ML110760683

Initial Exam 2011-301 Final RO Written Exam with References

ML110760683
Person / Time
Site:	Browns Ferry
Issue date:	03/17/2011
From:	NRC/RGN-II/DRS/OLB
To:	Tennessee Valley Authority
References
50-259/11-301, 50-260/11-301, 50-296/11-301
Download: ML110760683 (82)

Text

ILT 1102 Written Exam Unit I is at 100% Reactor Power AND Core Flow is 92%. A trip of IA Recirc Pump results in Operation in Region II of the Core Power to Flow Map.

Which ONE of the following completes the statement below?

The required action(s) in accordance with 1-AOl-68-IA, Recirc Pump Trip I Core Flow Decrease, is (are) to IMMEDIATELY A. insert a Manual Reactor Scram B. raise Core Flow until Region II of the Power to Flow Map is exited C. insert Control Rods until Region II of the Power to Flow Map is exited D. insert Control Rods until Load Line is < 95.2%; then, raise Core Flow to > 45%

I

ILT 1102 Written Exam

2. A leak in the Unit I Drywell results in the following conditions:

• Drywell Temperature is 1700 F and rising

• A Lockout occurs on 4kV Shutdown Board C

• Reactor Level is (i-) 10 inches and stable

• Suppression Pool Level is 15 feet Which ONE of the following completes the statements below?

In accordance with 1-EOI-2, Primary Containment Control, Drywell Spray must be initiated before MAXIMUM Drywell Temperature of _(1). Assuming no manual electric board transfers are performed, RHR _(2)_ is (are) available for Drywell Spray from the control room.

A. (1)200°F (2) Loop I ONLY B. (1)200°F (2) Loop I AND Loop II C. (1)280°F (2) Loop I ONLY D. (1)280°F (2) Loop I AND Loop II 2

ILT 1102 Written Exam

3. Unit 2 was operating at 100% Reactor Power.

A ground AND subsequent fire in Shutdown Board 250V DC Distribution Panel SB-B resulted in de-energization of the SB-B panel AND trip of 4kV Shutdown Board B Normal Feeder Breaker.

Which ONE of the following completes the statements below?

480V Shutdown Board 2B is _(1)_.

4kV Shutdown Board B _(2) automatically transfer to its alternate source.

A. (1) energized (2) will B. (1) de-energized (2) will C. (1)energized (2) will NOT D. (1) de-energized (2) will NOT 3

ILT 1102 Written Exam

4. Given the following conditions:

• Unit 3 is operating at 20% Reactor Power

• A pipe rupture results in loss of ALL EHC with the Main Turbine online Which ONE of the following completes the statements below?

Reactor Pressure will _(1).

An automatic scram (2)_ occur.

A. (1) rise (2) will B. (1) lower (2) will C. (1) rise (2) will NOT D. (1) lower (2) will NOT 4

ILT 1102 Written Exam

5. Given the following:

• Unit2inMode2

• Intermediate Range Monitors (IRMs) indicate 29.1 on Range 3

• Reactor Period is 90 seconds.

Which ONE of the following identifies approximately how long it will take to reach the IRM Scram setpoint?

A. 35 seconds B. 65 seconds C. 125 seconds D. 180 seconds 5

ILT 1102 Written Exam

6. Which ONE of the following functions can be performed at Backup Control Panel 2-25-32?

A. Close ALL MSIVs B. Operate ALL ADS Valves C. Suppression Chamber Spray D. Control Reactor Level with HPCI 6

ILT 1102 Written Exam

7. Unit 3 is operating at 100% Reactor Power when the foHowing alarms AND indications are received:

• A Partial Loss of Reactor Building Closed Loop Cooling Water occurs.

• RWCU NON-REGENERATIVE HX DISCH TEMP HIGH, (3-9-4B, Window 17) is in alarm.

• RWCU Non- Regenerative Heat Exchanger Discharge Temperature is 140° F.

Which ONE of the following completes the statement below?

The Reactor Water Cleanup (RWCU) Pumps will receive a DIRECT TRIP input from A. either the isolation valve position or the non-Regenerative Heat Exchanger high temperature signal B. either the isolation valve position or a low flow condition after 30 seconds C. the non-Regenerative Heat Exchanger high temperature signal ONLY D. a low flow condition after 30 seconds ONLY 7

ILT 1102 Written Exam

8. Control Air Header Pressure is lowering due to a rupture in the system.

Which ONE of the following identifies the HIGHEST Control Air Pressure that will result in Service Air Isolation Valve, 0-FCV-33-1, closing AND the reason?

A. 30 psig; To isolate non-essential Service Air loads.

B. 30 psig; Due to insufficient air pressure to keep the valve open.

C. 50 psig; To isolate non-essential Service Air loads.

D. 50 psig; Due to insufficient air pressure to keep the valve open.

8

ILT 1102 Written Exam

9. Unit 3 is in Mode 4 with the following conditions:

• Reactor Level band is (+) 78 inches to support testing.

• ALL Reactor Recirc AND RWCU Pumps are isolated and tagged out.

• RHR Loop I in Shutdown Cooling experiences an inadvertent Group 2 Isolation AND can NOT be restored.

Which ONE of the following completes the statements below?

Accurate Reactor Water Temperature (1)_ available.

If Reactor Coolant Stratification occurs, it is indicated by _(2).

A. (1)is (2) a MINIMUM differential temperature of 50°F or greater between Reactor Vessel Bottom Head AND any Reactor Vessel Feedwater Nozzle B. (1)is NOT (2) a MINIMUM differential temperature of 50°F or greater between Reactor Vessel Bottom Head AND any Reactor Vessel Feedwater Nozzle C. (1)is (2) a MINIMUM differential temperature of 75°F or greater between Reactor Vessel Bottom Head AND any Reactor Vessel Feedwater Nozzle D. (1)isNOT (2) a MINIMUM differential temperature of 75°F or greater between Reactor Vessel Bottom Head AND any Reactor Vessel Feedwater Nozzle 9

ILT 1102 Written Exam

10. Unit I is in a Refueling Outage. The Refueling SRO reports that an IRRADIATED fuel assembly has been seated in the WRONG location in the core. The grapple remains engaged on the bundle.

The following conditions are then noted:

• Rising count rates on SRMs

• SRM Period lights illuminated

• Rising dose rates on the Refuel Floor Which ONE of the following describes an IMMEDIATE Operator action in accordance with Refueling AOls?

A. Verify Secondary Containment is intact.

B. Raise the fuel bundle from the core location.

C. If any CRD Pump is in service stop the CRD Pump.

D. If SLC is operable place SLC PUMP lA/i B, 1-HS-63-6A control switch in START A OR START B.

10

ILT 1102 Written Exam

11. Unit 2 was at 100% Reactor Power when a spurious Group I Isolation occurred. The pressure transient caused a small-break LOCA to occur inside the Drywell.

Which ONE of the following describes the basis for actions with respect to 12 psig Suppression Chamber Pressure?

A. Drywell sprays must be initiated prior to this pressure to prevent opening the Suppression Chamber to Reactor Building vacuum breakers AND de-inerting the containment.

B. Drywell sprays must be initiated above this pressure because almost ALL of the nitrogen AND other non-condensable gases in the drywell have been transferred to the torus AND chugging is possible.

C. Above this pressure indicates that almost ALL of the nitrogen AND other non-condensable gases in the torus have been transferred to the drywell air space AND Suppression Chamber Sprays will be ineffective.

D. Above this pressure indicates that almost ALL of the nitrogen AND other non-condensable gases in the drywell have been transferred to the torus so initiating Drywell Sprays may result in containment failure.

11

ILT 1102 Written Exam

12. Unit I HPCI is in operation in Pressure Control Mode per l-EOI Appendix 11C, ALTERNATE RPV PRESSURE CONTROL SYSTEMS HPCI TEST MODE

• Reactor Pressure is 1050 psig

• 1-FIC-73-33, HPCI SYSTEM FLOW/CONTROL, is in Automatic Which ONE of the following completes the statement below?

To lower Reactor Pressure, the operator is required to use _(1) AND (2)_ in accordance with 1-EOI Appendix 11C.

A. (1) 1-FCV-73-36, HPCI/RCIC CST TEST VLV, (2) throttle it in the CLOSE direction B. (1) 1-FCV-73-36, HPCI/RCIC CST TEST VLV, (2) throttle it in the OPEN direction C. (1) 1-FIC-73-33, HPCI SYSTEM FLOW/CONTROL, (2) LOWER the setpoint D. (1) 1-FIC-73-33, HPCI SYSTEM FLOW/CONTROL, (2) RAISE the setpoint 12

ILT 1102 Written Exam

13. Unit 2 has experienced a LOCA AND the following conditions exist:

• Suppression Chamber Pressure is 5 psig

• Suppression Pool level is 14.5 feet

• Drywell Pressure is 7.5 psig

• Suppression Pool Temperature is 205° F

• BOTH RHR Loop I Pumps are in Suppression Chamber I Drywell Spray with Loop flow of 11,500 gpm

• Core Spray Pump 2A flow is 4000 gpm

• RHR Pump 2B flow is 10500 gpm

• NO other ECCS Pumps are running Based on the above conditions, which ONE of the following identifies the ECCS Pump(s) that has (have) sufficient NPSH for continued operation?

[REFERENCE PROVIDED]

A. Core Spray Pump 2A ONLY B. RHRPump52AAND2CONLY C. RHR Pumps 2A, 2B AND 2C ONLY D. Core Spray Pump 2A AND RHR Loop I Pumps 13

ILT 1102 Written Exam

14. Given the following Unit 2 plant conditions:

• Reactor pressure is being maintained at 50 psig

• Temperature near the water level instrument run in the Drywell is 2200 F

• The Shutdown Vessel Flooding Range Instrument (2-Ll-3-55) is reading (+) 35 inches Which ONE of the following is the HIGHEST Drywel) Run Temperature at which the 2-Ll-3-55 reading (+) 35 inches is considered valid?

[REFERENCE PROVIDED]

A 200°F B 250°F C 270°F D. 300° F 14

ILT 1102 Written Exam

15. Unit 3 was at 100% Reactor Power when a leak from the Torus resulted in Suppression Pool Level of 11.4 feet. Required actions of the EOls have been performed.

Which ONE of the following completes the statement below?

Two minutes after initiating required EOl actions, Wide Range Reactor Pressure Indication(s) available on Control Room Panel(s) _(1) will be _(2)_.

A. (1)3-9-5 ONLY (2) stable B. (1)3-9-5 ONLY (2) lowering C. (1) 3-9-3 AND 3-9-5 (2) stable D. (1) 3-9-3 AND 3-9-5 (2) lowering 15

ILT 1102 Written Exam

16. Given the following Unit 1 plant conditions:

• HPCI 12OVAC POWER FAILURE, (1-9-3F, Window 7) is in alarm

• Reactor Water Level is (-) 122 inches and lowering

• Drywell Pressure is 1.8 psig and steady

• Assume NO operator action Which ONEof the following completes the statements below?

ADS will automatically initiate in _(1). This actuation is in response to a LOCA _(2).

A. (1) 265 seconds (2) inside the Drywell B. (1)360 seconds (2) inside the Drywell C. (1)265 seconds (2) outside the Drywell D. (1)360 seconds (2) outside the Drywell 16

ILT 1102 Written Exam

17. An ATWS has occurred on Unit 1 with the following time line AND conditions:

• At 1200 Reactor Power is 15%

• At 1210 SLC is initiated

• At 1235 SLC Storage Tank Level is 67%

• At 1300 SLC Storage Tank Level is 43%

Which ONE of the following completes the statements below?

In accordance with 1 -EOI-1, RPV Control, _(1 )_ is the earliest time the crew must commence depressurizing the Reactor below the Shutdown Cooling Reactor Pressure interlock.

Cooldown rate of 1000 F/hour _(2) be exceeded.

A. (1)1235 (2) can B. (1)1235 (2) CANNOT C. (1) 1300 (2) can D. (1) 1300 (2) CANNOT 17

ILT 1102 Written Exam

18. Unit 2 is in Start Up. Off Gas Treatment Select Switch, 2-XS-66-1 13, is in BYPASS. The following alarms/indications are received:

• OG POST-TREATMENT RADIATION HIGH, (2-9-4C, Window 33)

• Offgas Post-Treatment Radiation is 6.5x1 cps Which ONE of the following identifies the impact of this condition on the Offgas System?

A. NO valves will reposition B. Adsorber Bypass Valve, 2-FCV-66-1 13B will close. NO other valves will reposition.

C. Adsorber Bypass Valve, 2-FCV-66-1 13B will close AND Adsorber Inlet Valve, 2-FCV 11 3A will open. NO other valves will reposition.

D. Adsorber Bypass Valve, 2-FCV-66-1 13B will close. Adsorber Inlet Valve, 2-FCV 11 3A AND Charcoal Adsorber Train 2 Inlet Valve, 2-FCV-66-1 18 will open.

18

ILT 1102 Written Exam

19. With ALL 3 Units operating at 100% Reactor Power, a fire at 4 kV Shutdown Board A has resulted in the following:

• Failure of Unit 1 RHR Pump 1A AND Core Spray Pump IA

• Shift Manager has declared an Appendix R Fire In accordance with Safe Shutdown Instructions, which ONE of the following identifies which, if any, Reactor(s) is (are) required to be scrammed?

A. NO Reactor Scram is required B. Unit I ONLY C. Unit 1 AND Unit 2 ONLY D. ALL3 Units 19

ILT 1102 Written Exam

20. Unit 3 is operating at 80% Reactor Power AND the crew has entered 0-AOl-57-1 E, Grid Instability, due to the 500 kV system voltage being at 513 kV. The crew reaches the following step in the procedure:

• RAISE reactive power until voltage returns to 520 kV.

Which ONE of the following identifies how to raise reactive power AND the 161 kV Capacitor Bank Status that will restore the system voltage in accordance with 0-AOl-57-1 E?

A. Depress the EHC load set RAISE pushbutton, 3-HS-47-75C; Check the 161 kV Capacitor Banks are IN service.

B. Depress the EHC load set RAISE pushbutton, 3-HS-47-75C; Check the 161 kV Capacitor Banks are OUT of service C. Place the Generator Field Voltage Auto Adjust (90P), 3-HS-57-26, to the RAISE position; check the 161 kV Capacitor Banks are IN service.

D. Place the Generator Field Voltage Auto Adjust (90P), 3-HS-57-26, to the RAISE position; check the 161 kV Capacitor Banks are OUT of service.

20

ILT 1102 Written Exam

21. Unit 3 is operating at 28% Reactor Power, when a lightning strike results in a loss of ALL Condenser Circulating Water Pumps. Immediate Actions of 3-AOl-i 00-1, Reactor Scram, are complete.

Which ONE of the following identifies the AUTOMATIC protective actions that will occur?

A. Reactor Feed Pump Turbine trip AND Main Turbine Bypass Valve closure ONLY B. MSIV Closure, Reactor Feed Pump Turbine trip AND Main Turbine Bypass Valve closure ONLY C. Main Turbine trip, Reactor Feed Pump Turbine trip AND Main Turbine Bypass Valve closure ONLY D. MSIV Closure, Main Turbine trip, Reactor Feed Pump Turbine trip AND Main Turbine Bypass Valve closure 21

ILT 1102 Written Exam

22. Unit 1 is performing a startup per 1-GOl-1 00-1 A, Unit Startup. When the Operator At The Controls (OATC) placed the rod movement control switch to the single notch out position for the next control rod, the rod quickly moved 3 notches beyond its intended position. The following indications are received:

• SRM PERIOD, (1-9-5A, Window 20), in alarm

• SRM period indicates 10 seconds on 1-Xl-92-7/44A D -

Which ONE of the following completes the statement below?

The OATC is required to A. STOP Control Rod withdrawal ONLY.

B. INSERT Control Rods until the Reactor is brought subcritical.

C. SHUT DOWN the Reactor until a thorough assessment has been performed.

D. REINSERT the last Control Rod withdrawn to obtain a stable period greater than 60 seconds.

22

ILT 1102 Written Exam

23. Unit I is at 100% Reactor Power when Control Rod Drive (CRD) Pump 1A trips. During the start of CRD Pump IB, the following occurs:

• Control Rod 30-23 moves from position 16 to position 14

• Control Rod 38-31 is selected and moves from position 16 to position 12 without Operator action Which ONE of the following identifies the required action(s) in accordance with CRD AOIs?

A. Scram the Reactor.

B. Reduce Reactor Power to 90%

C. Insert Control Rod 30-23 ONLY to position 00 using CONTINUOUS IN.

D. Insert Control Rods 30-23 AND 38-31 to position 00 using CONTINUOUS IN.

23

ILT 1102 Written Exam

24. Unit I Suppression Pool Level is (i-) 5 inches and CST level is 550.

Which ONE of the following completes the statements below?

HPCI Suction _(1 )_ automatically transfer to the Suppression Pool.

RCIC Suction _(2)_ automatically transfer to the Suppression Pool.

A. (1) will (2) will B. (1)will (2) will NOT C. (1)will NOT (2) will D. (1)willNOT (2) will NOT 24

ILT 1102 Written Exam

25. Unit 1 is at 100% Reactor Power with the following system line ups:

• Reactor Building Closed Cooling Water (RBCCW) Pumps IA AND 1 B are in service

• Reactor Water Cleanup (RWCU) Pumps IA AND I B are in service

• Fuel Pool Cooling and Cleanup (FPCC) Pump IA is in service Unit I Reactor Scrams AND the following alarms I indications are received:

• 480 V Shutdown Board 1A is locked out

• RBCCW SURGE TANK LEVEL HIGH, (1-9-4C, Window 6)

• RBCCW EFFLUENT RADIATION HIGH, (1-9-3A, Window 17)

• RX BLDG,TURB BLDG, RE ZONE EXH RADIATION HIGH, (1-9-3A, Window 4)

Which ONE of the following is a potential cause of the alarms?

Leakage into RBCCW from A. Reactor Recirc Pump seal coolers B. Fuel Pool Cooling Heat Exchangers C. Reactor Water Cleanup Pump Seal Coolers D. Reactor Water Cleanup Non-Regenerative Heat Exchangers 25

ILT 1102 Written Exam

26. A HPCI Steam Supply leak has resulted in elevated Secondary Containment temperatures AND area water levels. HPCI Steam Supply Isolation valves have failed to isolate AND CANNOT be manually closed. Two Secondary Containment Water Levels are above their Maximum Safe Value requiring Emergency Depressurization.

Which ONE of the following completes the statement below?

In accordance with EOl-3, Secondary Containment Control Bases, ALL of the following are reasons for requiring Emergency Depressurization with the EXCEPTION of A. placing the primary system in the lowest possible energy state B. rejecting decay heat to the suppression pool, rather than secondary containment C. reducing driving head and flow of primary systems that are unisolated and discharging into secondary containment D. allowing access into the Reactor Building by the Emergency Response Organization to locate and manually isolate the leak 26

ILT 1102 Written Exam

27. Unit 2 was operating at 100% Reactor Power when a LOCA occurred. Plant conditions are as follows:

• Drywell H 2 is 3% increasing

• Drywell 02 is 4% increasing

• Suppression Chamber H 2 is 2% steady

• Suppression Chamber 02 is 3% steady Which ONE of the following completes the statement below?

Based on the above conditions, Nitrogen must be lined up to A. the Drywell B. the Suppression Chamber C. the Drywell AND Suppression Chamber D. NO primary containment area; the Primary Containment EOI entry condition for hydrogen concentration has NOT been exceeded 27

ILT 1102 Written Exam

28. An accident occurred on Unit 2 AND resulted in the following conditions:

• Reactor water level indicates () 200 inches on Post Accident Range

• Reactor pressure is 400 psig

• ALL RHR I LPCI are lost

• ONLY ONE CRD Pump AND ONE Core Spray pump are running Which ONE of the following completes the statement below?

Adequate core cooling

[REFERENCE PROVIDED]

A. does NOT exist B. is provided by Spray Cooling C. is provided by Steam Cooling D. is provided by Core Submergence 28

ILT 1102 Written Exam

29. Unit 1 is in Mode 4 with RHR Pump I B in Shutdown Cooling.

Which ONE of the following completes the statements below?

In accordance with Tech Spec 3.5.2, ECCS Shutdown, RHR Pump I B (1)_ Operable for the ECCS function.

The MAXIMUM allowed RCS cooldown rate per Tech Spec 3.4.9, RCS Pressure and Temperature (PIT) Limits, is _(2).

A. (1)is (2) 100°F per hour B. (1)is (2)100°F in any one hour period C. (1)isNOT (2)100°F per hour D. (1)is NOT (2)100°F in any one hour period 29

ILT 1102 Written Exam

30. Unit I was operating at 100% Reactor Power; when the reactor scrammed on low RPV water level and HPCI auto started, which resulted in the following conditions:

• RPV water level lowered to (-) 50 inches and is currently (+) 55 inches and slowly lowering.

Which ONE of the following, is the FIRST condition that would cause an AUTOMATIC restart of HPCI?

A. Level lowers to (+) 27 inches.

B. Level lowers to (÷) 2 inches.

C. Level lowers to (-) 45 inches.

D. Drywell Pressure greater than 2.45 psig.

30

ILT 1102 Written Exam

31. Unit 2 was operating at 100% Reactor Power, when a plant event resulted in a reactor scram AND loss of 250 VDC RMOV BD 2A. Degrading plant conditions have resulted in the following:

• Reactor Pressure is 325 psig and stable

• A few minutes later, Drywell Pressure is 2.8 psig Based on the above conditions, which ONE of the following predicts how Core Spray will be affected by the bus loss?

A. ALL Core Spray pumps will start AND ALL injection valves will open.

B. ONLY the Loop I Core Spray pumps will start AND Loop I injection valves will open.

C. ONLY the Loop 2 Core Spray pumps will start AND Loop 2 injection valves will open.

D. NO Core Spray pumps will start AND NO injection valves will open.

31

ILT 1102 Written Exam

32. Unit I is executing 1-EOl-1, RPV Control, due to a Scram AND an ATWS. The Unit Operator (UO) is directed to inject Standby Liquid Control (SLC) per 1-EOI Appendix 3A, SLC Injection.

The UO places the SLC Pump control switch in the START-A position.

Given the following plant conditions:

• SLC SQUIB VALVE CONTINUITY LOST, (1-9-5B, Window 20) Extinguished

• SQUIB VALVE A and B CONTINUITY, blue lights on Panel 1-9-5 Illuminated

• SLC Pump 1A red light Illuminated Which ONE of the following describes the status of SLC AND the correct action(s) to take as stated in 1-EOI Appendix 3A?

A. ONE squib valve has fired.

Start SLC Pump I B, AND verify proper operation.

B. NEITHER squib valve has fired.

Start SLC Pump 1 B, AND verify proper operation.

C. ONE squib valve has fired.

Verify proper system operation by observing the SLC tank level lowering by -1 % per minute.

D. BOTH squib valves have fired.

Verify proper system operation by observing the SLC tank level lowering by -1% per minute.

32

ILT 1102 Written Exam

33. Unit 2 was operating at 100% Reactor Power, when the plant experienced a complete loss of the Control Air system The following plant conditions exist

• ALL eight Scram Solenoid Group A/B Logic Reset Lights are NOT lit

• Recirc Pumps are Tripped

• Reactor Power is 20%

You are the OATC and have been directed to perform 2-EOI Appendix 1D, Insert Control Rods Using Reactor Manual Control System (RMCS).

Which ONE of the following completes the statement below?

Verify CRD Pump operating, (1) , direct manually opening CRD Flow Control Valve (2-FCV-85-1 IA or B), verify Mode Switch in SHUTDOWN, bypass the Rod Worth Minimizer, CRD Power Switch ON, select control rod, AND place CRD (2)

A. (1) reset ARI (2) Control Switch in ROD IN, until green 00 is lit, on the four rod display B. (1)resetARl (2) Notch Override Switch in EMERG IN, until the control rod stops moving inward C. (1) direct closure of CHARGING WATER SHUTOFF, 2-SHV-85-586 (2) Control Switch in ROD IN, until the green 00 is lit, on the four rod display D. (1) direct closure of CHARGING WATER SHUTOFF, 2-SHV-85-586 (2) Notch Override Switch in EM ERG IN, until the control rod stops moving inward 33

ILT 1102 Written Exam

34. Unit 2 is performing a startup with the following conditions:

• Mode Switch is in STARTUP

• Reactor is critical

• IRMs are steady on Range 2 Which ONE of the following identifies the IRM power source AND the effect of a loss of power to a single IRM?

IRM Power Source Effect of Power Loss to IRM A. 24 VDC Battery Rod Block ONLY B. 24 VDC Battery Rod Block AND Half Scram C. 250 VDC Battery Rod Block ONLY D. 250 VDC Battery Rod Block AND Half Scram 34

ILT 1102 Written Exam

35. Which ONE of the following completes the statement below?

The applied voltage to the SRM detector is (1 )_ than the applied voltage used for the IRM detector AND the SRM electrode generates an electrical signal (2) proportional to neutron flux in the core.

A. (1)lower (2) directly B. (1) higher (2) directly C. (1)lower (2) inversely D. (1) higher (2) inversely 35

ILT 1102 Written Exam

36. A plant start up on Unit 3 is in progress. A control rod block has occurred. The following nuclear instrument indications are noted:

SRMA SRMB SRMC SRMD Position Full in Mid-position Mid-position Full in Counts (CPS) 3 9.5x10 125 150 3 8.0x10 HM A IRM B IRM C IRM D IRM E IRM F IRM G IRM H 25/125 15/125 35/125 55/125 75/125 75/125 30/125 25/125 Range 3 Range 2 Range 3 Range 3 Range 2 Range 2 Range 3 Range 3 Which ONE of the following identifies the MINIMUM action needed to clear the ROD WITHDRAWAL BLOCK?

A. Insert SRM B ONLY B. InsertSRMBANDSRMC C. RangeuponlRMBAND IRM Ftorange3 D. RangeuponlRME AND IRMFto range3 36

ILT 1102 Written Exam

37. Unit 2 APRM Channel 3 has a total of 18 LPRM inputs.

Which ONE of the following statements identifies the expected response to this condition?

A. The APRM will produce a Rod Block signal ONLY.

B. NO Rod Block OR Reactor Scram signals are generated.

C. The APRM will produce a Rod Block signal AND a Scram signal input to EACH 2/4 logic voter module.

D. The APRM will produce a Rod Block signal AND a Scram signal input to ITS RESPECTIVE 2/4 logic voter module ONLY.

37

ILT 1102 Written Exam

38. Unit 2 experienced a loss of 250 VDC RMOV BD 2B Which ONE of the following statements describes the operation of the RCIC system?

A. RCIC will NOT automatically isolate.

B. RCIC will NOT automatically initiate.

C. The RCIC Flow Controller fails downscale.

D. ONLY the manual isolation is functional.

38

ILT 1102 Written Exam

39. Which ONE of the following completes the statement below?

The power supply to the Unit 2 RCIC Vacuum Pump is A. 250 VDC RMOV BD 2A B. 25OVDCRMOVBD2C C. 480 VAC RMOV BD 2A D. 480 VACRMOVBD2B 39

ILT 1102 Written Exam

40. Unit 2 was operating at 100% Reactor Power with RHR Pump 2D tagged out of service. A Loss of Coolant Accident with a subsequent Loss of Off Site Power has resulted in the following plant conditions:

• Reactor Water Level is (-)1 25 inches

• Drywell Pressure is 4.1 psig

• A AND C 4KV Shutdown Boards are de-energized Which ONE of the following identifies the MINIMUM action(s), if any, that will prevent the Automatic Depressurization System (ADS) from an Auto-Initiation?

A. NO action is required B. Place ONLY ADS Logic Inhibit Switch A to INHIBIT C. Place ONLY ADS Logic Inhibit Switch B to INHIBIT D. Place BOTH ADS Logic Inhibit Switches to INHIBIT 40

ILT 1102 Written Exam

41. Which ONE of the following completes the statement below?

A trip of BOTH division I (A, C) Reactor Water Cleanup Suction Isolation Valves low level sensor relay(s) within a logic trip channel will cause a _(1)_ isolation AND (2)_

closure.

A. (1)half (2) NO valve B. (1)half (2) inboard valve C. (1)full (2) inboard valve D. (1)full (2) inboard AND outboard valve 41

ILT 1102 Written Exam

42. Unit 2 is starting up following a refueling outage with Reactor Pressure at 80 p51g.

RPS MG Set A has tripped. RPS Distribution Panel A has NOT yet been transferred to its alternate source.

The Low-Low-Low Reactor Water Level instrument providing input to PCIS Channel B2 fails downscale.

Which ONE of the following describes the response of MSIVs AND Main Steam Line Drains?

A. ONLY the Inboard Steam Line Drain valve AND ALL MSIVs close.

B. ONLY the Outboard Steam Line Drain valve AND ALL MSIVs close.

C. Inboard AND Outboard Steam Line Drain valves AND ALL MSIVs close.

D. Inboard AND Outboard Steam Line Drain valves close, AND ALL MSIVs remain open.

42

ILT 1102 Written Exam

43. During a transient on Unit 1, Reactor Pressure reached 1150 psig.

Which ONE of the foNowing identifies how many SRVs opened?

A. Four B. Eight C. Nine D. Thirteen 43

ILT 1102 Written Exam

44. Unit 2 Feedwater Level Control System (FWLCS) is operating in 3-Element Control with Narrow Range Level Instruments indicating as follows

• 2-LT-3-53, LEVEL A, (+) 46 inches

• 2-LT-3-60, LEVEL B, (+) 32 inches

• 2-LT-3-206, LEVEL C, (+) 34 inches

• 2-LT-3-253, LEVEL D, (+) 33 inches Which ONE of the following completes the statement below?

If 2-LT-3-60, LEVEL B, is manually bypassed, the FWLCS will control Reactor Water Level based on A. ONLY the 2-LT-3-206 instrument B. LOWEST of 2-LT-3-206 OR 2-LT-3-253 instruments C. AVERAGE of 2-LT-3-206 AND 2-LT-3-253 instruments D. AVERAGE of 2-LT-3-53, 2-LT-3-206, AND 2-LT-3-253 instruments 44

ILT 1102 Written Exam

45. Which ONE of the following completes the statement below?

Standby Gas Treatment System _(1) are designed to remove elemental iodine AND the (2)_ are designed to reduce relative humidity to less than 70%.

A. (1) HEPA Filters (2) Moisture Separators B. (1) Carbon Beds (2) Moisture Separators C. (1) HEPA Filters (2) Electric Heaters D. (1) Carbon Beds (2) Electric Heaters 45

ILT 1102 Written Exam

46. The Unit 1 Unit Preferred Inverter is operating in a normal lineup, when a loss of off-site power AND a failure of DG A to start occurs.

Which ONE of the following completes the statement below?

The Unit Preferred Inverter is powered from A. 480V RMOV BD IA B. 250 VDC Battery Board 4 C. 250 VDC Battery Board 5 D. the Unit Preferred Transformer 46

ILT 1102 Written Exam

47. Which ONE of the following completes the statements below?

The 1001 AND 1003 breaker from Unit 2 Unit Preferred System (UPS) Motor-Motor-Generator (MMG) set will trip on (1)_ at the output of the MMG.

In accordance with 2-AOl-57-4, Loss of Unit Preferred, if UPS is lost, the crew must

_(2)_.

A. (1) underfrequencyONLY (2) take manual control of Master Feedwater Level Controller B. (1) underfrequencyONLY (2) verify Reactor Feedwater Control System is maintaining Reactor Water Level C. (1) under frequency OR overvoltage (2) take manual control of Master Feedwater Level Controller D. (1) under frequency OR overvoltage (2) verify Reactor Feedwater Control System is maintaining Reactor Water Level 47

ILT 1102 Written Exam

48. Battery Rooms 1, 2, and 3 HVAC Systems are not operating properly.

Which ONE of the following completes the statements below?

The concern is that _(1 )_.

Plant procedures direct the utilization of an _(2)_.

A. (1) lead-calcium batteries tend to release toxic gas into the atmosphere at temperatures above 90 °F (2) Emergency Exhaust Fan ONLY B. (1) the design limit for hydrogen concentration in the rooms may be reached during battery charging operations (2) Emergency Exhaust Fan ONLY C. (1) lead-calcium batteries tend to release toxic gas into the atmosphere at temperatures above 90 °F (2) Emergency Exhaust Fan ANDIOR Portable Temporary Ventilation Equipment D. (1) the design limit for hydrogen concentration in the rooms may be reached during battery charging operations (2) Emergency Exhaust Fan ANDIOR Portable Temporary Ventilation Equipment 48

ILT 1102 Written Exam

49. Diesel Generator (DIG) A is synchronized to 4KV Shutdown Board A. The instrumentation readings for the D/G are as follows:

• Voltage = 4160VAC

• Frequency = 60 Hz

• Current = 280 amps

• Vars = 2200 Kvars

• Watts = 2600 Kw Which ONE of the following is the correct action to obtain a 0.8 lagging power factor?

Take the

[REFERENCE PROVIDED]

A. Governor control switch to RAISE.

B. Governor control switch to LOWER.

C. Voltage Regulator control switch to RAISE.

D. Voltage Regulator control switch to LOWER.

49

ILT 1102 Written Exam

50. G Control Air Compressors microcontroller fails, causing the Compressor Inlet Flow Valve to throttle open and the Compressor Bypass Control Valve to fail fully open Which ONE of following completes the statement below?

Control Air Header pressure will A. stabilize between 110 to 120 psig B. stabilize between 90 to 110 psig C. stabilize between 75 to 90 psig D. increase to 132 psig 50

ILT 1102 Written Exam

51. Control Air Compressors A AND C are in service. A momentary loss of power to 480V Shutdown Board I B occurs. Three seconds later, normal voltage is restored.

Which ONE of the following completes the statement below?

Control Air Compressor _(1 )_ will trip AND _(2)_ automatically re-start when normal voltage is restored.

A. (1)A (2) will B. (1)C (2) will C. (1)A (2) will NOT D. (1)0 (2) will NOT 51

ILT 1102 Written Exam

52. Which ONE of the following completes the statement below?

The Unit 2 Reactor Building Closed Cooling Water (RBCCW) Temperature Controller, 2-TIC-24-80, is located in Unit 2 Reactor Building at _(1)_.

If the controller is placed in AUTO with the indications shown below, the Temperature Control Valve will modulate to a more _(2)_.

A. (1) Panel 2-25-1 96, Elevation 565 (2) closed position B. (1) RBCCW Heat Exchanger area, Elevation 593 (2) close position C. (1) Panel 2-25-1 96, Elevation 565 (2) open position D. (1) RBCCW Heat Exchanger area, Elevation 593 (2) open position 52

ILT 1102 Written Exam

53. Unit 2 RBCCW Heat Exchanger 2A is being filled and vented per 2-01-70, Reactor Building Closed Cooling Water System.

Which ONE of the following completes the statement below?

While filling the Heat Exchanger, RBCCW Surge Tank Level will lower until RBCCW SYS SURGE TANK FILL VALVE, 2-FCV-70-1, A. is manually opened from the Control Room B. is manually opened locally at the Surge Tank C. automatically opens at 4 inches below the Surge Tank centerline D. automatically opens at 4 inches above the Surge Tank centerline 53

ILT 1102 Written Exam

54. Unit I Control Rod Drive System has ruptured on the Charging Water Header upstream of the header restricting orifice.

Which ONE of the following completes the statement below?

This condition is indicated by the CRD Pump IA motor amps being _(1)_ than normal AND the CRD Flow Control Valve traveling FULL _(2)_.

A. (1) LOWER (2) OPEN B. (1) HIGHER (2) OPEN C. (1)LOWER (2) CLOSED D. (1) HIGHER (2) CLOSED 54

ILT 1102 Written Exam

55. During a UNIT I startup, a control rod drive mechanism is difficult to withdraw and remains at position 00.

The HCU hydraulic lines were vented.

Which ONE of the following completes the statement below in accordance with 1-01-85, Control Rod Drive System?

GOTO A. ROD IN, then ROD OUT NOTCH with the CRD CONTROL SWITCH, release if rod moves B. ROD OUT NOTCH with the CRD CONTROL SWITCH, then NOTCH OVERRIDE with the CRD NOTCH OVERRIDE SWITCH, release switches if rod moves C. EMERGENCY IN with the CRD NOTCH OVERRIDE SWITCH, then simultaneously place the CRD CONTROL SWITCH in ROD OUT NOTCH, release switches if rod moves D. EMERGENCY IN, then NOTCH OVERRIDE with the CRD NOTCH OVERRIDE SWITCH, and then simultaneously place CRD CONTROL SWITCH in ROD OUT NOTCH, release switches if rod moves 55

ILT 1102 Written Exam

56. Unit I is operating at 100% Reactor Power with the A Traversing In-Core Probe (TIP) inserted in the core. A transient occurs resulting in the following plant conditions:

• Reactor Level is (-) 20 inches

• Drywell pressure is 1.5 psig Which ONE of the following completes the statement below?

The A TIP will withdraw to the _(1) position AND the Ball Valve position will be

_(2)_.

A. (1)PARKED (2) open B. (1)PARKED (2) closed C. (1)lN-SHIELD (2) open D. (1) IN-SHIELD (2) closed 56

ILT 1102 Written Exam

57. Unit 2 is at 100% Reactor Power with Residual Heat Removal (RHR) Loop II in Suppression Pool Cooling mode. The following alarms are received on Unit 1:

• DRYWELL PRESSURE HIGH HALF SCRAM, (1-9-4A, Window 8)

• RX PRESS LOW CORE SPRAY/RHR PERMISSIVE, (1-9-3C, Window 35)

Which ONE of the following describes the current status of Unit 2 RHR system AND what actions, if any, must be taken to restore Suppression Pool Cooling on Unit 2?

A. ALL four RHR pumps receive a trip signal. Place RHR Loop II in Suppression Pool Cooling IMMEDIATELY.

B. 2A AND 2C RHR Pumps are tripped. 2B AND 2D pumps are unaffected. NO additional action is required.

C. ALL four RHR pumps receive a trip signal. Place RHR Loop II in Suppression Pool Cooling after a 60-second time delay.

D. 2B AND 2D RHR Pumps are tripped. 2A AND 2C pumps are unaffected. Place RHR Loop I in Suppression Pool Cooling IMMEDIATELY.

57

ILT 1102 Written Exam

58. Unit 3 is operating at 100% Reactor Power with the Alternate Supply Breaker 1528 to 4kV Unit Board 3B tagged out of service. An accident results in the following conditions:

• Unit Station Service Transformer 3B locks out

• Suppression Chamber Pressure reaches 3 psig

• 3A AND 3B RHR pumps are running in Suppression Chamber Spray Mode.

Which ONE of the following completes the statement below?

The power supply for the 4 kV Shutdown Board to RHR Pump 3A is (1)_ AND RHR Pump 3B is_(2)_.

A. (1) Common Station Service Transformer A (2) Common Station Service Transformer A B. (1) Common Station Service Transformer A (2) its associated Emergency Diesel Generator C. (1) its associated Emergency Diesel Generator (2) Common Station Service Transformer A D. (1) its associated Emergency Diesel Generator (2) its associated Emergency Diesel Generator 58

ILT 1102 Written Exam

59. Given the following:

• Unit I is in Mode 5

• The Refuel Platform is over the Spent Fuel Pool

• The Reactor Mode Switch is in START & HOT STBY for testing Which ONE of the following identifies when a rod block will occur?

A. When the Refuel Platform Fuel Grapple is lowered.

B. When a load is placed on the Refuel Platform Fuel Grapple.

C. When the Refuel Platform is driven near or over the core.

D. Immediately when the Refuel Platform moves toward the core.

59

ILT 1102 Written Exam

60. RFPT IA OVERSPEED TEST TRIP LOCKOUT, 1-HS-3-109A, has been placed in the ELEC position per 1-01-3, Reactor Feedwater System, Section 8.9, RFPT Overspeed Trip Test, when RFPT 1A experiences an ACTUAL over-speed condition.

Which ONE of the following describes the AUTOMATIC response of RFPT 1A?

A. Trips as a result of the electrical trip solenoid.

B. Trips as a result of the mechanical trip mechanism.

C. Will ONLY trip when I-HS-3-109A is restored to the NORM position.

D. Will ONLY trip when ELECT OVERSPEED TEST BYP, 1-HS-3-0109B is released from TEST to NORM 60

ILT 1102 Written Exam

61. Unit 2 Offgas Post Treat Radiation Monitor, 2-RM-90-265A, has failed downscale.

Which ONE of the following completes the statements below?

If Offgas Post Treat Radiation Monitor, 2-RM-90-266A, reaches the High-High-High setpoint, Off-Gas System Isolation Valve, 2-FCV-66-28, _(1) close.

If Offgas Post Treat Radiation Monitor, 2-RM-90-266A, fails downscale, Off-Gas System Isolation Valve, 2-FCV-66-28, _(2)_ close.

A. (1) will (2) will B. (1)willNOT (2) will C. (1)will (2) will NOT D. (1)will NOT (2) will NOT 61

ILT 1102 Written Exam

62. Given the following Control Room Emergency Ventilation (CREV) system conditions:

• CREV Train A was started to prove operability following maintenance on the charcoal trays using the STOP-AUTO-START switch on Panel 9-22.

• The SYSTEM PRIORITY SELECTOR SWITCH is selected for TRAIN-B.

Which ONE of the following completes the statement below that describes the CREV system response should a valid CREV initiation signal be received?

CREV Train B would_(1) AND CREV Train A would _(2).

A. (1) initiate (2) shutdown B. (1)NOT initiate (2) shutdown C. (1) initiate (2) NOT shutdown D. (1)NOT initiate (2) NOT shutdown 62

ILT 1102 Written Exam

63. On Unit 1, Standby Gas Treatment System (SGTS) A, Control Switch I -HS-65-1 8A on Panel 1-9-25 has been placed in the pull-to-lock position.

Which one of the following conditions would still cause SGTS A to start?

A. Unit 2 drywell pressure rises to 2.5 psig.

B. Unit 3 SGTS A start pushbutton is depressed.

C. The local (SGTS Building) SGTS A start pushbuffon is depressed.

D. SGT TRAIN A INBD ISOL TEST SIG Keylock switch (HS-65-48A) is placed in the TEST position.

63

ILT 1102 Written Exam

64. Which ONE of the following completes the statements below?

Jet Pumps are designed such that following a DBA LOCA, a re-floodable core volume NO lower than _(1) is assured.

Following a DBA LOCA with ALL ECCS available, Severe Accident Management Guidelines

_(2)_ be required to be entered.

A. (1) (-)180 inches (2) will B. (1) (-)180 inches (2) will NOT C. (1) (-)215 inches (2) will D. (1) (-)215 inches (2) will NOT 64

ILT 1102 Written Exam

65. Which ONE of the following combinations of electrical board losses would result in BOTH Control Room Emergency Ventilation Fans being de-energized? (Assume normal alignment)

A. 480V Shutdown Board 3B; 4kV Shutdown Board 3EA B. 480V Shutdown Board 1 B; 4kV Shutdown Board 3EA C. 480V Shutdown Board 3B; 4kV Shutdown Board A D. 480V Shutdown Board IB; 4kV Shutdown Board A 65

ILT 1102 Written Exam 66.

CURVE 6 PRESS SUPPR PRESS 35 I t 30 Cl) 25 Cl)

SAFE -*

10 IN1-

)1.

Cl) 0 - - . -- -- - -- -

1111.5 12 13 14 15 16 17 18 19 20 SUPPR PL LVL (Fr)

Which ONE of the following completes the statement below?

In accordance with the EOI Program Manual derivation, Line on Curve 6, Pressure Suppression Pressure, above, corresponds to the Suppression Pool Water Level at which the A. Downcomer Vents become uncovered B. HPCI Turbine Exhaust opening becomes uncovered C. Safety Relief Valve (SRV) Tailpipe openings become uncovered D. Control Room Suppression Pool Water Narrow Range Level Indication goes off scale low 66

ILT 1102 Written Exam

67. Which ONE of the following is a Design Basis of HPCI?

A. Maintain sufficient reactor water inventory so the fuel wont overheat when a reactor isolation AND loss of feedwater occurs.

B. Make up water to the vessel in the event of a loss of coolant situation that does NOT result in rapid vessel depressurization.

C. Assures that the reactor core is adequately cooled to limit fuel clad temperature to

<1800 °F in the event of a large break in the reactor coolant system.

D. Assures that the reactor core is adequately cooled to limit primary containment pressure in the event of a small break in the reactor coolant system.

67

ILT 1102 Written Exam

68. Which ONE of the following defines the purpose of the Rod Worth Minimizer (RWM) in accordance with Technical Specifications?

A. Ensures that fuel enthalpy does not exceed 280 cal/gm during a control rod drop accident when Reactor Power is < 10%.

B. Ensures that fuel enthalpy does not exceed 280 cal/gm during a control rod drop accident when Reactor Power is > 27%.

C. Ensures that the Minimum Critical Power Ratio remains greater than 1.08, while withdrawing control rods, when Reactor Power is < 10%.

D. Ensures that the Minimum Critical Power Ratio remains greater than 1.08, while withdrawing control rods, when Reactor Power is > 27%.

68

ILT 1102 Written Exam

69. Unit I Plant Startup is in progress.

Which ONE of the following completes the statement below?

In accordance with 1-GOI-IOO-IA,Unit Startup, Control Rod withdrawal is limited to single notch when the _(1)_ SRM count rate doubling is reached AND must continue until

_(2)_.

A. (1) fourth (2) the Reactor is Critical B. (1) fifth (2) the Reactor is Critical C. (1) fourth (2) Reactor is in the heating range Power D. (1) fifth (2) Reactor Power is in the heating range 69

ILT 1102 Written Exam

70. Which ONE of the following completes the statement below?

When Reactor Steam Dome Pressure of _(1 )_ is exceeded (as stated in Unit 2 Tech Spec 3.4.10, Reactor Steam Dome Pressure), it must be restored to within limits in a MAXIMUM completion time of _(2).

A. (1) 1050 psig (2)15 minutes B. (1) 1050 psig (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. (1) 1073 psig (2)15 minutes D. (1) 1073 psig (2) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 70

ILT 1102 Written Exam

71. Which ONE of the following describes the meaning of a BLUE magnetic border being installed on a Main Control Room panel annunciator?

This type of border indicates that the annunciator A. has ONE OR more alarm inputs disabled B. is NOT ABNORMAL for current plant conditions C. is associated with ongoing testing OR maintenance D. window is being relocated to a different window location 71

ILT 1102 Written Exam

72. A valve lineup is to be performed on valves with the following conditions:

• Area temperature is 1150 F

• Area radiation is 40 mr/hr

• The valves are located 20 off the floor Independent Verification of this valve lineup is expected to take 0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

Which one of the following choices completes the statement below in accordance with NPG-SPP-1 0.3, Verification Program?

Based on the above conditions, Independent Verification of this lineup A. CANNOT be exempted B. may be exempted due to elevation C. may be exempted due to excessive dose D. may be exempted due extreme temperature 72

ILT 1102 Written Exam

73. Which ONE of the following completes the statement below?

The Wide Range Gaseous Effluent Radiation Monitor System (WRGERMS) consists of

_(1)_ ranges, AND has _(2)_.

A. (1)TWO (2) monitors in ALL three Units Control Rooms B. (1)THREE (2) monitors in ALL three Units Control Rooms C. (1)TWO (2) a monitor in Unit 2 Control Room ONLY D. (1)THREE (2) a monitor in Unit 2 Control Room ONLY 73

LT 1102 Written Exam A plant emergency is in progress that requires a declaration in accordance with EPIP-1, Emergency Plan Implementing Procedure.

The plant emergency in progress is NOT a security threat to facility protection.

Which one of the following is the Lowest Classification that the Operations Support Center (OSC) AND the Technical Support Center (TSC) must be activated?

OSC TSC A. Alert Alert B. Alert Site Area Emergency C. Site Area Emergency Alert D. Site Area Emergency Site Area Emergency 74

ILT 1102 Written Exam

75. ALL High Pressure Injection has been lost on Unit 2.

• At 16:00:00, Reactor Water Level is (-) 110 inches

• At 16:02:00, Reactor Water Level is (-) 118 inches

• Reactor Water Level continues to lower at the same rate Which ONE of the following completes the statement below?

A Common Accident Signal will be initiated by (1) Range level instruments AND the EARLIEST time that ALL Core Spray Pumps will have auto started is (2)

A. (1) Emergency (2)16:03:07 B. (1) Post Accident (2) 16:03:07 C. (1) Emergency (2)16:03:21 D. (1) Post Accident (2)16:03:21 75

1 KEYIDfl SCORING & 0 RESCORE I MULTIPLE ANSWER SCORING Pearson NCS Test Sheet 1001W PRINTING .D CORRECTANSWER 0 MARK X 0 TOTAL ONLYC LOTIO: MARKONLY ONE TF TF Form No. 95677 1 A C

• E TF 51 A TF 26 A B C E 76 ABC BE Reorder Form No. 95677 2 A B D E 52 O B C 0 B 1-800-367-6627 Fax 1-507-451-4513 27ø .d, 0 E 77 A BC C BE valuebridge. ncspearson.com 3 A. BCD E 53 *B. C (

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• E 78 ABC BE 4 B C D E 54 A B C E 29 A ç B 79 A) .CB C bC (ED 5 A B * ::p 55

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PERCENT PERCENT CORRECT CORRECT ROSTER LETTER NUMBER GRADE SCORE SCORE STUDENTID NUMBER RESCORE RESCORE MARKING Q) (9.) (9.) (9.) (P.) (.0.) (9) (2) (P.) (0.)

INSTRUCTIONS NAME Use a No. 2 Pencil

.9. CD CD CD (I) CD CD CD CD SUBJECT Fill oval completely CD CD CD CD CD CD CD CD PERIOD DATE A .C. Q E (B) CD CD CD CD CD (B) CD Erase cleanly CD CD

Mark fefIexC lorrns by Pearson NCS MM956774 20

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RO REFERENCES PROVIDED 13 EOl Curve 1 & 2 Rev. 8 14 EOI Caution 1 / Curve 8 28 2-LI-3-52/62 Correction Curve 49 DG KW vs. KVAR LOADING 0-01-82 Illustration 1

CURVE I CS NPSH LIMITS 250 230 10 PSIGSAFE*

U U

0 210 1 DO 5PSIGSAFE* *w%%%l 1- 0 PSI G!SAF

-J 170 0

U) 150 - -

130 110 90 p 4 C0 500 1500 2500 3500 4500 CS PUMP FLOW (GPM) *SUPPR CHMSR PRESS CURVE 2 RHR NPSH LIMITS 245 235 15 PSIG SAFE

• 225

-11OPSIGSAFE*

215 I SPSIGSAFE*

205 LU 195 C PSIG SAFE

• 185 175 165 155 *_____

145 iii sti iii iii iii ii 500 2500 4500 6500 8500 10500 12000 RHR PUMP FLOW (GPM) *SUPPR CHMBR PRESS a

CAUTIONS CAUTION

• A4 RPV WATER LVI INSTRUMENT MAY BE USED TO DETERMINE OR TREND LVI. .YWEN.IT READS ABOVE THE MIN IMUM INDICATED LVL ASSOCIATED WITH THE HIGHEST MAX OW OR SC RUN TEMP.

• IF DWTEMPS, OR SC AREATEMPS TABLE 6),ASA?PLICABLE, ARE OUTSIDETHE SAFE REGION OF CURVES, TXE ASSOCIATED INSTRUMENT MAY BE UN RELIABLE DUE TO BOILING IN THE RUN.

MINIMUM MAXDWRUNTEMP MAX SC INSTRUMENT RANGE INDICATED (FROM XR-64-50 RUN TEMP LVL OR Ti-64-52AB (FROM TABLE 6 ON SCALE N/A BELOW 150

-145 N/A 151 TO 200 EMERGENCY IJ-3-58A, B -140 N/A 201 TO 250

-130 N/A 251 T0300

-120 N/A 301 T0350 LI-3-53 ON SCALE N/A BELOW 150 LI-3-60 +5 N/A 151 TO 200 LI-3-206 .15 N/A 201 TO 250 LI-3-253 .20 N/A 251 TO 300 LI-3-208A, 8, C, D +3) N/A 301 TO 350 LI-3-52 POST L I- 3.* ACCIDENT ON SCALE N/A N/A

-268T0+32

+10 BELOW 100 N/A

+15 100 TO 150 N/A SHUTDOWN +20 151 TO 200 N/A LJ-3-55 FLOODUP +30 201 TO 250 N/A 0 TO +400 .40 251 TO 300 N/A

.50 301 TO3&) N/A 351 TO 400 N/A

C 0 2-LI-3-52 & 62 CORRECTION CURVES

-I LU Ui

-j 0

LU ACTUAL I LEVEL C.)

180

- 200 215 0 100 200 300 400 500 600 700 800 900 1000 1104)

REACTOR PRESSURE (PSIG) rq i

SPN Standby Diesel Generator System 0-01-82 Unito Rev,0112 Page 171 of 174 Illustration I (Page 1 of 1)

DO kW vs. IcVAR Loading

• 200 3000 2*00 2400 220*

2000 1000 KW 1800 1200 1000

- LOpS

- LAGOINC 0*0 0i OUTCOINa is 400 200 .

- 1*

0 -

0 200 400 *00 *00 1000 1200 1400 1100 1000 2000 2200 2400 WAR (Lagging or Outgoing)