1.201001K1.11001 - 2H1 1-P603: o Cooling Water dP 0 psid o ... · 2H1 1-P603: o Charging Water Pressure 1480 psig o Cooling Water dP 0 psid o Drive Water dP Upscale o Drive Water

HLT-07 RO NRC EXAM

1.201001K1.11001 -•

The Unit 2 reactor is operating at 100% power with the following indications present on panel2H1 1-P603:

o Charging Water Pressure 1480 psigo Cooling Water dP 0 psido Drive Water dP Upscaleo Drive Water Flow 0 gpmo Cooling Water Flow 5 gpm

With the above indications, which ONE of the choices below completes the followingstatements?

The CRD has been fully closed.

RWCU Seal Purge flow

__________

isolated?

A. Flow Control Valve, 2C1 1-FOO2A;is

B. Flow Control Valve, 2C11-FOO2A;is NOT

C. Drive Water Pressure Control Valve, 2C1 1-F003,is

D. Drive Water Pressure Control Valve, 2C1 1-F003,is NOT

1

HLT—07 RO NRC EXAM

2. 202001A1.02 001

Which ONE of the choices below completes the following statements concerning monitoringUnit 2 INDIVIDUAL jet pump flows and a potential problem associated with a jet pump failureduring a Loss of Coolant Accident (LOCA)?

If jet pump #3 failure were to occur during plant operation, the INDIVIDUAL failed jetpump dP can be monitored on panel

A catastrophic failure of jet pump #3 will be indicated by

A. 2H11-P602;a sudden INCREASE in reactor power

B. 2H11-P602;a sudden REDUCTION in jet pump differential pressure

C. 2H11-P619;a sudden INCREASE in reactor power

D. 2H11-P619;a sudden REDUCTION in jet pump differential pressure

2

HLT-07 RO NRC EXAM

3. 202002K3.03 001

Unit 2 is operating at 100% RTP when a malfunction causes a Recirc runback signal to SpeedLimiter #1 on BOTH Recirc Pumps.

Which ONE of the choices below completes the following statements?

While the Recirc Pumps are reducing speed, INDICATED reactor water level on2C32-R606A, B and C, Narrow Range instruments will

__________

The FINAL Recirc Pump speed will be

__________

A. decrease;22%

B. decrease;33%

C. increase;22%

D. increase;33%

3


4. 203000G2.4.34 001

An event occurred on Unit 2 requiring control to be transferred to the Remote Shutdown Panel(RSDP).

o ALL Emergency Transfer Switches have been placed to the “EMERGENCY Positiono Subsequently, a LOCA signal is received and Reactor pressure decreases to 90 psig

Which ONE of the choices below completes the following statement concerning Unit 2 RHRLPCI Injection from the RSDP?

Placing the Emergency Transfer Switches, for the RHR pump(s) controlled from the RSDP,to the “EMERGENCY” Position

__________

The LPCI injection path associated with the above pump(s)

A. will NOT defeat the auto start function for the pump(s);must be MANUALLY aligned to inject into the RPV

B. will NOT defeat the auto start function for the pump(s);will AUTOMATICALLY align to inject into the RPV

C. will defeat its auto start function for the pump(s);must be MANUALLY aligned to inject into the RPV

D. will defeat its auto start function for the pump(s);will AUTOMATICALLY align to inject into the RPV

4

HLT-07 RO NRC EXAM

5. 204000K4.01 001

Unit 2 is at operating at RTP when a malfunction occurs causing the following conditions:

o RWCU HX room temperature and pump room temperatures peaked at 125°Fo RWCU differential flow reached 60 gpm for 30 seconds then went to 0 gpm (indicated)o Non-Regenerative HX (NRHX) outlet temperature peaked at 125°Fo ‘2W RWCU pump cooling water temperature peaked at 145°Fo The “2W’ RWCU pump tripped

Based on these conditions, which ONE of the choices below is the reason the”2B” RWCU pumptripped?

The “2B” RWCU pump tripped because of high

A. differential flow

B. pump room temperature

C. pump cooling water temperature

D. Non-Regenerative HX (NRHX) outlet temperature

5

HLT-07 RO NRC EXAM

6. 205000K5.02 001

Unit 2 is shutdown with the following conditions:

o A’ ioop of RHR is in Shutdown Cooling (SDC)o 2E1 1-F008, SDC Suction Vlv, is OPENo 2E1 1-F009, SDC Suction Vlv, is OPENo 2E1 1-FO15A, RHR Inbd Inj Vlv, is OPENo Reactor pressure is 125 psig and steady

o Subsequently, 2E1 1-F048A, Hx Bypass valve, fails full OPEN and cannot be re-closedo Reactor pressure starts increasing at 1 psig/minute

Without any operator actions and based on the above conditions, which ONE of the choicesbelow completes the following statements?

When Reactor pressure reaches 140 psig, RHR Valves,

___________

will be CLOSED.

The RHR pumps

________

receive a trip signal as a result of these valve closures.

A. 2E1 1-F008 and 2E1 l-F009 (ONLY);will

B. 2E1 1-F008 and 2E1 1-F009 (ONLY);will NOT

C. 2E11-F008, 2E11-F009 and 2E11-FO15A;will

D. 2E11-F008, 2E11-F009 and 2E11-FO15A;will NOT

6

HLT-07 RO NRC EXAM

7. 206000K5.06 001

The Unit 2 Shift Supervisor has established operation at the Remote Shutdown Panel due toControl Room evacuation.

Currently Unit 2 reactor water level is -30 inches and reactor pressure is 1000 psig.

The HPCI system is operating with the following parameters:

o HPCI turbine speed = 3000 rpmo HPCI pump discharge pressure = 780 psig

An operator makes an adjustment locally, which results in the HPCI turbine speed increasing to5050rpm.

After the operator makes the adjustment, which ONE of the choices below completes thefollowing statement?

The operator is using a

___________

to monitor HPCI turbine speed and the HPCI turbine

_______

have tripped.

A. locally mounted gauge;should

B. locally mounted gauge;should NOT

C. strobe tachometer;should

D. strobe tachometer;should NOT

7

HLT-07 RO NRC EXAM

8. 209001K1.12 001

A transient has occurred on Unit 2.

At 10:00 the following conditions exist:

o Drywell pressure 0.7 psigo Reactor water level -95 inches decreasing 2 inches/minuteo Reactor pressure 500 psig decreasing 2 psig/minuteo 2A Core Spray pump is MANUALLY started


At 10:01, the number of CS/RHR Pump Room Coolers operating is

__________

At 10:05,

__________

CS/RHR Pump Room Coolers will be operating.

A. zero (0);ONLY two (2)

B. zero (0);ALL four (4)

C. two (2);ONLY two (2)

D. two(2);ALL four (4)

8

HLT-07 RO NRC EXAM

9. 209001K5.O1 001

A LOCA is in progress. The 2A Core Spray pump is injecting at 1000 gpm to maintain RPVwater level above the top of active fuel.

Which ONE of the following would be an indication that the 2A Core Spray pump isexperiencing cavitation?

A. The motor amps are steadily increasing.

B. The pump trips due to low suction pressure.

C. The minimum flow valve intermittently opens and closes.

D. The pump discharge pressure steadily increases as flow decreases.

9

HLT-07 RO NRC EXAM

10. 211000K4.02 001

Unit 2 is operating at 100% RTP with the 2B SBLC pump inoperable.

o The 2B SBLC pump breaker is Danger Tagged OPEN

The crew has just been tasked with performing 34SV-C41-002-2, Standby Liquid Control PumpOperability Test, for the 2A SBLC pump.

Which ONE of the choices below completes the following statement concerning the SquibValve Continuity lights on the 2H11-P603 panel and the RWCU System?

After the operator locally starts the 2A SBLC Pump,

A. two (2) Squib Valve Continuity lights on the 2H1 l-P603 panel will be ILLUMiNATED andthe RWCU System WiLL isolate

B. two (2) Squib Valve Continuity lights on the 2H1 1-P603 panel will be ILLUMINATED andthe RWCU System WILL NOT isolate

C. ONLY one (1) Squib Valve Continuity light on the 2H11-P603 panel will beILLUMINATED and the RWCU System WILL isolate

D. ONLY one (1) Squib Valve Continuity light on the 2H1 1-P603 panel will beILLUMINATED and the RWCU System WILL NOT isolate

10

HLT-07 RO NRC EXAM

11. 212000A2.08 001

Unit 2 is in Mode 4 with RHR Shutdown Cooling in service.

An event occurs causing RWL to decrease and results in the following:

o 2C32-R606A-C GEMAC (+) 2 inches (LOWEST level reached)

o Subsequently, the NPO recovers RWL to (+) 20 inches


During this event, the RPS RWL Scram Setpoint

__________

EXCEEDED.

34AB-E1 1-001-2, Loss Of Shutdown Cooling,

__________

REQUIRED to be entered.

A. was;is NOT

B. was;is

C. was NOT;is NOT

D. was NOT;is

11


12. 212000K3.03 001

Unit 2 is operating at 100% RTP when a loss of RPS Bus 2A occurs.

Which ONE of the choices below describes the affect of losing RPS Bus 2A on the LPRMs?

A. ONLY Half of the LPRMs inputs associated with APRMs 2B & 2D are still VALID.

B. ONLY Half of the LPRMs inputs associated with APRMs 2A & 2C are still VALID.

C. NONE of the LPRMs inputs associated with APRMs 2B & 2D are still VALID.

D. ALL of the LPRMs inputs associated with APRMs 2A & 2C are still VALID.

12

HLT-07 RO NRC EXAM

13. 215002K6.04 001

Unit 2 is operating at 100% power with a centrally located control rod selected.

o The operator bypasses APRM channel “A” due to bad CPU

Which ONE of the choices below identifies the effect this action will have on the RBM ‘A”channel?

RBM “A” will automatically use the

A. “C” APRM channel to monitor the neutron flux in the locality of the selected rod

B. “C” APRM channel to determine one of the three upscale setpoints

C. “D” APRM channel to monitor the neutron flux in the locality of the selected rod

D. “D” APRM channel to determine one of the three upscale setpoints

13

HLT-07 RO NRC EXAM

14. 215003A1.06 001

Unit 1 is in Startup with IRM lA! indicating 50 on Range 4. ALL other IRMs are readingMid-scale on their respective range.

The NPO momentarily positions IRM IA Range switch to Range 3 and then back to Range 4.


With IRM ‘lA” on Range 3,

_________

and 603-238, ROD OUT BLOCK, will be in thealarm condition.

Once IRM ‘lA” is returned to Range 4, the IRM ‘lA” will be EXTINGUISHED.

A. annunciators 603-221, IRM UPSCALE, 603-203, IRM BUS A UPSCALE TRIP OR INOP;

Drawer UPSC amber light on 1H1 1—P606

B. annunciators 603-221, IRM UPSCALE, 603-203, IRM BUS A UPSCALE TRIP OR INOP;

UPSC amber light on the benchboard (horizontal portion) of lHl l-P603

C. ONLY annunciators 603-221, IRM UPSCALE;

UPSC amber light on the benchboard (horizontal portion) of 1H1 1-P603

D. ONLY annunciators 603-221, IRM UPSCALE;

Drawer UPSC amber light on 1H1 1-P606

14

HLT-07 RO NRC EXAM

15. 215004K6,02 001

Unit 1 is starting up.

o Reactor Water Level (+) 37 Incheso The reactor is criticalo IRMs are all on-scale on Range 3

A loss of 24/48 VDC “IB”, 1R25-S016, occurs.

Which ONE of the choices below will occur as a result of this power loss?

Source Range Monitor (SRM)__________ indicator will fail

__________

A. ‘iC”;as is

B. ‘iC”;downscale

C. “lD”;as is

D. ‘iD”;downscale

15


16. 215005A1.01 001

Unit 2 is at 9% RTP when the following occurs:

o LPRM 44-21A fails UPSCALE (Inputs into APRM 2Dh)o Subsequently, Operations bypasses the failed LPRM

The following represents the status of APRM “2D’ fiçr LPRM 44-21A is bypassed:

o Number of Level D LPRM Inputs ... 6o Number of Level C LPRM Inputs ... 4o Number of Level B LPRM Inputs ... 5o Number of Level A LPRM Inputs ... 2


When LPRM 44-21A failed upscale, APRM “2D” power indication

_________

After LPRM 44-21A is bypassed, APRM “2D is inoperable because there aretoo few

_________

A. remained the same;total LPRM inputs

B. remained the same;LPRM inputs per level

C. increased;total LPRM inputs

D. increased;LPRM inputs per level

16

HLT-07 RO NRC EXAM

17. 215005A4.03 001

Unit 1 is operating at 100% RTP when 603-210-1, APRM/OPRM TRIP, alarm comes in andthen immediately clears due to a momentary failure of one (1) APRM.


With the above condition, a RPS Half Scram signal

__________

have been received.

If the APRM is bypassed, the TOTAL number of 2/4 Logic modules (Voters) that will havethe associated APRM’s bypass light ILLUMINATED is

__________

A. would;two (2)

B. would;four (4)

C. would NOT;two (2)

D. would NOT;four (4)

17

HLT-07 RO NRC EXAM

18. 216000A4.01 001

A transient has occurred on Unit 2 resulting in Reactor Water Level (RWL) decreasing.

A RWL Milestone is established at -175 inches.

Subsequently, an Emergency Depress is performed.

A Normal RWL band of (+) 32 to (+) 42 inches is established.

Which ONE of the choices below completes the following statement for determiningACCURATE RWL?

To determine when the -175 inch Milestone is reached, the NPO will be monitoring RWL atpanel 2H1 1-

__________

to determine when RWL is in its Normal band.

A. P601 and then transition to the 2H1 1-P603 panel

B. P601 and continue monitoring at the 2H1 1-P601 panel

C. P602 and then transition to the 2H1 1-P603 panel

D. P602 and continue monitoring at the 2H1 1-P602 panel

18

HLT-07 RO NRC EXAM

19. 217000K2.04 001

Which ONE of the choices below is the power supply to RCIC Barometric Condenser VacuumPump, 2E5 1 -C002-2?

A. 1251250V DC SWGR 2C, 2R22-S018

B. 125/250V DC SWGR 2D, 2R22-S019

C. 250V DC MCC 2A, Reactor Building Feeder, 2R24-S021

D. 125V DC DIST. CAB. 2D, ESS DIV I, 2R25-S 129

19

HLT-07 RO NRC EXAM

20. 218000K1.04 001

Unit 2 has experienced a Loss of Offsite Power (LOSP).

The following conditions existed at 15:00:

o ALL low pressure ECCS pumps have been manually startedo RPV Pressure 860 psig controlled by LLSo RWL -97 inches, decreasing at 2 inches/minuteo Drywell Pressure 1.0 psig, increasing at 0.3 psi/minuteo ADS Inhibit Switches “Normal’ position

Given these trends, which ONE of the following predicts the EARLIEST time that the ADSvalves will have automatically OPENED?

A. 15:03

B. 15:06

C. 15:13

D. 15:15

20

HLT-07 RO NRC EXAM

21. 223001A3.04 001

A LOCA has occurred on Unit 2 resulting in Drywell pressure increasing to 20 psig.

Subsequently, Drywell Sprays are placed in service and Drywell pressure is reduced to 1.0 psig.


The Drywell I Torus Vacuum Breakers will automatically cycle while Drywell pressure is

Monitoring for proper automatic operation of the Drywell / Torus Vacuum Breakers can beperformed from

__________

A. increasing to 20 psig;panel 2H1 1-P602 AND locally at panel 2T48-P001

B. increasing to 20 psig;panel 2H 11 -P602 ONLY

C. decreasing to 1.0 psig;panel 2H1 1-P602 AND locally at panel 2T48-P001

D. decreasing to 1.Opsig;panel 2H1 1-P602 ONLY

21

HLT-07 RO NRC EXAM

22. 223002K3.10 001

Unit 2 is at 100% power and the T2A’ Reactor Protection System (RPS) M/G Set trips.

Which ONE of the choices below completes the following statement?

After RPS M/G Set “2A” trips, the operating Reactor Water Cleanup pump

A. will AUTOMATICALLY trip due to suction valve closure

B. will AUTOMATICALLY trip due to low suction pressure

C. must be MANUALLY tripped due to suction valve closure

D. must be MANUALLY tripped due to low suction pressure

22

HLT-07 RO NRC EXAM

23. 233000K2.02 001

Unit 1 is in Mode 4 with 1BI and ‘iD’ Residual Heat Removal (RHR) pumps running inShutdown Cooling with Fuel Pool Cooling Assist in service.

o A condition develops on Emergency Bus 416OVAC “iF” which causes it to de-energize

Which ONE of the following predicts the status of the “IB” and “iD” RHR pumps?

A. “lB’ RHR Pump has stopped“iD’ RHR Pump has stopped

B. “lB’ RHR Pump is running‘iD” RHR Pump has stopped

C. “iB” RHR Pump has stopped‘iD” RHR Pump is running

D. “lB’ RHR Pump is running“iD’ RHR Pump is running

23

HLT-07 RO NRC EXAM

24. 234000K5.02 001

Unit 2 is in a refueling outage with the following conditions.

o Rx Mode Switch Locked in the REFUEL positiono Control rods One control rod is fully WITHDRAWNo Main Fuel Grapple Lowered, but verified to be able to clear the cattle chute by 3 ft.

(Empty grapple move)o NO rod is selected

The Refuel Bridge is over the Spent Fuel Pool and is moving toward the core to pick up the fuelbundle at position 17-42.

Which ONE of the following choices completes the following statements concerning how therefueling interlocks will respond?

With these conditions, the Refuel Bridge

___________

move to the intended core location.

When the Refuel Bridge stops, if the Grapple Raise/Lower switch is placed in the “LOWER’position, the Main Grapple

___________

lower.

A. will;will

B. will;will NOT

C. will NOT;will

D. will NOT;will NOT

24

HLT-07 RO NRC EXAM

25. 239002A3.02 001

Unit 2 experienced a Group One from 100% power.

Eight (8) SRV amber lights are illuminated and “B’ SRV is currently open with reactor pressureat 875 psig.

Which ONE of the choices below is the LOWEST reactor pressure which must have beenreached to cause these conditions?

A. 1080 psig

B. ll2Opsig

C. ll3Opsig

D. ll4Opsig

25

HLT-07 RO NRC EXAM

26. 241000A2.23 001

Unit 2 is operating at 23% reactor power.

The Main Turbine/Generator has just been tied to the grid.

Subsequently, 650-136, Vibration Alarm, is received.

Investigation reveals that Turbine Eccentricity is 3 mils and Vibration is 14 mils and has been atthese values for the last 2 minutes.


JAW 34S0-N30-0O1-2, Main Turbine Operation, the

__________

is required to be used formonitoring Eccentricity on the Main Turbine.

To CLOSE the Main Turbine Stop Valves, the NPO will

__________

on 2H1 1-P650 panel.

A. 2N32-R609, “TURBINE METAL EXPANSION/TEMP” recorder;select the “Close Valves” button on the “Control” -“Speed” Screen

B. 2N32-R609, “TURBINE METAL EXPANSION/TEMP” recorder;depress the Turbine Trip pushbuttons

C. Human Machine Interface (HMI) Screen;select the “Close Valves” button on the “Control” -“Speed” Screen

D. Human Machine Interface (HMI) Screen;depress the Turbine Trip pushbuttons

26

27. 259002A4.07 001

HLT-07 RU NRC EXAM

Unit 2 is at 60% power removing the “B” RFPT from service with the following conditions:

o “A” RFPT is in Auto, controlled from the FW Master Controller 2C32-R600o “B” RFPT is in Manual, as indicated below on M/A station, 2C32-R6O1Bo NO other switches have been repositioned

With the “B” RFPT controller in “Manual”, which ONE of the choices below completes thefollowing statements?

The “B” RFPT will be used to lower “B” RFPT flow.

Depressing the “B” RFPT “PF” key will

A. speed setter switch;lower the “B” RFPT setpoint by 4 inches

B. speed setter switch;change the “Green” bar display to “Controller Output”

C. output lever;lower the “B” RFPT setpoint by 4 inches

D. output lever;change the “Green” bar display to “Controller Output”

RFP B M?A STATION

27

HLT-07 RO NRC EXAM

28. 261000A1.01 001

Unit 2 is operating at 100% RTP.

At 10:00, an event occurs resulting in Unit 2 Drywell pressure increasing to and stabilizingat 2.5 psig.


At 10:15, with NO operator actions, the TOTAL amount of Unit 2 SBGT System flow goingto the Main Stack is expected to be between

__________

SCFM.

Unit 2 SBGT flow can be monitored on panels 2H11-P654 &

__________

A. 3000 and 4000;2H1 1-P657

B. 3000 and4000;2H1 1-P700

C. 6000 and 8000;2H1 1-P657

D. 6000 and 8000;2H1 1-P700

28

HLT-07 RO NRC EXAM

29. 261000K3.02 001

Unit 2 is operating at 100% RTP with the following conditions:

o Unit 2 Refueling Hatch installedo 2A Standby Gas Treatment (SBGT) Fan is Danger Tagged out for maintenance

Subsequently, the following occurs at the listed times:

10:00 A RWCU System break in the Unit 2 Reactor Building10:05 2Dl 1-K609A-D, Rx. Bldg. Contaminated Area Radiation increase to 20 mr/hr10:10 The Supply breaker for 2R24-S012, 600V MCC, trips OPEN

With NO operator action, which ONE of the choices below predicts how the Off-siteRadioactive Release Rates will be affected?

At 10:08, the Reactor Building Stack release rate will be

_________

than at 10:04.

At 10:15, the Main Stack release rate will be

__________

at 10:08.

A. higher;approximately the same as

B. higher;lower than

C. lower;approximately the same as

D. lower;lower than

29

HLT-07 RO NRC EXAM

30. 26200 1G2.4.47 001

WHITE LIGHTS

A. running, but is NOT tied to 4160 VAC 1E bus

B. running and IS tied to 4160 VAC 1E bus

C. NOT running, but can be manually started from the control room

D. NOT running and can NOT be started from the control room

A LOSP has occurred on Unit 1.

The operator notices the following indications on panel 1H1 1-P652 for 416OVAC 1E bus and itsassociated Diesel Generator (DG):

o LOSP 86 lockout TRIPPEDo Normal and Alternate supply breakers OPENo Auto Start System Operative light EXTINGUISHED

BLUE LIGHTS(EXTINGUISHED)

VOLT SELECT 1


The DG associated with 416OVAC 1E bus is

__________

30

HLT-07 RO NRC EXAM

31. 262002A3.01 001

Unit 2 is at 100% power when the following occurs:

o Loss of OffSite Power (LOSP)o !2A1? EDG fails to start

Which ONE of the below choices completes the following statements?

After the LOSP, the Unit 2 Vital AC Bus will INITIALLY receive power from

________

Three (3) hours later and without any operator actions, the Vital AC Busautomatically transfer to ANOTHER power source.

A. the Vital AC batteries;will

B. the Vital AC batteries;will NOT

C. 600 V Bus 2D via Vital AC battery charger;will

D. 600 V Bus 2D via Vital AC battery charger;will NOT

31

HLT-07 RO NRC EXAM

32. 263000A2.02 001

Unit 2 is operating at 100% power, with the “2A” and “2B” 125/25OVDC Station ServiceBatteries on equalize charge.

o All Control Building Chillers and fans trip and can NOT be restoredo Control Building temperatures start increasing

Which ONE of the following completes both statements concerning the effect of charging thebatteries with the above conditions present and any required actions to mitigate theconsequences of the event?

With the above conditions,

__________

To mitigate the consequences of this event, the operator will enter

A. Hydrogen concentration will rise in the battery rooms;

34AB-T41-001-2, ‘Loss Of ECCS, MCREC Or Area Ventilation Systems” and startEmergency Exhaust Fans 2Z41-C014 and 2Z41—C015

B. Hydrogen concentration will rise in the battery rooms;

34SO-R42-001-2, “125 VDC AND 125/250 VDC SYSTEM”, and secure all the batterychargers

C. the Battery Chargers will trip when their high temperature trip setpoint is reached;

34AB-T41-001-2, “Loss Of ECCS, MCREC Or Area Ventilation Systems” and startEmergency Exhaust Fans 2Z41-C014 and 2Z41-C015

D. the Battery Chargers will trip when their high temperature trip setpoint is reached;

34SO-R42-001-2, “125 VDC AND 125/250 VDC SYSTEM”, and secure all the batterychargers

32

HLT-07 RO NRC EXAM

33. 264000K4.06 001

Unit 2 is operating at 100% RTP with 34SV-R43-003-2, Diesel Generator 2C Monthly Test, inprogress.

Diesel Generator 2C is loaded to 1800 kW.

Which ONE of the choices below completes the following statements concerning operation ofthe Speed Droop and the Load Limit knobs? (Answer each part independently of each other)

If the Speed Droop Knob on Diesel Generator 2C is slowly turned to the zero (0) position,Diesel Generator 2C

_________

shutdown.

Slowly turning the Load Limit knob on Diesel Generator 2C to the zero (0) position,

A. will NOT;will completely shut off the fuel oil supply to Diesel Generator 2C

B. will NOT;will decrease the load to “0” kW and Diesel Generator 2C will continue to run

C. will;will completely shut off the fuel oil supply to Diesel Generator 2C

D. will;will decrease the load to “0” kW and Diesel Generator 2C will continue to run

33

HLT-07 RO NRC EXAM

34. 268000A4.01 001

JAW 34SV-SUV-019-2, Surveillance Checks, and TS 3.4.4, RCS Operational LEAKAGE,which ONE of the choices below identifies the integrator used in determiningUNIDENTIFIED! Leakage rate and its location?

A. Drywell Floor Drain Sump Integrator, 2G1 1-K601, located on panel 2H11-P602.

B. Drywell Floor Drain Sump Integrator, 2G1 l-K601, located on panel 2H1 l-P613.

C. Drywell Equipment Drain Sump Integrator, 2G1 l-K603, located on panel 2H11-P602.

D. Drywell Equipment Drain Sump Integrator, 2G11-K603, located on panel 2H11-P613.

34

HLT-07 RO NRC EXAM

35. 286000G2.4.9 001

Unit 1 experiences a LOCA and LOSP with ALL Unit 1 Emergency Diesel Generators failing tostart and cannot be manually started.

The following conditions exist on Unit 1:

o Reactor water level -160 inches, decreasing 2 inches/minuteo Reactor pressure 25 psig, slowly lowering

31E0-EOP-1 10-1, Alternate RPV Water Level Control, is in progress.

With the above conditions, which ONE of the choices below completes the following statementsconcerning Fire Water Injection into the Residual Heat Removal (RHR) System?

JAW 31E0-EOP-1 10-1, Alternate RPV Water Level Control, the Fire System can be usedfor RPV injection by aligning it

___________

The MAXIMUM number of Fire Pumps that can be started is

__________

A. INDIRECTLY into the RHR System via the Condensate Transfer System piping;two (2)

B. INDIRECTLY into the RHR System via the Condensate Transfer System piping;three (3)

C. DIRECTLY into the RHR System piping;two (2)

D. DIRECTLY into the RHR System piping;three (3)

35

36. 295001AK2.01 001

HLT-07 RO NRC EXAM

Unit 2 is operating at 73% power with both Recirc Pumps operating at 70% speed when the2A Recirc Pump trips.

After conditions stabilize, 2B21-R613, Core Plate DpIRx Core Flow, indicates as shown onFigure 1 below:

With NO operator action, which ONE of the choices below completes the following statements?

The flow through the “A” Loop Jet Pumps is depicted in

__________

The % Rated Core flow indicated on Figure 1 for 2B21-R613, Core Plate DpIRx Core Flow,

_________

of actual Core flow.

A. Figure 2;is an accurate indication

B. Figure 2;is NOT an accurate indication

C. Figure 3;is an accurate indication

D. Figure 3;is NOT an accurate indication

CORE PLATE dpIRX CORE FLOW2B21-R613

“A” ,eire Pump 13” Recite Pump

Figure 2Coolant Flow

Direct in,,

“A” Recite Pump “13” Recite Pump

Coolant I low —Direction Figure 3

36

HLT-07 RO NRC EXAM

37. 295003AK1.03 001

Unit 2 is operating at 100% RTP when the following occurs on 4160V Bus 2G:

o Normal Supply Breaker trips OPENo Alternate Supply Breaker automatically CLOSES


The associated Diesel Generator is expected to

__________

Three (3) minutes later, PSW flow to the Turbine Building is expected to

__________

A. remain in standby;have isolated

B. remain in standby;remain in service

C. have automatically started;have isolated

D. have automatically started;remain in service

37

HLT-07 RO NRC EXAM

38. 295004G2.4.11 001

Unit 2 was operating at 100% power.

o A loss of 2R25-S002. 125 VDC Cabinet 2B, occurs

o Subsequently, a malfunction occurs causing 2B31-FO31B, Recirc 2B Discharge Valve,to inadvertently travel full CLOSED

With the above conditions, which ONE of the choices below completes the followingstatements?

As 2B31-FO31B CLOSES, the 2B ASD

_________

A. will perform a ‘Ramp Shutdown” to zero rpm and then the 4160V Input Breaker must bemanually OPENED from the Control Room

B. will perform a “Ramp Shutdown” to zero rpm and then the 4160V Input Breaker will tripOPEN

C. 4160V Input Breaker will remain closed UNTIL it is manually OPENED LOCALLY

D. 4160V Input Breaker will IMMEDIATELY trip OPEN

38

HLT-07 RO NRC EXAM

39. 295005AK3.06 001

Unit 2 was operating at 100% RTP when the following occurred:

o Startup Aux. Transformer (SAT) 2D de-energizedo Reactor scrammedo Main Generator tripped

Which ONE of the choices below describes the expected status of the 4160 VAC Station ServiceBuses 2A and 2B and why? (Assume NO operator actions have been taken).

4160V buses 2A and 2B are

A. de-energized to prevent overloading SAT 2C

B. de-energized to prevent paralleling out of synch power supplies

C. energized from SAT 2C to keep the Main Condenser available

D. energized from SAT 2C to keep forced Core flow available

39


40. 295006AA1.01 001

Unit 2 is in a refueling outage.

o Reactor Mode Switch position REFUELo SRM Shorting Links REMOVED

A SRM detector failure results in the SRM 2A indication reading 5x105 CPS.

What is the expected status of the 2H11-P603 panel WHITE RPS Scram Group A and B lights?

RPS Scram Group A WHITE lights are expected to be

RPS Scram Group B WHITE lights are expected to be

__________

A. EXTINGUISHED;EXTINGUISHED

B. EXTINGUISHED;ILLUMINATED

C. ILLUMINATED;EXTINGUISHED

D. ILLUMINATED;ILLUMINATED

40

HLT-07 RO NRC EXAM

41. 295009AA1.03 001

Unit 1 is operating at 60% RTP with the following conditions:

o “lB” RFPT in service with ‘lA” RFPT on its turning gearo Both Recirculation Pump speeds are 65%

o “lB” RFP trips due to the running Condensate Booster pumps trippingo RWL lowered to -65” before the operator recovered RWL to +35” with HPCI

Which ONE of the choices below describes the FINAL condition of BOTH RecirculationPumps?

A. Running at #1 speed limiter

B. Running at #2 speed limiter

C. Running at #3 speed limiter

D. Tripped

41

42. 295010G2.4.18 001

HLT-07 RO NRC EXAM

The following conditions exist on Unit 2:

o Drywell temperature = 300°Fo Drywell pressure 5 psigo Reactor = shutdown (all rods in)o RPV water level = 32” and steady

GRAPH 8

DR’{WELL SPRAY INITIArJON LIMIT

FMatfl

With the above plant conditions, which ONE of the choices below completes the followingstatements?

If Drywell Sprays are initiated, Primary Containment could

___________

The Unit 2 Primary Containment Design Temperature

__________

been exceeded.

A. fail from exceeding the capacity of the Torus-to-Drywell vacuum breakers;has

B. fail from exceeding the capacity of the Torus-to-Drywell vacuum breakers;has NOT

C. be de-inerted from opening the Reactor Bldg. to Torus vacuum breakers;has

D. be de-inerted from opening the Reactor Bldg. to Torus vacuum breakers;has NOT

OUt)

WSSS raresseesaOOrssa . rsarrarea rsssea4flfl PSFSSSSSA

&c’E_ /Ssarsrs.“. S‘a

,SAFEj

°°rinn

DWTEMP

(°F)

0 10 20 30 40DRY WELL PRESSURE (psig)

42

HLT-07 RO NRC EXAM

43. 295013AK2.01 001

Unit 1 is operating at 90% power.

o A Safety Relief Valve (SRV) inadvertently opened causing Suppression Pool watertemperature to increase

o Suppression Pool water temperature reaches 102°F before operators are able to close theSRV

Which ONE of the choices below describes the required Residual Heat Removal (RHR)Suppression Pool Cooling alignment?

A. Place ONLY one loop of RHR in Suppression Pool cooling, and the RHR heat exchangerIS required to be isolated prior to starting the RHR pump.

B. Place ONLY one loop of RHR in Suppression Pool cooling, and the RHR heat exchangerIS NOT required to be isolated prior to starting the RHR pump.

C. Place ALL available RHR loops in Suppression Pool cooling, and the RHR heat exchangerIS required to be isolated prior to starting the RHR pumps.

D. Place ALL available RHR loops in Suppression Pool cooling, and the RHR heat exchangerIS NOT required to be isolated prior to starting the RHR pumps.

43

HLT-07 RO NRC EXAM

44. 295016AA2.07 001

The control room has been abandoned and 31RS-OPS-OO1-2, Shutdown From Outside ControlRoom, is being implemented.

The SS has ordered Torus Sprays to be placed in service.


Torus pressure can be determined using

Torus Sprays can be initiated from the Remote Shutdown Panel, 2C82-POO1, ONLY in the

A. SPDSintheTSC;“B” Loop

B. SPDSintheTSC;“A” Loop

C. a permanently mounted gauge on the 87’ level of the Reactor Building;“B” Loop

D. a permanently mounted gauge on the 87’ level of the Reactor Building;“A” Loop

44

HLT-07 RO NRC EXAM

45. 295018AK3.06 001

Unit 2 is operating at 5% power when two (2) RBCCW pumps fail and will NOT run.

The following exists:

o PSW/RBCCW Hx dP increaseso The SS directs the SO to LOWER PSW/RBCCW Hx dP to 30 psid by throttling

2P41-F491, PSW Outlet Valve From RBCCW Hx

JAW 34SO-P42-O0l-2, Reactor Building Closed Cooling Water System, which ONE of thefollowing completes these statements?

To LOWER the PSW/RBCCW Hx dP, the SO will throttle 2P41-F491 in the

_________

direction.

The setpoint for 650-23 8, HX PSW/RBCCW DIFF PRESS LOW, is

__________

A. CLOSE;7 psid

B. CLOSE;20 psid

C. OPEN;7 psid

D. OPEN;20 psid

45

HLT-07 RO NRC EXAM

46. 295019AA2.02 001

Unit 2 is operating at 100% power with 2P52-F565, “Rx Bldg Inst N2 To Non-mt Air El 185Isol Vlv’, tagged in the closed position when the following occurs:

o Unit 2 experiences a loss of ALL Unit 2 Station Service Air Compressorso Instrument and Service Air pressure drops to zero (0) psig

Which ONE of the choices below completes BOTH statements for the following ventilationdampers as their respective air pressure decreases to zero (0) psig?

2T46-FOO1A, SBGT A Fltr Inlet From Rx Bldg, valve will

__________

2T41-F044A, Rx Bldg Inboard Isol Dmprs Inaccessible Areas Exhaust Fans Disch, valvewill

_______

A. travel open;remain open

B. travel open;travel closed

C. remain closed;remain open

D. remain closed;travel closed

46

HLT-07 RO NRC EXAM

47. 295020AK1.05 001

Unit 2 is operating at 100% power.

o Nitrogen (N2) is being added to the Unit 2 Drywell (DW) from the Unit 1 N2 Storage Tank

34SO-T48-O022, “Containment Atmosphere Control and Dilution System” section 7.3.1,‘Alternate Primary Containment Nitrogen Makeup From CAD loop A, Unit 1 or Unit 2 N2Storage Tank” is being used to add the N2.

o 2T48-F1 13, “Nitrogen to DW isolation valve” is OPENo 2T48-F1 14, “Nitrogen to DW isolation valve” is OPENo DW venting using Standby Gas Treatment is in progresso A fault in 2C71-P001, “RPS Power Dist Panel” results in a loss of the’2A” Reactor

Protection System (RPS) buso It will take 8 hours to restore the “2A” RPS bus

If the operator stationed at the 2H1 1-P657 panel does NOT take any action, which ONE of thefollowing describes the operational implications for the DW?

A. N2 addition to the DW will continue and a loss of DW cooling will eventually occur due tohigh DW pressure.

B. N2 addition to the DW will continue and DW cooling will remain in operation indefinitely.

C. N2 addition to the DW will automatically isolate and DW cooling will remain in operationindefinitely.

D. N2 addition to the DW will automatically isolate and a simultaneous loss of DW coolingwill occur.

47

HLT-07 RO NRC EXAM

48. 295021G2.2.40 001

Unit 2 is shutdown.

BOTH Loops of RHR are operating in Parallel Shutdown Cooling (SDC) operation.

The following conditons exist:

o Rx pressure 34 psigo BOTH Rx Recirculation pumps Offo “2C” RHR pump Danger Tagged out of serviceo “2D” RHR pump Danger Tagged out of service

Subsequently, an equipment malfunction causes 2E1 1-FOO6B, Shutdown Cooling Vlv, toCLOSE and CANNOT be reopened.


JAW Tech Spec LCO 3.4.7, ‘Residual Heat Removal (RHR) Shutdown Cooling System -Hot Shutdown”, the MINiMUM number of REQUIRED RHR SDC Subsystems

With 2E1 l-FOO6B closed, the “2B” RHR pump will

__________

A. is met;trip

B. is met;continue to run

C. is NOT met;trip

D. is NOT met;continue to run

48

HLT-07 RO NRC EXAM

49. 295023AA1.04 001

A refueling accident occurs on Unit 2.

The following Area Radiation Monitors (ARM) red Trip Lights illuminate at Control RoomARM Panel 2D21-P600:

o 2D21-K6O1A, Reactor head laydown areao 2D21-K6O1M, Spent Fuel Pool & New Storage

Which ONE of the following predicts how the Main Control Room Environmental Control(MCREC) system is affected and operation of the ARMs?

With the above conditions, the MCREC system will

___________

After mitigating actions are completed AND the above ARMs are indicating below theirTrip setpoints, the ARM red TRIP lights

___________

reset.

A. remain in the Normal Mode;must be manually

B. remain in the Normal Mode;will automatically

C. align to the Pressurization Mode;must be manually

D. align to the Pressurization Mode;will automatically

49

HLT-07 RO NRC EXAM

50. 295024EA2.06 001

A steam line break inside containment has occurred on Unit 2.

o Drywell pressure is 10.5 psig and slowly increasingo Torus pressure is 10 psig and slowly increasingo Neither Drywell or Torus sprays have been initiated

Which ONE of the following describes the effect of the steam line break on Torus watertemperature and requires Primary Containment sprays with these conditions?

The Torus water temperature will heat up

With the above conditions and at this time, Sprays are REQUIRED to be placedin service.

A. uniformly throughout the Torus due to the design of the downcomers;

BOTH Drywell and Torus

B. uniformly throughout the Torus due to the design of the downcomers;

ONLY Torus

C. directly under the area of the DW leak due to the energy being distributed directly to theTorus water in that area;

BOTH Drywell and Torus

D. directly under the area of the DW leak due to the energy being distributed directly to theTorus water in that area;

ONLY Torus

50

HLT-07 RO NRC EXAM

51. 295025G2.1.27 001


JAW TS 3.4.3. Safety/Relief Valves (SIRVs), the SRV Safety function requires aMINIMUM of

__________

SRVs to be operable.

if reactor pressure reaches 1200 psig, the Reactor Coolant System DESIGN pressure

__________

have been exceeded.

A. 10;will

B. 10;will NOT

C.5;will

D.5;will NOT

51

HLT-07 RO NRC EXAM

52. 295026EK3.04 001

An ATWS is in progress on Unit 2 with 31E0-EOP-01 1-2, RCA RPV Control (ATWS),flowchart in progress.


JAW EOP definitions the reason SBLC is injected before exceeding the B11T Curve(Graph 5) is to ensure that Hot Shutdown Boron Weight is injected before exceeding the

At 10% RTP, the LOWEST listed Torus temperature at which the BuT Curve (Graph 5)will be EXCEEDED is

________

Reference Provided

A. Primary Containment Pressure Limit;120°F

B. Primary Containment Pressure Limit;125°F;

C. Heat Capacity Temperature Limit;120°F

D. Heat Capacity Temperature Limit;125°F;

52

HLT-07 RO NRC EXAM

53. 295028EA1.03 001

Unit 2 was at 100% power when a Steam Line break occurred inside the Drywell (DW).

The following conditions now exist:

o Drywell Pressure 8 psigo Bulk Average Drywell Temperature 265°F


JAW 3 1EO-EOP- 100-2, Miscellaneous Emergency Overrides’, the”2A” DW Chiller

A. is NOT allowed to be restarted, because this DW temperature is above the allowed windingtemperature for restart of the DW Cooling Fan Motors

B. is NOT allowed to be restarted, because at this DW temperature the potential for a rupture inthe DW coolers exist

C. is allowed to be restarted. The operator must first place the LOCA override switch to“BYPASS” and then reset the 86 Lockout relay at the DW Chiller breaker

D. is allowed to be restarted. The operator must first reset the 86 Lockout relay at the DWChiller breaker and then place the LOCA override switch to “BYPASS”

53

HLT-07 RO NRC EXAM

54. 295030EK1.02 001

Unit 2 is operating at 100% power when a Loss of Coolant Accident occurs.

The High Pressure Coolant Injection (HPCI) system is being used to control RPV water level.

o HPCI flow rate 4,000 gpmo RWL -60’ and increasing at 20” per minuteo Torus level 135 incheso Torus temperature 190°Fo Torus Pressure 4psig

With the above conditions, SELECT the HIGHEST listed flowrate that maintains HPCIoperation in the ACCEPTABLE Region of the HPCI NPSH limits?

Reference Provided

A. 3,750 gpm

B. 3,250 gpm

C. 2,750 gpm

D. 2,250 gpm

54

HLT-07 RO NRC EXAM

55. 295031EA1.02 001

Unit 2 was operating at 100% power, when an event occurred resulting in the following:

o Reactor water level: -45” (lowest level reached) and increasing 45 inches/minuteo Reactor pressure: 900 psig and slowly decreasingo Drywell pressure: 0.8 psig and steadyo Both CRD pumps tripped and can NOT be started


Based on these conditions, with NO additional operator actions, one (1) minute laterONLY

__________

will have indication of flow to the reactor vessel.

A. HPCI and RCIC

B. the Reactor Feedpumps

C. HPCI, RCIC and the Reactor Feedpumps

D. RCIC and the Reactor Feedpumps

55

HLT-07 RO NRC EXAM

56. 295032EA1.05 001

Following a transient on Unit 2, current plant conditions are:

o Reactor water level is -20 inches, rising 5 inches/minuteo Reactor pressure is 750 psig, slowly lowering

Subsequently the following conditions occur:

o RCIC Room Area Cooler Temperature is 160°Fo HPCI Room Area Cooler Temperature is 175°Fo RCIC is injecting at 400 gpmo HPCI is injecting at 600 gpm


With the above conditions,

__________

REQUIRED to be MANUALLY isolated.

A. ONLY the HPCI System is

B. ONLY the RCIC System is

C. BOTH HPCI and RCIC Systems are

D. NEITHER HPCI nor RCIC Systems are

56

HLT-07 RO NRC EXAM

57. 295035EA2.02 001

Unit 2 is operating at 100% power with the following:

o 2T41C001A, “Rx. Bldg Supply Fan,” in service with 5,300 cfm flowo 2T41-COO7A, “Rx Bldg Vent Exhaust Fan,” in service with 6,500 cfm flowo 2T41-COO7B, “Rx Bldg Vent Exhaust Fan,” is tagged out

Subsequently, 2T41-COO7A, “Rx Bldg Vent Exhaust Fan,” Trips.

With NO operator action, which ONE of the choices below completes the following statements?

After 2T4l-COO7A trips, the Rx. Bldg SUPPLY Fan flow will

__________

After 2T41C007A trips, the Offsite release rate from the Rx. Bldg Stack will

__________

A. remain at 5,300 cfm;decrease to zero (0) cpm because NO Exhaust fans are discharging to the Rx. Bldg. Stack

B. remain at 5,300 cfm;decrease but remain greater than zero (0) cpm since some Exhaust fans are still dischargingto the Rx. Bldg. Stack

C. decrease to zero (0) cfm;decrease to zero (0) cpm because NO Exhaust fans are discharging to the Rx. Bldg. Stack

D. decrease to zero (0) cfm;decrease but remain greater than zero (0) cpm since some Exhaust fans are still dischargingto the Rx. Bldg. Stack

57

HLT-07 RO NRC EXAM

58. 295037EK2.01 001

Unit 2 was at 84% RTP when it is discovered that the Alternate Rod Insertion (ART) Systemwill NOT perform its intended function.

Subsequently, an auto-scram signal was received.

The OATC inserted a manual scram and performed RC- 1.

The following conditions currently exist:

o Reactor power is 35% RTPo The 8 white RPS Scram Group lights on 2H1 l-P603 are illuminatedo Full core display blue lights are ALL extinguished

With the above conditions and JAW 31E0-EOP-103-2, EOP Control Rod Insertion Methods,INDEPENDENTLY EVALUATE each of the following control rod insertion methods todetermine if they will be an effective method for control rod insertion?

Placing the RPS Test Trip Logic Switches to TRIP

_________

be effective.

Venting the Scram Air Header be effective.

A. will;will

B. will;will NOT

C. will NOT;will

D. will NOT;will NOT

58

HLT-07 RO NRC EXAM

59. 295038EK1.02 001

An event has ocurred at Plant Hatch with a potential radiation release to the public.


The NPO will determine Projected Offsite dose using

If an emergency is declared due to the high Offsite release rate, the INITIAL emergencynotification to State and Local Officials is REQUIRED within a MAXIMUM of

___________

from when the emergency is declared.

A. 73EP-EIP-015-O, Offsite Dose Assessment;15 minutes

B. 73EP-EIP-O 15-0, Offsite Dose Assessment;30 minutes

C. 73EP-EIP-018-0, Prompt Offsite Dose Assessment;15 minutes

D. 73EP-EIP-018-0, Prompt Offsite Dose Assessment;30 minutes

59

HLT-07 RO NRC EXAM

60. 300000K 1.02 001

Unit 2 is at 100% power with the following conditions:

o A Service Air Header break has occuredo The break is greater than the capacity of the Service Air Compressors

Which ONE of the choices below completes the following statements as Service Air pressuredecreases?

The isolation setpoint for 2P51-F017, Turbine Building Service Air Isolation Valve,is

______________

If 2P51-F017 fails to isolate, CRD Flow Control Valves, 2C11-FOO2A & B

_________

losepneumatic supply.

A. 70 psig;will

B. 70 psig;will NOT

C. 50 psig;will

D. 50 psig;will NOT

60

HLT-07 RO NRC EXAM

61. 300000K6.04 001

Unit 2 is operating at 100% RTP with the 2P51-CO01C, Station Service Air Compressor(SSAC), in service and 2P51-COO1B, SSAC, in the Automatic Mode.

o 2P51-COOIC, SSAC, trips.

If NO operator action is taken, which ONE of the choices below completes the followingstatements?

The setpoint at which 2P51-COO1B, SSAC, will Automatically Start & Load is

________

If the 2P51-COO1B, SSAC fails to Start & Load, the Outboard MSIVs (2B21-F028A-D),are expected to

__________

A. 100 psig;remain open

B. 100 psig;drift closed

C. 107 psig;remain open

D. 107 psig;drift closed

61

HLT-07 RO NRC EXAM

62. 400000K2.02 001

Unit 1 is at 100% power when the following annunciators alarm:

o 600V BUS 1D BREAKER TRIPPED, 652-318o 600V BUS 1D UNDERVOLTAGE, 652-323

Which ONE of the following lists two components that have lost power?

A. RBCCW Pump A;RBCCW Drywell Outlet Isolation Valve, 1P42-F052

B. RBCCWPumpA;RWCU Inboard Suction Isolation Valve, 1G31-F001

C. RBCCWPumpB;RBCCW Drywell Outlet Isolation Valve, 1 P42-F052

D. RBCCWPumpB;RWCU Inboard Suction Isolation Valve, 1G3 1-FOOl

62

HLT-07 RO NRC EXAM

63. 500000EK3.07 001

Unit 1 has experienced an accident that results in these Primary Containment parameters:

o Hydrogen concentration .... 8%o Oxygen concentration 7%o Drywell (DW) pressure .... 14 psig and slowly increasingo Torus level >300 inches

With the above conditions and JAW 31E0-PCG-001-1, “Primary Containment Gas Control”chart, which ONE of the choices below completes the following statements?

The operator is required to vent the

___________

the containment atmosphere.

Placing Torus Sprays in service

__________

allowed.

A. DW to reduce the flammability of;is

B. DW to reduce the flammability of;is NOT

C. Torus to reduce the flammability and scrub;is

D. Torus to reduce the flammability and scrub;is NOT

63

HLT-07 RO NRC EXAM

64. 600000AK1.02 001

A fire is reported on Unit 1, in the “lB’ Diesel Generator Room.

Which ONE of the choices below is the fire suppression system that is in this room?

A. Automatically actuated Carbon Dioxide System with a manual backup

B. Automatically actuated Halon System with a manual backup

C. ONLY a manually actuated Carbon Dioxide System

D. ONLY a manually actuated Halon System

64

HLT-07 RO NRC EXAM

65. 700000AK2.07 001

BOTH units are operating at 100% power.

The Northern Control Center has notified the control room crews that 230 KV Bus voltagecannot be maintained above the normal minimum voltage.

Current 4160VAC Emergency Bus voltages are 3800 VAC.


To RAISE reactive load (VARS) from the HMI Screen, the operator will select

__________

lAW 34AB-S 11-001-0, Operation With Degraded System Voltage, if after 30 minutes the4160VAC Emergency Bus voltages have not changed, a TOTAL of__________ 4160VACEmergency Buses will be transferred to their respective Diesel Generator.

A. EX2100 then REGULATOR ADJUST and depress RAISE;two (2)

B. EX2 100 then REGULATOR ADJUST and depress RAISE;four (4)

C. PSI-LOAD then LOAD SET and depress RAISE;two (2)

D. PSI-LOAD then LOAD SET and depress RAISE;four (4)

65

HLT-07 RO NRC EXAM

66. G2.1.2 001

Unit 2 experiences a Loss of ALL High pressure feed.

o LPCI and Core Spray (CS) automatically initiateo RWL is being controlled by the OATC using LPCI and CS

RWL is recovered to its normal band and the OATC is ready to depress the auto initiation signalreset pushbutton for RHR.

JAW 31G0-OPS-021-O, Manipulation Of Controls And Equipment, which ONE of the choicesbelow completes the following statement?

The

___________

does NOT have the AUTHORiTY to procedurally authorize resetting theLPCI initiation signal under these conditions.

NOTE: Operator At The Controls = OATC; Balance Of Plant = BOP

A. Shift Manager

B. OATConUnit2

C. BOP NPO on Unit 2

D. Extra NPO on Unit 2

66

HLT-07 RO NRC EXAM

67. G2.1.21 001

Southern Nuclear Operating Company

‘SOUTHERN Management Conduct of Operations Version 8.0

Nuclear I

I NMP-OS-007COMPANY Procedure Page 1 of 51Peer Team ChampionlProcedure Owner: David R,Vineyard! Fleet Operations Manager! Corporate

(Print: Name / Title I Site)

Original Signed by David Vineyard(Peer Team Champion/Procedure Owner’s Approval Signature)

/ 12/08/2011(Approval Date)

Effective Dates:

CATEGORY SECTIONSContinuous: NONEReference: NONEInformation: ALL

Based on the above cover sheet, which ONE of the choices below completes the followingstatements?

JAW NMP-AP-001, Development and Control of Southern Nuclear Procedures, on12/10/2011 this version of NMP-OS-007

_________

the CORRECT version to be used byOperations.

For the indicated PROCEDURE LEVEL OF USE, placekeeping is

__________

A. was;required

B. was;allowed, but NOT required

C. was NOT;required

D. was NOT;allowed, but NOT required

Approved By:

NACorporate

12/14/2011FNP

12/14/2011HNP

PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP..003

12/14/2011VEOP

67

HLT-07 RO NRC EXAM

68. G2.1.6 001

Which ONE of the following identifies the required communication protocol during transientsJAW DI-OPS-59-896, Operations Management Expectations, Attachment 5, Strategies ForSuccessful Transient Mitigation?

An annunciator check

___________

required prior to the SS giving a crew brief.

If during a Crew Brief, alarms 603-205 & 603-206, Reactor Vessel Level 2 Div I & Div IITrip, are received, the NPO

__________

expected to call a Time Out.

A. is;is

B. is;is NOT

C. is NOT;is

D. is NOT;is NOT

68

HLT-07 RO NRC EXAM

69. G2.2.23 001

Which ONE of the choices below identifies a Unit 1 Tech Spec LCO condition that will requireentry into a Required Action Statement (RAS)? (NOT A TRACKING RAS)

A. Torus water level is 149.5 inches in Mode 1.

B. RCIC is mop in Mode 3 with reactor steam dome pressure at 100 psig.

C. Reactor steam dome pressure is 1052 psig in Mode 1.

D. Drywell pressure is 1.80 psig in Mode 2.

69

HLT-07 RO NRC EXAM

70. G2.2.37 001

An event has occurred on Unit 2 requiring entry into 31 EO-EOP- 113-2, Terminating AndPreventing Injection Into The RPV.

JAW step 3.1.1.1, HPCI is OFF with 2E41-C002-3, HPCI Aux Oil pump, in thePULL-TO-LOCK position.

Which ONE of the choices below completes the following statement concerning HPCIoperability and Turbine Control Valve position?

lAW Tech Spec 3.5.1, HPCI is considered

__________

A. operable and the Turbine Control Valve will be fully closed

B. operable and the Turbine Control Valve will be fully open

C. inoperable and the Turbine Control Valve will be fully closed

D. inoperable and the Turbine Control Valve will be fully open

70

HLT-07 RO NRC EXAM

71. G2.2.44 001

Unit 1 RHR Loop B has been placed in the Shutdown Cooling (SDC) Mode of operation withthe following pump alignment:

RHR Pump lB Running in SDC ModeRHRSW Pump lB .... Running

The following alarms/conditions are received:

(601-3 14) RHR SYSTEM I ACTIVATED(60 1-234) RHR SYSTEM IT ACTIVATEDReactor Water level is -120 inches

lAW 34S0-E1 1-010-1, Residual Heat Removal System, which ONE of the choices belowcompletes the following statements concerning the status of RHR Loop B Suction Valves?

With the above conditions, 1E1 1-FOO6B, Shutdown Cooling Vlv,

__________

After 1E11-FOO6B is closed, the operator will

___________

A. must be manually CLOSED;verify 1E1 1-FOO4B, Torus Suction Vlv, has automatically opened

B. must be manually CLOSED;manually open 1E1 l-FOO4B, Torus Suction Vlv

C. will automatically CLOSE;verify 1E1 1-FOO4B, Torus Suction Vlv, has automatically opened

D. will automatically CLOSE;manually open 1E1 l-FOO4B, Torus Suction Vlv

71

HLT-07 RO NRC EXAM

72. G2.3.13 001

An INiTIAL Drywell (DW) entry is required on Unit 1.

With Unit 1 at 8% RTP, which ONE of the choices below completes the following statementsJAW 31G0-OPS-005-O, Primary Containment Entry?

The MAXIMUM reactor power allowed for this type of DW entry (INITIAL) is

________

A Two (2) man Backup Team

___________

required to be in place for this entry.

A. lO%RTP;is

B. lO%RTP;is NOT

C. 15%RTP;is

D. 15%RTP;is NOT

72

HLT-07 RO NRC EXAM

73. G2.3.14 001

Unit 1 was at 35% power when the Hydrogen Injection System was placed in service inAUTOMATIC - EXTERNAL mode JAW 34S0-P73-001-1, “Hydrogen and Oxygen injectionand Control for HWC” section 7.1.2, Placing 1P73-R025, Hydrogen Controller, inEXTERNAL.’

o Power is raised from 35% power to 100% powero At 100% power hydrogen flow rate indicates 40 SCFM

Which ONE of the following answers both of these statements?

lAW 34S0-P73-001-l, “Hydrogen and Oxygen injection and Control for HWC”, hydrogeninjection flow rate is

___________

the normal 100% power flow rate.

Main Steam Line radiation levels in the Steam Chase will stabilize

___________

the expectednormal full power background radiation levels estabilished JAW 34GO-OPS-001-1, PlantStartup.

A. above;at

B. above;above

C. below;at

D. below;below

73

HLT-07 RO NRC EXAM

74. G2.4.26 001

Which ONE of the choices below completes the following statements concerning a fire in theService Building Document Storage Room?

The Service Building Document Storage Room is equipped with a

__________

fire suppression system.

JAW 3OAC-OPS-003-O, Plant Operations, a MINIMUM of Fire BrigadeMembers must be onsite to respond to this fire.

A. Halon;five (5)

B. Halon;three (3)

C. CO2;five (5)

D. CO2;

three (3)

74

HLT-07 RO NRC EXAM

75. G2.4.32 001

Unit 2 was operating at 100% RTP when a loss of electrical power results in a loss of asignificant number of Main Control Room annuciators and a reactor scram.

An ALERT Emergency classification is declared.


The LATEST time from the ALERT declaration that the INITIAL Plant Page Announcementcan be made and still meet the requirements of NMP-EP-111-002, Emergency NotificationNetwork Communicator Instructions - Hatch, is

_________

Without additional direction from the Emergency Director, the operator is REQUIRED tomake

_________

A. 15 minutes;the INITIAL Plant Page Announcement, followed by a repeat Plant Page Announcementapproximately 30 minutes later

B. 15 minutes;ONLY the Initial Plant Page Announcement

C. 30 minutes;the INITIAL Plant Page Announcement, followed by a repeat Plant Page Announcementapproximately 30 minutes later

D. 30 minutes;ONLY the Initial Plant Page Announcement

End of test 75

NRC RO REFERENCES

RO EXAM

1. Unit 2 EOP Graph 5, BuT Curve

2. Unit 2 EOP Graph 17A, HPCI Pump NPSH Limit, (Torus Water Level At or Above 146”)

3. Unit 2 EOP Graph 17B, HPCI Pump NPSH Limit, (Torus Water Level Below 146”)

BO

RO

NIN

JEC

TIO

NIN

ITIA

TIO

NT

EM

PE

RA

TU

RE

UN

IT2

170

160

TO

RU

S150

WA

TE

RT

EM

P140

(°F)

130

120

110

100

f%

.://

Z/4

,/

//‘;‘/)

///y4

/\f/

//

/•/.

‘/.7

/7

//

t//

7/7

/

240-

230-

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(°F)

210-

200-

190-

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ergencyD

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Belo

w10

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*

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w5

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180-

170-I

0500

10001500

20002500

30003500

40004500

5000

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(gpm)

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230-

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ergencyD

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placeofthis

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uppressionC

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U

HLT-07 RO NRC EXAMAnswers

# ID 01 201001K1.11 I D2 202001A1.02 I D3 202002K3.03 I C4 203000G2.4.34 I C5 204000K4.O1 1 C6 205000K5.02 1 A7 206000K5.06 I C8 209001K1.12 I D9 209001K5.O1 1 C10 211000K4.021 Dii 212000A2.08 I B12 212000K3.03 1 D13 215002K6.04 I B14 215003A1.06 I B15 215004K6.02 I D16 215005A1.O1 I D17 215005A4.03 I D18 216000A4.01 1 A19 217000K2.04 I C20 218000KI.04 I B21 223001A3.04 1 C22 223002K3.10 1 A23 233000K2.02 I B24 234000K5.02 I D25 239002A3.02 1 C26 241000A2.23 I D27 259002A4.07 I D28 261000A1.01 1 C29 261000K3.02 I D30 262001G2.4.47 I A31 262002A3.01 I B32 263000A2.02 I A33 264000K4.06 I A34 268000A4.01 1 B35 286000G2.4.9 I A36 295001AK2.01 1 C37 295003AK1.03 1 D38 295004G2A.1l I C39 295005AK3.06 1 A40 295006AA1.01 I A41 295009AA1.03 1 D42 295010G24.18 I D43 295013AK2.01 I D44 295016AA2.07 1 A45 295018AK3.06 1 C46 295019AA2.02 1 B47 295020AK1.05 1 A

AnswersID 0

48 295021G2.2.40 I C49 295023AA104 I C50 295024EA2.06 1 B51 295025G2.1.27 1 B52 295026EK3.04 1 D53 295028EA1.03 I B54 295030EK1.02 I C55 295031EA1.02 1 C56 295032EA1.05 I A57 295035EA2.02 1 D58 295037EK2.01 I A59 295038EK1.02 1 C60 300000K1.02 I B61 300000K6.04 I A62 400000K2.02 I C63 500000EK3.07 1 B64 600000AK1.02 1 A65 700000AK2.07 I A66 G2.1.21 B67 G2.1.21 I D68 G2.1.6 1 A69 G2.2.23 1 D70 G2.2.37 1 C71 G2.2.44 I B72 G2.3.13 I A73 G2.3.14 I B74 G2.4.26 1 A75 G2.4.32 I ASECTION 1 (75 items) 75.00

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1.201001K1.11001 - 2H1 1-P603: o Cooling Water dP 0 psid o ... · 2H1 1-P603: o Charging Water Pressure 1480 psig o Cooling Water dP 0 psid o Drive Water dP Upscale o Drive Water