to the SNSWP To prevent pump run out due to high flow conditions B.

The B Train is aligned to the SNSWP To prevent cavitation due having all 4 RN pumps suction aligned to LLI C.

The A Train is aligned to the SNSWP To prevent pump runout due to high flow conditions D.

The A Train is aligned to the SNSWP To prevent cavitation due having all 4 RN pumps suction aligned to LLI Page 55 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

56 (1 point)

Given the following condition associated with Unit 1:

S/Gs IA & lB are faulted and indicating <5% WR Level SIGs 1C & 1D are indicating 30% NR Level All CA is unavailable Containment Pressure is 3.5 PSIG E-0 (Reactor Trip or Safety Injection) has been completed Based on the indications described above, which ONE (1) of the following describes the NEXT procedure to be implemented and action(s) required?

A.

Go to EP-E2 (Faulted S/G Isolation)

Isolate C & D S/Gs B.

Go to FR-H.I (Response to Loss of Secondary Heat Sink)

Commence NCS feed and bleed C.

Go to FR-H.I (Response to Loss of Secondary Heat Sink)

Restore feed water flow to C & D S/Gs D.

Go to EP-E2 (Faulted S/G Isolation)

Close all MSIVs and MSIV bypasses Page 56 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

57 (1 point)

Gven the following conditions on Unit 1:

The unit is operating at 70% RTP

Rod control is in AUTOMATIC

Annunciator IAD-2 I D9 (RPI AT BOTTOM ROD DROP) alarms

DRPI indicates that rod M14 (adjacent to Power Range N-44) has dropped The dropped rod will be confirmed by the following indications:

Control rods will move OUT if Tave decrease below Tf by a MINUMUM of (1)

Over the next several hours the overall core QPTR will (2)

Which ONE (1) of the following completes the statements above?

A.

1. 1°F

2. decrease B.

1. 1.5°F

2. decrease C.

1. 1°F

2. increase D.

1. 1.5°F

2. increase Page 57 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

58 (1 point)

If an Emergency Boration flowpath via I NV-265B (Boric Acid to NV Pumps) can NOT be established:

AP-38 directs the Operators to (1)

FR-S.1 directs (2)

Which ONE (1) of the following completes the statements above?

A.

1. OPEN I NV-269 (BA to Charging Pumps Block) ONLY

2. manually aligning the NV pumps suction to the FWST B.

I. OPEN I NV-269 (BA to Charging Pumps Block) AND INV-267A (Boric Acid To Blender Control).

2. manually aligning the NV pumps suction to the FWST.

C.

1. OPEN 1 NV-269 (BA to Charging Pumps Block) ONLY

2. manually initiating Safety Injection to align the NV pumps suction to the FWST.

D.

1. OPEN I NV-269 (BA to Charging Pumps Block) AND INV-267A (Boric Acid To Blender Control).

2. manually initiating Safety Injection to align the NV pumps suction to the FWST.

Page 58 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

59 (1 point)

Given the following plant conditions:

A Ventilation Unit Condensate Drain Tank (VUCDT) release to the RC Discharge is in progress A 1 EMF-44(L) Trip 2 alarm is received Which ONE (1) of the following describes the automatic response to the EMF alarm?

A.

All Unit I VUCDT pumps trip ONLY.

B.

1WL-322B (Cont. Vent Drn Otsd Isol) closes ONLY.

C.

1WL-320 (VUCDT Rad Monitor Outlet) AND 1WP-35 (WMTNUCDT to RC CNTRL) close.

D.

1WL-320 (VUCDT Rad Monitor Outlet) AND 1WL-322B (Cont. Vent Drn Otsd Isol) close.

Page 59 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

60 (1 point)

Given the following indication on Unit 1:

Unit is operating at 100% RTP 1EMF-18 (Reactor Coolant Filter 1A) is in Trip 2 alarm 1EMF-48 (Reactor Coolant Hi Rad) is also in Trip 2 alarm The crew has implemented AP-1 8 (High Activity In Reactor Coolant)

Chemistry has reported that the cause of the high activity is due to FAILED FUEL Which ONE (1) of the following describes the action required per AP-1 8 and reason for that action?

A.

Increase L/D to 120 GPM Increases the removal rate of fission products resulting from the failed fuel.

B.

Increase L/D to 120 GPM Increases the effectiveness of the fission product gas removal by the VCT by increasing the flow rate through the NV system.

C.

Place cation bed demineralizer in service Facilitates the removal of fission products resulting from the failed fuel.

D.

Place cation bed demineralizer in service The cation bed will remove lithium causing a pH change that prevents further fuel degradation.

Page 60 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

61 1 point)

The following conditions exist on Unit 1:

The crew is responding to a Small-Break LOCA

Due to a failure to establish adequate safety injection flow FR-C.2 (Response to Degraded Core Cooling) has been implemented

NCPs B and C are running Which ONE (1) of the following RVLIS DIP conditions would indicate Degraded Core Cooling conditions exist?

REFERENCE PROVIDED A

TRAINA=18%

TRAIN B = 27%

B TRAINA=25%

TRAIN B = 27%

C.

TRAIN A = 23%

TRAIN B = Failed D.

TRAIN A = Failed TRAIN B = 21%

Page 61 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

62 (1 point)

The NC inventory requirements for SI termination during performance of FR-P.1 (Response to Imminent Pressurized Thermal Shock Condition) are (1) restrictive than the termination criteria during performance of E-O (Reactor Trip or Safety Injection).

One evolution that would be allowed DURING a soak 1

in FR-Ri is (2)

Which ONE (1) of the following completes the statements above?

A.

1. less

2. initiate an NC system cooldown B.

1. more

2. initiate an NC system cooldown C.

1. less

2. placing Auxiliary Spray in service D.

i. more

2. placing Auxiliary Spray in service Page 62 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

63 (1 point)

Unit 1 was in MODE 3 when a steam generator over pressure event occurred. Given the following events and conditions:

The crew entered FR-H.2 (Response to SIG Overpressure) lB SIG pressure is 1235 PSIG lB SIG NR level is 95%

The 1A, 1C and 1D SIG pressures are all 850 PSIG and 50% NR level All feedwater isolation status lights are DARK Which ONE (1) of the following statements describes the FIRST action to be taken per this procedure, and the reason for this action?

A.

Open the lB S/G PORVt0 immediately reduce pressure in the lB S/G B.

Dump steam from the 1 B S/G using CA pump #1 to immediately reduce pressure in the lB S/G C.

Manually isolate feedwater to the 1 B S/G to prevent additional feedwater from further pressurizing the lB S/G D.

Dump steam fromthe IA, IC and ID S/Gsto reduce NC system temperature and reduce pressure in the lB S/G Page 63 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

64 (1 point)

Given the following conditions on Unit 2:

A LOCA has occurred inside Containment Containment Pressure indicates 4 PSIG and rising NC Pressure indicates 1400 PSIG and decreasing FWST level is 200 inches The breaker for 2NS-3B, (Train B NS Pump Suction valve from FWST) has tripped, and cannot be reclosed Which ONE (1) of the following describes the effect on Control Board operations of the NS system?

A.

2B NS Pump can NOT be started.

B.

ONLY 2NS-1B (Train B Containment Sump Isolation Valve) can be opened.

C.

ONLY 2NI-184B (Train B Containment Sump Isolation Valve) can be opened open.

D.

2NS-1 B AND 2N1-184B (Train B Containment Sump Isolation Valves) can be opened.

Page 64 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

65 (1 point)

Given the following:

A Unit I RO is performing PT111A146001003 A (Semi-Daily Surveillance [tems Checklist)

The operator observes that I EMF 38, 39 & 40 sample points are aligned to upper containment ONLY 1)

Which ONE (1) of the following describes the MODE(s) where 1EMF 38(L) is required to be capable of NC system leak detection?

2)

What effect (if any) does the sample point alignment described above have on the sampling capability?

REFERENCE PROVIDED A.

1. M0de1ONLY

2. Due to the limited amount of communication between atmosphere in upper and lower containment, I EMF-38 will not be able to detect a 1 GPM NC system leak wfthin one hour.

B.

1. M0de1ONLY

2. Due to the normal mixing of containment atmosphere by the ventilation system, this does not significantly affect the ability of this sample package to sample the containment atmosphere.

C.

1. Modes 1-4

2. Due to the limited amount of communication between atmosphere in upper and lower containment, 1 EMF-38 will not be able to detect a 1 GPM NC system leak within one hour.

D.

1. Modes 1-4

2. Due to the normal mixing of containment atmosphere by the ventilation system, this does not significantly affect the ability of this sample package to sample the containment atmosphere.

Page 65 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

66 (1 point)

Given the following on Unit 2:

Maintenance is performing PLANNED work on equipment in the Unit 2 Turbine Building The work results in an OAC Priority Alarm (below the line) that the OATC has seen before during this particular maintenance activity The alarm was not specifically discussed prior to the work starting and this is the first time the alarm has been received during the shift Per OMP 2-2 (Conduct of Operations) which ONE (1) of the following would be the REQUIRED response by the OATC?

A.

The alarm is NOT required to be announced to the crew.

The alarm response is REQUIRED to be reviewed.

B.

The alarm is NOT required to be announced to the crew.

The alarm response is NOT REQUIRED to be reviewed.

C.

Announce the noun name of the alarm which shall be repeated back by the C/R Supervisor.

The alarm response is REQUIRED to be reviewed.

D.

Announce the noun name of the alarm which shall be repeated back by the C/R Supervisor.

The alarm response is NOT REQUIRED to be reviewed.

Page 66 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

67 (1 point)

In accordance with Tech. Spec. 3.4.16 (RCS Specific Activity, the LCO limits for Reactor Coolant System Dose Equivalent 1-13 1 (DEl) AND gross specific activity (GSA) are:

1) Less than or equal to pCi/gm DEl

2) Less than or equal to pCi/gm GSA Which ONE (1) of the following completes the statements above?

A.

1. 0.1

2. 100/E-bar B.

1. 100/E-bar

2. 0.1 C.

L 1.0

2. 100/E-bar D.

1. 100/E-bar

2. 1.0 Page 67 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

68 (1 point)

Given the following conditions on Unit 1:

A reactor startup is in progress on the unit In accordance with SOMP 01-02 (Reactivity Management):

One active licensed SRO and (1) shall be dedicated to the reactor startup, with no concurrent responsibilities.

The DEDICATED SRO is (2) to perform peer checks related to the reactor startup.

Which ONE (1) of the following completes the statements above?

A.

1. oneactivelicensedRO

2. allowed B.

1. one active licensed RO

2. NOT allowed C.

1. two active licensed ROs

2. allowed D.

1. two active licensed ROs

2. NOT allowed Page 68 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

69 (1 point)

In accordance with NSD 700 (Verification Techniques):

To verify the position of a normally closed valve by turning the valve in the open direction, it requires (1)

To verify the position of a LOCKED OPEN valve, the operator shall (2)

Which ONE (1) of the following completes the statements above?

A.

1. noRedorWhitetagsONLY

2. remove locking device and physically verify valve position then replace the locking device B.

1. no Red or White tags AND supervisor permission

2. remove locking device and physically verify valve position then replace the locking device C.

1. noRedorWhitetagsONLY

2. ensure the locking device is properly installed and locked ONLY D.

1. no Red or White tags AND supervisor permission

2. ensure the locking device is properly installed and locked ONLY Page 69 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

70 (1 point)

Given the foHowing:

Both units are operating at 100% RTP The foflowing alarms are received on both units:

o lAD-li /C5(XFMRAURGENTALARM) o 2AD-1 1 I C5 (XFMR A URGENT ALARM)

Operations Test Group is performing B Train RN Valve Stroke Timing Each alarm is the resuft of a loss of ONE Cooling Group to the respective transformer To prevent a turbine runback to <56%, cooling must be restore to the (1) within aMAXIMUMof (2)

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

A.

1.

1A Main Transformer

2. 8min45sec B.

1.

1A Main Transformer

2. 28min45sec C.

1. 2AMainTransformer

2. 8min45sec D.

1. 2AMainTransformer

2. 28min45sec Page 70 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

71 (1 point)

Regarding the use of Electronic Dosimeters (ED):

If a DOSE alarm setpoint is exceeded, the alarm will (1)

If a DOSE RATE alarm setpoint is exceeded, the alarm will (2)

Which ONE (1) of the following completes the statements above?

A.

1. not clear until the ED is reset

2. clear when the dose rate drops below the alarm setpoint B.

1. not clear until the ED is reset

2. not clear until the ED is reset C.

1. automatically clear after 10 seconds

2. clear when the dose rate drops below the alarm setpoint D.

1. automatically clear after 10 seconds

2. not clear until the ED is reset Page 71 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

72 (1 point)

Given the following conditions:

A team of Operators is preparing to enter the RCA to perform a valve lineup in a high radiation area The Radiation Work Permit (RWP) specifies that the individual workers must not exceed their annual ALERT exposure limits Based on the conditions above, the individual workers exposure must remain LESS THAN a MAXIMUM of (1) of the annual (2)

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

A.

1.80%

2. NRC exposure limit B.

1. 80%

2. Duke administrative exposure limit C.

1. 90%

2. NRC exposure limit D.

1. 90%

2. Duke administrative exposure limit Page 72 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

73 (1 point)

Given the following conditions on Unit 1:

Unit 1 has experienced a Large Break LOCA Containment pressure is currently 4.5 PSIG Which ONE (1) of the following describes the correct parameters and logic which would require entry into the RED path procedure FR-C.1 (Response to Inadequate Core Cooling) per the CSF status trees?

A.

WR TH > 720° F and UR RVLIS Level indicates less than 60 B.

Core Exits> 700° F and UR RVLIS Level indicates less than 60 C.

WR TH > 700° F and LR RVLIS Level < 39%

D.

Core Exits> 700° F and LR RVLIS Level < 39%

Page 73 of 75

McGuire Nuclear Station 2011 MNSRONRCExamination Question:

74 1 point)

The following conditions on Unit 1:

Due to a fire in the Auxiliary Building control of the plant has been transferred to the SSF PZR level is 85% and increasing slowly PZR pressure is 2100 PSIG and STABLE The SSF PZR Heaters are ON 1)

In accordance with AP-24 (Loss of Plant Control Due to Fire) what actions should be taken with regards to controlling PZR level?

2)

What indications available at the SSF could be used to verify natural circulation?

A.

1. Allow the PZR to fill

2. NC Loop WIR Pressure and Steam Generator Pressure B.

1. Allow the PZR to fill

2. Core Exit Thermocouples and NC Loop WIR Pressure C.

1. Open the Rx Head vents to lower PZR level

2. NC LoopW/R Pressure and Steam Generator Pressure D.

1. Open the Rx Head vents to lower PZR level

2. Core Exit Thermocouples and NC Loop WIR Pressure Page 74 of 75

McGuire Nuclear Station 2011 MNS RO NRC Examination Question:

75 (1 point)

Given the following conditions on Unit 1:

The unit is stable at 47% RTP Turbine Impulse Pressure is 350 PSIG Which ONE (1) of the following is the MINUMUM condition that would require entry into AP-03 (Load Rejection)?

A.

CF Pump 1A ONLY TRIPs B.

CF Pumps 1AAND lB TRIP C.

Busline IA ONLY DEENERGIZES D.

Buslines IA AND lB DEENERGIZE Page 75 of 75

Reference Listfor:

2011 MNS RO NRC Examination Steam Tables including Mollier Diagram ECAO.1 Enc4 Tech Spec 38.1 (AC Sources

- Operating)

FR-C.2 Page 10 Tech Spec 3.4.15 (RCS Leakage Detection Instrumentation)

Printed 6/9/2011 1:06:13 PM

I LOSS OF ALL AC POWER RECOVERY WITHOUT S/I r

MNS I

REQUIRED i

PAGE NO.

I I

31of31 EPIIIAJ5000IECA-O. I I - Page 1 of 1 I

Rev. 10 TJNIT 1 Natural Circulation Parameters 1.

The following conditions support or indicate natural circulation flow:

NC subcooling GREATER THAN 0°F S/G pressures STABLE OR GOING DOWN NC T-Hots STABLE OR GOING DOWN

Core exit T/Cs STABLE OR GOING DOWN NC T-Colds AT SATURATION TEMPERATURE FOR S/G PRESSURE (WITHIN THE LIMITS OF THE GRAPH BELOW).

2.

Natural Circulation flow is not established.

THEN raise dumping steam to establish Natural Circulation fl-ow.

1200 1100 S

G 1000 p

R 900 E

800 S

U R

700 E

600 P

S I

500 G

400 300 200 100 0

600 200 250 300 350 400 450 500 550 NC T-COLD(°F)

AC Sources Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC SourcesOperating LCO 3.8.1 The following AC electrical sources shall be OPERABLE:

a.

Two qualified circuits between the offsite transmission network and the Onsite Essential Auxiliary Power System; and b.

Two diesel generators (DGs) capable of supplying the Onsite Essential Auxiliary Power Systems; AND The automatic load sequencers for Train A and Train B shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS NOTE LCO 3.O.4.b is not applicable to DG5.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One offsite circuit A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable.

OPERABLE offsite circuit.

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Declare required feature(s) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from with no offsite power discovery of no available inoperable when offsite power to one its redundant required train concurrent with feature(s) is inoperable.

inoperability of redundant required feature(s)

AND (continued)

McGuire Units 1 and 2 3.8.1-1 Amendment Nos. 221/203

AC Sources Operating 3.8.1 B.1 Perform SR 3.8.1.1 for the offsite circuit(s).

AND B.2 Declare required feature(s) supported by the inoperable DG inoperable when its required redundant feature(s) is inoperable.

AND 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of Condition B concurrent with inoperability of redundant required feature(s)

B.3.1 Determine OPERABLE DG is not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.2 for OPERABLE DG.

AND (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.3 Restore offsite circuit to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

AND 6 days from discovery of failure to meet LCO B.

One DG inoperable.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 24 hours McGuire Units I and 2 3.8.1-2 Amendment Nos. 184/1 66

ACTIONS AC Sources Operating 3.8.1 (continued)

For Unit I only, the Completion Time that the IA EDG can be inoperable as specified by Reguired Action B.4 may be extended beyond the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and 6 days from discovery of failure to meet the LCO up to a total of 10 days as part of the IA EDG Jacket/Intercooler Water Pump Motor repair. Upon completion of the repair and restoration, this footnote is no longer applicable and will expire at 1741 hours0.0202 days 0.484 hours 0.00288 weeks 6.624505e-4 months on June 15, 2007.

CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.4 Restore DG to OPERABLE 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months status.

AND 6 days from discovery of failure to meet LCO C.

Two offsite circuits C.1 Declare required feature(s) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from inoperable, inoperable when its discovery of redundant required Condition C feature(s) is inoperable, concurrent with inoperability of redundant required feature(s)

AND C.2 Restore one offsite circuit 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to OPERABLE status.

McGuire Units I and 2 3.8.1-3 Amendment Nos. 241/-,

AC Sources Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

One offsite circuit NOTE inoperable.

Enter applicable Conditions and Required Actions of LCO 3.8.9, AND Distribution Systems Operating, when Condition D is One DG inoperable, entered with no AC power source to any train.

D.1 Restore offsite circuit to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

OR D.2 Restore DG to OPERABLE 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months status.

E.

Two DGs inoperable.

E.1 Restore one DG to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months OPERABLE status.

F.

One automatic load F.1 Restore automatic load 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sequencer inoperable, sequencer to OPERABLE status.

G.

Required Action and G.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A, B, AND C, D, E, or F not met.

G.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months H.

Three or more AC H.1 Enter LCO 3.0.3.

Immediately sources inoperable.

McGuire Units I and 2 3.8.1-4 Amendment Nos. 184/1 66

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated power 7 days availability for each offsite circuit.

SR 3.8.1.2 NOTES 1.

Performance of SR 3.8.1.7 satisfies this SR.

2.

All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

3.

A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer.

When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.7 must be met.

Verify each DG starts from standby conditions and 31 days achieves steady state voltage 3740 V and 4580 V, and frequency 58.8 Hz and 61.2 Hz.

(continued)

McGuire Units I and 2 3.8.1-5 Amendment Nos. 184/166

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

NOTES 1.

DG loadings may include gradual loading as recommended by the manufacturer.

2.

Momentary transients outside the load range do not invalidate this test.

3.

This Surveillance shall be conducted on only one DG at a time.

4.

This SR shall be preceded by and immediately follow without shutdown a successful performance of SR 3.8.1.2 or SR 3.8.1.7.

Verify each DG is synchronized and loaded and operates for 60 minutes at a load 3600 kW and 4000 kW.

SR 3.8.1.3 SURVEILLANCE FREQUENCY 31 days SR 3.8.1.4 Verify each day tank contains 39 inches of fuel oil.

31 days SR 3.8.1.5 Check for and remove accumulated water from each day 31 days tank.

SR 3.8.1.6 Verify the fuel oil transfer system operates to 31 days automatically transfer fuel oil from storage tank to the day tank.

(continued)

McGuire Units I and 2 3.8.1-6 Amendment Nos. 254 I 234

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.7 NOTES All DG starts may be preceded by an engine prelube period.

Verify each DG starts from standby condition and 184 days achieves in 11 seconds voltage of 3740 V and frequency of 57 Hz and maintains steady state voltage 3740 V and 4580 V, and frequency 58.8 Hz and 61.2 Hz.

SR3.8.1.8 NOTES This Surveillance shall not be performed in MODE I or 2.

Verify automatic and manual transfer of AC power 18 months sources from the normal offsite circuit to each alternate offsite circuit.

(continued)

McGuire Units I and 2 3.8.1-7 Amendment Nos. 184 /166

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.9 Verify each DG, when connected to its bus in parallel with 18 months offsite power and operating with maximum kVAR loading that offsite power conditions permit, rejects a load greater than or equal to its associated single largest post-accident load, and:

a.

Following load rejection, the frequency is 63 Hz; b.

Within 3 seconds following load rejection, the voltage is 3740 V and 4580 V; and c.

Within 3 seconds following load rejection, the frequency is 58.8 Hz and 61.2 Hz.

SR 3.8.1.10 Verify each DG does not trip and voltage is maintained 18 months 4784 V during and following a load rejection of 3600kWand4000 kW.

(continued)

McGuire Units I and 2 3.8.1-8 Amendment Nos. 192 (Unit 1) 173 (Unit 2)

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.11 NOTES 1.

All DG starts may be preceded by an engine prelube period.

2.

This Surveillance shall not be performed in MODE 1,2,3, or4.

Verify on an actual or simulated loss of offsite power 18 months signal:

a.

De-energization of emergency buses; b.

Load shedding from emergency buses; c.

DG auto-starts from standby condition and:

1.

energizes the emergency bus in 11 seconds, 2.

energizes auto-connected blackout loads through automatic load sequencer, 3.

maintains steady state voltage 374OVand 4580V, 4.

maintains steady state frequency 58.8 Hz and 61.2 Hz, and 5.

supplies auto-connected blackout loads for 5 minutes.

(continued)

McGuire Units I and 2 3.8.1-9 Amendment Nos. 184/166

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR3.8.1.12 NOTES All DG starts may be preceded by prelube period.

Verify on an actual or simulated Engineered Safety 18 months Feature (ESF) actuation signal each DG auto-starts from standby condition and:

a.

In 11 seconds after auto-start signal achieves voltage of 3740 and during tests, achieves steady state voltage 3740 V and 4580 V; b.

In 11 seconds after auto-start signal achieves frequency of 57 Hz and during tests, achieves steady state frequency 58.8 Hz and 61.2 Hz; c.

Operates for 5 minutes; and d.

The emergency bus remains energized from the offsite power system.

(continued)

McGuire Units I and 2 3.8.1-10 Amendment Nos. 184/1 66

AC Sources Operating 3.8.1 (continued)

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.13 Verify each DGs non-emergency automatic trips are 18 months bypassed on actual or simulated loss of voltage signal on the emergency bus concurrent with an actual or simulated ESF actuation signal.

SR 3.8.1.14 NOTES 1.

Momentary transients outside the load range do not invalidate this test.

2.

DG loadings may include gradual loading as recommended by the manufacturer.

Verify each DG, when connected to its bus in parallel with 18 months offsite power and operating with maximum kVAR loading that offsite power conditions permit, operates for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

a.

For 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 4200 kW and 4400 kW; and b.

For the remaining hours of the test loaded 3600 kW and 4000 kW.

McGuire Units I and 2 3.8.1-11 Amendment Nos.242/223

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.15 NOTES 1.

This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 3600 kW and 4000 kW.

Momentary transients outside of load range do not invalidate this test.

2.

All DG starts may be preceded by an engine prelube period.

Verify each DG starts and achieves, in 11 seconds, 18 months voltage 3740 V, and frequency 57 Hz and maintains steady state voltage 3740 V and 4580 V and frequency 58.8 Hz and 61.2 Hz.

SR 3.8.1.16 NOTES This Surveillance shall not be performed in MODE 1, 2, 3, or4.

Verify each DG:

18 months a.

Synchronizes with offsite power source while loaded with emergency loads upon a simulated restoration of offsite power; b.

Transfers loads to offsite power source; and c.

Returns to standby operation.

(continued)

McGuire Units I and 2 3.8.1-12 Amendment Nos. 184/166

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR3.8.1.17 NOTES This Surveillance shall not be performed in MODE 1, 2, 3, or4.

Verify, with a DG operating in test mode and connected 18 months to its bus, an actual or simulated ESF actuation signal overrides the test mode by:

a.

Returning DG to standby operation; and b.

Automatically energizing the emergency load from offsite power.

SR 3.8.1.18 Verify interval between each sequenced load block is 18 months within design interval for each automatic load sequencer.

(continued)

McGuire Units I and 2 3.8.1-13 Amendment Nos. 184/166

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.19 NOTES 1.

All DG starts may be preceded by an engine prelube period.

2.

This Surveillance shall not be performed in MODE 1,2,3, or4.

Verify on an actual or simulated loss of offsite power 18 months signal in conjunction with an actual or simulated ESF actuation signal:

a.

De-energization of emergency buses; b.

Load shedding from emergency buses; and c.

DG auto-starts from standby condition and:

1.

energizes the emergency bus in 11

seconds, 2.

energizes auto-connected emergency loads through load sequencer, 3.

achieves steady state voltage 3740 V and 4580V, 4.

achieves steady state frequency 58.8 Hz and 61.2 Hz, and 5.

supplies auto-connected emergency loads for 5 minutes.

(continued)

McGuire Units I and 2 3.8.1-14 Amendment Nos. 184/1 66

AC Sources Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.20 NOTES All DG starts may be preceded by an engine prelube period.

Verify when started simultaneously from standby 10 years condition, each DG achieves, in 1 1 seconds, voltage of 3740 V and frequency of 57 Hz and maintains steady state voltage 3740 V and 4580 V, and frequency 58.8 Hz and 61.2 Hz.

McGuire Units 1 and 2 3.8.1-15 Amendment Nos. 184/1 66

MNS RESPONSE TO DEGRADED CORE COOLING PAGE NO.

EPI1IAI5000IFR-C.2 10 of 44 i

UNIT1 Rev.7 ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 7.

Check Reactor Vessel level as follows:

a.

Determine required reactor vessel delta P from table below:

Required REACTOR VESSEL D/P Number of NC Pumps TRN A

TRN B

On With 1A NC Pump With 1C NC Pump On Off On Off 4

44%

N/A 44%

N/A 3

30%

24%

30%

24%

2 23%

15%

23%

15%

1 16%

10%

16%

10%

b.

Check REACTOR VESSEL DIP b.

Perform the following:

GREATER THAN REQUIRED DELTA P.

1) if REACTOR VESSEL DIP going up, THEN observe Note prior to Step I and RETURN JQ. Step 1.

_2) IStep8.

c.

RETURN TQ procedure and step in effect.

8.

Check if one NC pump should be stopped:

a.

All NC pumps

- ON.

a. jQStep 10.

b.

Stop lB NC pump.

c.

Place I NC-29C (B NC Loop PZR Spray Control) in manual and CLOSED.

_d.

GOjQStep10.

RCS Leakage Detection instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:

a.

The containment floor and equipment sump level monitors and the incore instrument sump level alarm; b.

The containment atmosphere particulate radioactivity monitor; and c.

The containment ventilation unit condensate drain tank level monitor.

APPLICABILITY:

MODE 1 for all instrumentation, MODES 2, 3, and 4 for all instrumentation except the containment atmosphere particulate radioactivity monitor.

ACTIONS NOTE Separate Condition entry is allowed for each leakage detection instrument.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or both containment A.1 floor and equipment

- NOTE sump level monitor(s)

Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable, after establishment of steady state operation.

Perform SR 3.4.13.1.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND A.2 Restore inoperable 30 days containment floor and equipment sump level monitor(s) to OPERABLE status.

(continued)

McGuire Units I and 2 3.4.15-1 Amendment Nos. 235/217

ACTIONS (continued)

RCS Leakage Detection instrumentation 3.4.15 CONDITION REQUIRED ACTION COMPLETION TIME B.

Containment B.1 atmosphere particulate

- NOTE radioactivity monitor Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable, after establishment of steady state operation Perform SR 3.4.13.1.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR B.2 Analyze grab samples of Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the containment atmosphere.

C.

Containment ventilation C.1.1 unit condensate drain

- NOTE tank level monitor Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable, after establishment of steady state operation Perform SR 3.4.13.1.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR C.1.2 Analyze grab samples of Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

the containment atmosphere.

OR C.1.3 Perform SR 3.4.15.1.

Once per8 hours.

AND C.2 During Modes 2, 3, and 4, 30 days restore inoperable containment ventilation unit condensate drain tank level monitor to OPERABLE status.

(continued)

McGuire Units 1 and 2 3.4.15-2 Amendment Nos. 235 /217

ACTIONS (continued)

RCS Leakage Detection instrumentation 3.4.15 CONDITION REQUIRED ACTION COMPLETION TIME D.

Containment D.1 Restore containment 30 days atmosphere particulate atmosphere particulate radioactivity monitor radioactivity monitor to inoperable in MODE 1.

OPERABLE status.

AND OR Containment ventilation D.2 Restore containment unit condensate drain ventilation unit condensate 30 days tank level monitor drain tank level monitor to inoperable in MODE 1.

OPERABLE status.

E.

Incore instrument sump E.1 level alarm inoperable.

- NOTE Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

Perform SR 3.4.13.1.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months F.

Required Action and F.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

AND F.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months G.

All required monitors G.1 Enter LCO 3.0.3.

Immediately inoperable.

McGuire Units I and 2 3.4.15-3 Amendment Nos. 235 /217

RCS Leakage Detection instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of the containment 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months atmosphere particulate radioactivity monitor.

SR 3.4.15.2 Perform COT of the containment atmosphere particulate 92 days radioactivity monitor.

SR 3.4.15.3 Perform CHANNEL CALIBRATION of the containment 18 months floor and equipment sump level monitors.

SR 3.4.15.4 Perform CHANNEL CALIBRATION of the containment 18 months atmosphere particulate radioactivity monitor.

SR 3.4.15.5 Perform CHANNEL CALIBRATION of the containment 18 months ventilation unit condensate drain tank level monitor.

SR 3.4.15.6 Perform CHANNEL CALIBRATION of the incore 18 months instrument sump level alarm.

McGuire Units I and 2 3.4.15-4 Amendment Nos. 235 / 217

Examination KEYfor:

2011 MNS RO NRC Examination Question Answer Number 1

C 2

C 3

C 4

A 5

A 6

A 7

C 8

B 9

A 10 B

11 C

12 B

13 C

14 A

15 B

16 C

17 A

18 A

19 B

20 C

21 C

22 B

23 D

24 C

25 C

Printed 6/9/2011 1:06:33 PM Page 1 of3

Examination KEYfor:

2011 MNS RO NRC Examination Question Answer Number 26 C

27 D

28 A

29 C

30 A

31 C

32 A

33 D

34 D

35 C

36 B

37 C

38 D

39 C

40 C

41 A

42 B

43 D

44 A

45 A

46 D

47 B

48 D

49 B

50 C

Printed 6/9/2011 1:06:33 PM Page 2 of3

Examination KEYfor:

2011 MNS RO NRC Examination Question Answer Number 51 D

52 D

53 D

54 B

55 B

56 C

57 D

58 B

59 C

60 C

61 D

62 C

63 C

64 C

65 A

66 C

67 C

68 A

69 B

70 D

71 A

72 B

73 D

74 D

75 D

Printed 6/9/2011 1:06:33 PM Page 3 of3

ML112280599

Text

RESPONSE

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