ML15105A284

Initial Exam 2015-301 Final RO Written Exam

ML15105A284
Person / Time
Site:	Hatch
Issue date:	04/09/2015
From:	Division of Reactor Safety II
To:	Southern Co, Southern Nuclear Operating Co
References
Download: ML15105A284 (84)

Text

I Southern Nuclear Or>erating Company 1 ... Nuclear NMP-TR-213-F01 SOUTHERN~Management 1

Training Exam Coversheet Version 3.0 COMPANY Form Page 1 of 1 Name LMSID 4/9/2015 Date Exam Number ILT-09 SRO NRC EXAM 100.00 75 Exam Title Total Points Instructions

1. This is a(n) _8_ 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> exam .

2. This examination is a:

ltl Written exam with a pass/fail criteria.

0 Practical exam with a pass/fail criteria.

0 Other - - - - - - - - - - - - - - -

3. Answer all of the questions as indicated below:

0 On a separate paper.

ltl On a Scantron sheet.

0 On the exam by marking the correct response, or by filling in the blanks.

0 Orally communicate answer to the Instructor.

Prepared b y : - - - - - - - - - - - - - - - - - Reference Peer Check: _ _ _ _ __

Exam Writer initials Approved by: - - - - - - - - - - - - - - - - - - - -

Training Supervisor or designee WARNING CHEATING OF ANY KIND IS STRICTLY FORBIDDEN. ANY INDIVIDUAL CAUGHT CHEATING WILL AUTOMATICALLY FAIL THE EXAMINATION AND DISCIPLINARY ACTION WILL BE TAKEN.

WARNING All work completed on this examination is my own. To my knowledge, I have neither given nor received aid.

Examinee Signature:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

Exam Graded by: ____s=-C:.:A""'.... O N~------------

N T.:..:R""'... Grade: _ __

Grading R e v i e w : - - - - - - - - - - - - - - - - - - - - - -

(If required)

TR0.001

ILT-09 SRO NRC EXAM

1. 209001K2.0l 001 Which ONE of the choices below completes the following statements?

The power supply for the 2A Core Spray pump is _ _ __

The power supply for the 2B Core Spray pump is _ _ __

A. 4160V 2E, 2R22-S005; 4160V 2F, 2R22-S006 B. 4160V 2E, 2R22-S005; 4160V 20, 2R22-S007 C. 4160V 2F, 2R22-S006; 4160V 2E, 2R22-S005 D. 4160V 2F, 2R22-S006; 4160V 20, 2R22-S007 1

ILT-09 SRO NRC EXAM

2. 201003Al.02 001 Unit 2 is performing a Reactor Startup.

The OATC observes the following indications:

CHG WTR PRESS Q.G WTR dp DRWTRdp 2C11-R601 2C11..R&>3 2C11.R&02 IHSTBUS 2A 2A25*S102 2R25 *S10 1 p

s I

x 1

0 0

Based on the above conditions, If a Control Rod is moved, the Control Rod will travel _ _ _ _ than NORMAL speed.

Placing the control switch for 2Cl 1-F003, Drive Press Cntl Valve, to OPEN for one (1) second will cause Drive Water dp, 2Cll-R602, indication to _ _ __

A. faster; lower B. faster; rise

c. slower; lower D. slower; rise 2

ILT-09 SRO NRC EXAM

3. 201006Al.03 001 Unit 2 is starting up with the following conditions:

o Reactor power is 3.5 % RTP o Control Rod density equals 60%

The currently "Latched" rod step (step 12) has an Insert limit of 24 and a Withdraw limit of 48.

o All Control rods in the currently "Latched" step are at position 48 o Step 13 Control rods are at position 00 The RWM "Display" will FIRST indicate that Step 13 is "Latched" when the _ _ __

After RWM is "Latched" to Step 13, ALL of the Control rods "Latched" in this step will be indicated _ _ _ __

A. first Control rod in step 13 is selected; on the "List Rods" display of RWM B. first Control rod in step 13 is selected; by backlighting on the Control Rod Select Matrix C. last Control rod in step 12 reached position 48; on the "List Rods" display of RWM D. last Control rod in step 12 reached position 48; by backlighting on the Control Rod Select Matrix 3

ILT-09 SRO NRC EXAM

4. 295025EK2.01 001 Unit 2 is operating at 73% RTP when the following MSNs close:

o 2B21-F022A, Inboard Main Steam Isolation Valve o 2B21-F028B, Outboard Main Steam Isolation Valve o RPV pressure peaks at 1078 psig Based on the above conditions, The MSN position input to the RPS logic, due to the closure of the above combination of MSNs, resulted in a RPS signal.

The High Reactor Pressure RPS Scram setpoint _ _ _ _ been exceeded.

A. HALF Scram ONLY; has B. HALF Scram ONLY; has NOT C. FULL Scram; has D. FULL Scram; has NOT 4

ILT-09 SRO NRC EXAM

5. 205000K3.02 001 Unit 1 is in Mode 4 with RHR Loop B Shutdown Cooling in service.

Subsequently, a tube rupture occurs in RHR Heat Exchanger lB.

With the above conditions and NO operator actions, RWL will start going _ _ __

IA W 34SO-El 1-010-1, RHR System, the MINIMUM listed RHR to RHRSW differential pressure allowed is _ _ __

A. UP; 21 psid B. UP; 31 psid C. DOWN; 21 psid D. DOWN; 31 psid 5

ILT-09 SRO NRC EXAM

6. 206000AI .04 001 Unit 2 was operating at 100% RTP when a spurious scram occurred.

RPV pressure control has been transferred to the HPCI System due to the MSN s being manually closed.

IAW 34SO-E41-001-2, HPCI System, HPCI is operating in the Pressure Control Mode at the following times with the associated flows and 2E41-F008, Test To CST Valve, positions:

Time HPCiflow 2E41-F008 10:00 Ratedgpm 75% open 10:20 Ratedgpm 25% open Based on the above conditions; The HIGHEST rate of Torus water level increase will be occurring at _ _ __

If Torus water level reaches 151 inches, HPCI will be operating _ _ __

A. 10:00; on MINIMUM flow B. 10:00; at RATED flow

c. 10:20; on MINIMUM flow D. 10:20; at RA TED flow 6

ILT-09 SRO NRC EXAM

7. 206000A4.03 001 The Unit 2 HPCI system was manually placed in service following a Feedwater transient.

The following conditions exist:

o RWL ............................ 38 inches (lowest level reached -15 inches) o RPV Pressure ............... 920 psig o Drywell pressure ......... 0.5 psig (highest pressure reached 0.6 psig) o HPCI Bearing temperatures are steadily increasing The SRO directs the NPO to monitor HPCI Bearing temperatures.

With the above conditions and IAW 34SO-E41-001-2, High Pressure Coolant Injection (HPCI)

System, When HPCI was started, 2E41-F059, Lube Oil Clg Wtr valve, _ _ _ _ opened.

The NPO will monitor HPCI Bearing temperatures on Panel, _ _ __

A. was manually; 2Hl 1-P700 B. was manually; 2Hll-P614

c. automatically; 2Hl 1-P700 D. automatically; 2Hll-P614 7

ILT-09 SRO NRC EXAM

8. 201002K3.03 001 Unit 2 is performing a shutdown with reactor power at 13% RTP.

A FAILURE of the MASTER Timer occurs in the Reactor Manual Control System (RMCS).

o The MASTER Timer will NOT energize If the "Rod Movement Control" switch is placed to the "IN" position, the selected control rod INSERT.

A RWM "Insert Block" will _ _ _ _ control rod movement while using the "Emergency In/Notch Override" switch.

A. will; ALLOW B. will; PREVENT

c. will NOT; ALLOW D. will NOT; PREVENT 8

ILT-09 SRO NRC EXAM

9. 21IOOOKI.05001 Unit 2 was at 100% RTP when an ATWS occurred.

o RWL is 9 inches (lowest RWL reached -5 inches) o SBLC can NOT be initiated from the Control Room Subsequently, the LOCAL "2A" SBLC pump switch (2H21-P011) is placed in the RUN position.

With the above conditions, 2C41-F004A/B, Squib Valves, will _ _ __

RWCU System _ _ __

A. detonate ONLY after installing jumpers; will automatically isolate B. detonate ONLY after installing jumpers; must be manually isolated C. automatically detonate; will automatically isolate D. automatically detonate; must be manually isolated 9

ILT-09 SRO NRC EXAM

10. 212000K6.05 001 Unit 1 is operating at 30% RTP.

The following failure occurs on Turbine Control Valve (TCV) #1 Emergency Trip Supply (ETS)

Oil Pressure Sensor:

o The transmitter output for TCV #1, ETS Oil Pressure Sensor, begins drifting down and settles below its trip setpoint The TCV Closure RPS Scram setpoint is _ _ __

Based on the above conditions, a RPS HALF (1/2) Scram _ _ _ _ be received.

A. 670 psig; will B. 670 psig; will NOT

c. 1100 psig; will D. 1100 psig; will NOT 10

ILT-09 SRO NRC EXAM

11. 215003A2.05 001 A Unit 2 Reactor startup is in progress.

At 10:00, the IRMs indicate as follows:

o IRMs A, B, C & D 24/125 on Range 6 o IRMs E, F, G & H 10/40 on Range 5 IRMs A-Dare increasing 3/125 per minute AND IRMs E - H are increasing 9/40 per minute.

At 10:01, the voltage at the detector for IRM H decreases to one (1) VDC.

With the above IRM conditions, The EARLIEST listed time that the IRMs will initiate a half scram signal is _ _ __

IAW the associated ARPs on 2H 11-P603, an OD-7 Option 2, Control Rod Position Check, REQUIRED to be performed.

A. 10:01; is B. 10:01; is NOT

c. 10:03; is D. 10:03; is NOT 11

ILT-09 SRO NRC EXAM

12. 215004A3.0l 001 Unit 2 is performing a Shutdown By Prescribed Control Rod Sequence Insertion (Improved BPWS) IAW 3400-0PS-013-2, Plant Shutdown.

o IRMs are on Range 3 o SRM C & D are selected The following indications currently exist:

SOURCE RANGE MONITOR LEVEL A B 2C61-R800A 2C51-R8008 Based on these indications, Annunicator ROD OUT BLOCK, (603-238) _ _ _ _ be illuminated.

If the DRIVE IN pushbutton for SRM/IRM Drive Contol is depressed for 10 seconds and then released, SRM C & D indications above will _ _ __

A. will; stop increasing as soon as the "Drive IN" push button is released B. will; continue to increase until SRM C & D are fully inserted C. will NOT; stop increasing as soon as the "Drive IN" push button is released D. will NOT; continue to increase until SRM C & D are fully inserted 12

ILT-09 SRO NRC EXAM

13. 215004K2.0l 001 Unit 2 is starting up with Reactor power at 5% RTP.

24/48 VDC Cabinet 2B, 2R25-S016, de-energizes and can NOT be restored.

SRM Channels _ _ _ _ will have lost their power supply.

A. 2A&2C B. 2A&2D C. 2B &2C D. 2B &20 13

Il..T-09 SRO NRC EXAM

14. 215005K5.03 001 Unit 2 is starting up from a refueling outage.

o Reactor power is 7% RTP The NPO has just completed moving a Step of Control Rods to their withdraw limit of position 08.

Before movement of the next group of control rods, the following occurs, o One (1) Control Rod starts drifting out from position 08 With the above Control Rod drifting out, Notch positions will provide the HIGHEST change in magnitude of LPRM power indication as the control rod drifts through this range of notch positions.

IA W 34AB-Cl 1-004-2, Mispositioned Control Rods, the OATC is required to _ _ __

A. 20to 24; drive the drifting rod to position 08 using the EMERGENCY IN switch B. 20 to 24; manually SCRAM the reactor C. 36 to40; drive the drifting rod to position 08 using the EMERGENCY IN switch D. 36 to40; manually SCRAM the reactor 14

ILT-09 SRO NRC EXAM

15. 217000K3.03 001 After a loss of Main Condenser vacuum transient on Unit 2, RCIC is operating in Pressure Control Mode.

The RCIC flow controller, 2E51-R612, is in AUTOMATIC with an output of 75%.

Subsequently, a malfunction causes 2E51-R612 controller output to drift from 75% to 95%

resulting in the following RCIC indications:

PUMP SUCTION PUMP DISCH TUR8 IHLET TURBEXH PRESS PRESS PRESS PRESS 2E51-R6CM 2E51.-01 2E51.11602 2E51.-03 As the RCIC controller output drifts up to 95%, the reactor Cooldown Rate will _ _ __

Based on the above indications, RCIC should have _ _ _ __

A. decrease; ONLY automatically tripped B. decrease; automatically tripped AND isolated C. increase; ONLY automatically tripped D. increase; automatically tripped AND isolated 15

ILT-09 SRO NRC EXAM

16. 218000K5.01 001 Unit 2 was operating at 100% RTP when a LOCA occurred.

o ADS logic automatically opened the ADS valves during the transient When both ADS Inhibit Switches are placed in the "INHIBIT" position, the ADS valves will AND the 102.5 second ADS timer _ _ __

A. close; will reset B. close; will NOT reset

c. remain open; will reset D. remain open; will NOT reset 16

ILT-09 SRO NRC EXAM

17. 218000K1.04001 At 14:50, Unit 2 experiences a Loss of Offsite Power (LOSP).

At 15:00, the following conditions exist:

o ALL low pressure ECCS pumps have been manually started o RPV Pressure ...................... 860 psig controlled by LLS o RWL ............................ -97 inches, lowering at 2 inches/minute o Drywell Pressure .............. 0.85 psig, rising at 0.2 psig/minute o ADS Inhibit Switches .......... "Normal" position Given these trends, The EARLIEST listed time that the ADS valves will have automatically OPENED is _ _ __

A. 15:02 B. 15:04

c. 15:07 D. 15:13 17

ILT-09 SRO NRC EXAM

18. 219000A2.l3 001 Unit 2 is operating at 100% RTP when the following occurs; At 10:00, o 'M' SRV inadvertently opens 0 Suppression Pool temperature is 94 °F and rising 1°F/minute At 10:01, o Shift Supervisor directs a NPO to place RHR Loop A into Suppression Pool Cooling IAW 34SO-El 1-010-2, Residual Heat Removal System At 10:10, o 'M' SRV is closed o Suppression Pool temperature is 102°F and steady With the above conditions, At 10:02 and IA W 34SO-El 1-010-2, 2El l-F047A, Hx Inlet Valve, _ _ _ _ required to be CLOSED prior to starting the first RHR pump.

At 10: 10 and IAW 34AB-T23-003-2, Torus Temperature Above 95° F, ALL available RHR Loops required to be placed into Suppression Pool Cooling.

A. is; are B. is; are NOT

c. is NOT; are D. is NOT; are NOT 18

ILT-09 SRO NRC EXAM

19. 223002A4.0l 001 Unit 2 is operating at 100% RTP.

At 10:00, an event occurred which resulted in the following conditions:

o HPCI Equipment (Pipe Penetration) Room, 170°F o Torus Area Ambient Temperature, 170°F At 10:15, o HPCI Equipment (Pipe Penetration) Room, 185°F o Torus Area Ambient Temperature, 185°F With the above conditions, The EARLIEST listed time that 2E41-F002, HPCI Isolation valve, should have received an automatic isolation signal is _ _ __

2E41-F002 valve position _ _ _ _ be monitored on 2Hll-P601 Vertical Display.

A. 10:00; can B. 10:00; can NOT

c. 10:15; can D. 10:15; can NOT 19

ILT-09 SRO NRC EXAM

20. 223002K6.02 001 Unit 2 is operating at 100% RTP when the following occurs:

o RPS A DE-ENERGIZES Two (2) minutes later, a DC Switchgear DE-ENERGIZES as indicated below on Panel, 2Hl 1-P651; This row is Illuminated Based on the above electrical losses, The 125/250 VDC Battery Switchgear that de-energized is _ _ __

Ten (10) seconds later, _ _ _ _ of the Main Steam Isolation Valves (MSIVs) will have automatically isolated.

A. 125/250 VDC Batt Swgr 2B, 2R22-S017; four (4)

B. 125/250 VDC Batt Swgr 2B, 2R22-S017; none C. 125/250 VDC Batt Swgr 2A, 2R22-S016; four (4)

D. 125/250 VDC Batt Swgr 2A, 2R22-S016; none 20

ILT-09 SRO NRC EXAM

21. 230000K2.02 001 Unit 2 experiences a Loss of Offsite power.

o 4160V 2G is the ONLY 4160V bus that is ENERGIZED Based on the above conditions, RHR pump 2B _ _ _ _ be used for Suppression Pool Spray.

RHR pump 2D _ _ _ _ be used for Suppression Pool Spray.

A. can; can B. can; can NOT

c. can NOT; can D. can NOT; can NOT 21

ILT-09 SRO NRC EXAM

22. 239002Kl .07 001 Unit 2 is operating at 100% RTP when a transient occurs resulting in Suppression Pool level lowering with the following times and levels:

TIME LEVEL 10:00 147 inches 10:02 145 inches Based on the above conditions and IAW TS 3.6.2.2, Suppression Pool Water Level, the EARLIEST listed time that a Required Action Statement (RAS) is entered is _ _ __

The HIGHEST listed Suppression Pool water level at which the SRV T-Quenchers will be uncovered is _ _ __

A. 10:00; 57.4 inches B. 10:00; 62.9 inches

c. 10:02; 57.4 inches D. 10:02; 62.9 inches 22

ILT-09 SRO NRC EXAM

23. 245000K5 .07 001 Unit 2 is operating at 100% RTP when 2R13-C008A, Isophase Bus Cooling Unit fan, trips.

With the above conditions, The 2R13-C008B, lsophase Bus Cooling Unit fan, _ _ __

If 2R 13-COOSB subsequently trips, the MAXIMUM Unit 2 Main Generator output limit is _ _ __

A. will already be running; 12800 amps B. will already be running; 14000 amps C. must be manually started; 12800 amps D. must be manually started; 14000 amps 23

ILT-09 SRO NRC EXAM

24. 256000K6.0l 001 Unit 2 is operating at 100% RTP when a TOTAL loss of Instrument and Service Air occurs.

Based on the above conditions, The MAXIMUM listed Control Air pressure at which 2N21-Fl l l, Feedwater Startup Level Control Valve, will be LOCKED UP in its existing position is _ _ __

A. 49 psig B. 74 psig C. 84 psig D. 89 psig 24

Il.,T-09 SRO NRC EXAM

25. 25900102.4.35 001 Unit 1 is operating at 100% RTP when an event occurs requiring the Main Control Room to be evacuated.

The ONLY action taken prior to leaving the Main Control Room was to manually scram the reactor.

Control has been established at the Remote Shutdown panels.

The Shift Supervisor dispatches an operator to locally trip RFPT lA.

The operator will depress the local RFPT lA trip pushbuttons at the _ _ __

After RFPT lA is tripped locally, without any additional operator actions, RFPT lA will be _ _ __

A. Turbine Building 1H21-P216 Panel; on the turning gear B. Turbine Building 1H21-P216 Panel; windmilling C. Turbine Building RFPT lA area; on the turning gear D. Turbine Building RFPT lA area; windmilling 25

ILT-09 SRO NRC EXAM

26. 259002A3.04 001 Unit 2 is operating at 100% RTP with the following RWL indications:

o 2C32-R606A, GEMAC, indication: 37 .0 inches o 2C32-R606B, GEMAC, indication: 36.6 inches o 2C32-R606C, GEMAC, indication: 36.9 inches Subsequently, a leak occurs on the REFERENCE leg associated with the 2C32-R606A instrument resulting in a 3 inch/minute change in RWL.

Based on the above conditions and with NO operator actions, INITIALLY, the indication on RWL instrument 2C32-R606B will go _ _ __

and Feedwater flow will _ _ __

A. DOWN; DECREASE B. DOWN; INCREASE C. UP; DECREASE D. UP; INCREASE 26

ILT-09 SRO NRC EXAM

27. 261000A4.02 001 Unit 2 is operating at 100% RTP.

At 10:00, Secondary Containment receives an isolation signal.

At 10:01, the NPO secures SBGT 2A by placing the SBGT 2A fan control switch to the OFF position and then places the switch to the STBY position. (ONLY switch manipulated)

At 10:02, the following Unit 2 SPDS Diagnostic Screen is observed:

Based on the SPDS Diagnostic Screen at 10:02, The Unit 2 SBGT system _ _ _ _ operated as designed.

If SPDS becomes unavailable, Unit 2 SBGT flows can be monitored on Panels 2Hll-P657 and _ _ __

A. has; 2Hll-P654 B. has; 2Hll-P700

c. has NOT; 2Hll-P654 D. has NOT; 2Hll-P700 27

ILT-09 SRO NRC EXAM

28. 262001Al.04 001 Unit 2 is at 60% RTP with an operator transferring 4160 VAC Bus 2A to its Alternate supply.

The following conditions currently exist:

o Voltages are matched o Sync switch for the 4160 VAC 2A Alternate breaker is in the ON position o Sync light is at its dimmest (12 O'Clock position and steady) o Station SVC Interlock Cutout switch for ACB 135434-135454 is in the NORMAL (UP) position Subsequently, the operator places the control switch for ACB 135454 (Alternate supply breaker) in the close position and IMMEDIATELY releases the switch.

Based on the above conditions, Ten (10) seconds after the operator releases the control switch, the ampere indication will be as shown o n - - - - -

Figure 1 Figure 2 Figure 3 Figure 4 A. Figure 1 B. Figure 2 C. Figure 3 D. Figure4 28

ILT-09 SRO NRC EXAM

29. 262002K4.0l 001 Unit 2 is operating at 100% RTP when the following indications are received on Panel 2H 11-P651; VITAL AC Illuminated NORM PWR NORM PWR AVAILABLE NOT AVAILABLE Based on the above indications and, Fifteen (15) seconds later, the Vital AC Bus is receiving power from its Power Supply.

The Alternate AC supply for the Vital AC Bus is _ _ __

A. Alternate AC; 600V Bus 2C B. Alternate AC; 600V Bus 20

c. Backup DC; 600V Bus 2C D. Backup DC; 600V Bus 20 29

ILT-09 SRO NRC EXAM

30. 26300002.1.19 001 While monitoring SPDS on Unit 2, the following indications exist on the PCIS Diagnostic Groups l, 3, 4, & 5 Status screen; Based on the above SPDS indications, A loss of _ _ _ _ has occurred.

If HPCI receives a valid initiation signal, HPCI _ _ _ _ start and inject into the RPV.

A. 600V Rx. Bldg. MCC 2B, 2R24-S011A; will B. 600V Rx. Bldg. MCC 2B, 2R24-S011A; will NOT

c. 250 voe MCC 2B, 2R24-S022; will D. 250 VDC MCC 2B, 2R24-S022; will NOT 30

ILT-09 SRO NRC EXAM

31. 263000K5.01 001 Unit 2 is operating at 100% RTP with the "2A" and "2B" 125/250VDC Station Service Batteries on "Equalize" charge.

Subsequently, o All Control Building Chillers and fans trip and can NOT be restored o Control Building temperatures start increasing With the "2A" and "2B" 125/250VDC Station Service Batteries on "Equalize" charge, the 125/250VDC Station Service Battery Chargers output voltage will be the battery voltage.

With Control Building temperatures increasing and NO operator actions, the 125/250VDC Station Service Battery _ _ __

A. equal to; Room Hydrogen concentrations will rise in each of the battery rooms B. equal to; Chargers will trip when their high temperature trip setpoint is reached C. greater than; Room Hydrogen concentrations will rise in each of the battery rooms D. greater than; Chargers will trip when their high temperature trip setpoint is reached 31

ILT-09 SRO NRC EXAM

32. 264000A3.06 001 Unit 1 and Unit 2 are operating at 100% RTP when a TOTAL Loss Of Offsite Power (LOSP) occurs.

The Diesel Gen lB Keylock control switch is in the REMOTE UNIT 1 position.

With the above conditions, The automatic start of the Standby Diesel Service Water Pump, 2P41-C002, can be monitored for operation at _ _ __

INITIALLY, the Standby Diesel Service Water Pump, 2P41-C002 will be powered from 4160V _ _ __

A. 2Hll-P652 ONLY; lF B. 2Hll-P652 ONLY; 2F C. 2Hll-P652 and 1Hl 1-P652; lF D. 2Hl 1-P652 and 1Hl 1-P652; 2F 32

ILT-09 SRO NRC EXAM

33. 271000K4.0I 001 Which ONE of the choices below describes the reason for air purging the Off-Gas system for one hour prior to placing the system in operation following a Refueling Outage?

A. To provide cooling air to the hydrogen recombiner B. To dilute any hydrogen left in the system from previous use C. To provide cooling air to the post treatment radiation monitors D. To remove any radioactive Iodine deposited on the charcoal adsorbers 33

ILT-09 SRO NRC EXAM

34. 272000A3.02 001 Post Treatment Radiation Monitor Channel "A" and Channel "B" _ _ __

will cause an automatic isolation of the Unit 2 Main Stack Isolation valve, 2N62-F057.

A. INOP; DOWNSCALE B. INOP; HIGH-HIGH C. HIGH; DOWNSCALE D. HIGH; HIGH-HIGH 34

ILT-09 SRO NRC EXAM

35. 288000Kl .04 001 On Unit 1, Cooling water to the Safeguard Equipment Cooling (SEC) coolers is supplied by the System.

Cooling water to the Main Control Room Air Conditioning Unit Condensers is supplied by the System.

A. Reactor Building Chilled Water; Plant Service Water B. Reactor Building Chilled Water; Control Building Chilled Water C. Plant Service Water; Plant Service Water D. Plant Service Water; Control Building Chilled Water 35

ILT-09 SRO NRC EXAM

36. 290001A4.02 001 Unit 1 is operating at 100% RTP with RWCU Pump lA in service.

NPOs in the Main Control Room, monitoring the RWCU System, observe the following:

RWCUHX Time Room Temp 10:55 125°F 11:00 145°F 11:05 168°F Based on the above conditions, When the RWCU Hx Room temperatures reached their isolation setpoint, the RWCU System should have automatically isolated _ _ __

The EARLIEST listed time that the NPO is procedurally required to manually isolate the RWCU System is _ _ __

A. immediately; 11:00 B. immediately; 11:05

c. after a time delay; 11:00 D. after a time delay; 11:05 36

ILT-09 SRO NRC EXAM

37. 295001AA2.06 001 A Unit 2 startup is in progress IAW 3400-0PS-001-2, Plant Startup.

The following sequence of events occur:

o Both Recirc Pump speeds were raised from minimum speed to 30%

o After the Recirc Pump speeds were raised, ASD 2A tripped With the above current conditions, To manually calculate core flow rate, Loop "A" Jet Pump flow, 2B21-R611A, must be Loop "B" Jet Pump Flow, 2B21-R611B.

Core Flow Recorder, 2B21-R613, _ _ _ _ be indicating accurate core flow.

A. subtracted from; will NOT B. subtracted from; will

c. added to; will NOT D. added to; will 37

ILT-09 SRO NRC EXAM

38. 295003AK2.04 001 Unit 1 was operating at 100% RTP when a Loss of Offsite Power occurred.

The following conditions exist:

o "lE" 4160 VAC Bus........................ DE-ENERGIZES and remains de-energized o "lF" 4160 VAC Bus........................ ENERGIZED o "lG" 4160 VAC Bus........................ DE-ENERGIZES and remains de-energized With NO operator actions and based on the above conditions, The PSW System WILL supply cooling water to the _ _ __

The TOTAL number of PSW pumps supplying cooling water to these buildings is _ _ __

A. Reactor Building and Diesel Building ONLY; one (1)

B. Reactor Building and Diesel Building ONLY; two (2)

C. Reactor Building, Turbine Building and Diesel Building; one (1)

D. Reactor Building, Turbine Building and Diesel Building; two (2) 38

ILT-09 SRO NRC EXAM

39. 295004AK2.0l 001 Unit 2 is operating at 100% RTP when the following sequence of events occur:

At 11:00 - 125/250V DC SWITCHGEAR 2B, 2R22-S017, de-energized due to a fault on one of the previously in service Division II 125 VDC Battery Chargers At 11 :30 - Maintenance replaced the Di vision II Battery Fuses and 2R22-SO 17 is re-energized from the Division II Batteries IAW 34SO-R42-001-2, 125 VDC & 125/250 VDC System and with the above conditions, Local manipulation of a Throwover Switch REQUIRED to return the new combination of Division II 125 VDC Battery Chargers to service.

When placing a Battery Charger in service, the proper sequence of AC Input and DC Output breaker operation is to FIRST position the breaker to the ON position.

A. is; AC Input B. is; DC Output

c. is NOT; AC Input D. is NOT; DC Output 39

ILT-09 SRO NRC EXAM

40. 295005AK3.02 001 Unit 1 is operating late in core life with the EOC RPT breakers in service.

If the Main Turbine trips, the MINIMUM reactor power level which will result in an EOC RPT breaker trip is _ _ __

The trip of the EOC RPT breakers is designed to prevent exceeding the _ _ _ _ limit.

A. 24.0%;

APLHGR B. 24.0%;

MCPR

c. 27.6%;

APLHGR D. 27.6%;

MCPR 40

ILT-09 SRO NRC EXAM

41. 295006G2.l.31 001 Unit 2 is operating at 100% RTP with the 2Cl 1-F002A, Flow Control Valve, in service.

Subsequently, a transient occurs resulting in RWL lowering to -10 inches (lowest RWL reached) before being restored to normal with Feedwater.

FLOW CONTROL VLV 2C11-F002A Illuminated +

FLOW CONTROL VLV 2C11-F002B One (1) minute later and based on the above indications/conditions, 2C 11-F002A _ _ _ _ responding correctly.

2C 11-F002A indicating LIGHTS are located on _ _ __

A. is; 2Hl 1-P603 and locally at the 2C82-P001, Remote Shutdown Panel B. is; 2Hll-P603 Panel ONLY C. is NOT; 2Hl l-P603 and locally at the 2C82-P001, Remote Shutdown Panel D. is NOT; 2Hll-P603 Panel ONLY 41

ILT-09 SRO NRC EXAM

42. 29500802.1.20 001 Unit 2 was operating at 100% RTP when a transient resulted in the following:

o RWL increased to 102 inches o RPV pressure is 490 psig A NPO placed the control switch for Safety Relief Valve, 2B21-F013M, in the OPEN position.

Based on the above conditions and when 2B21-F013M control switch is placed to OPEN, INITIALLY, 2B21-F013M will be passing _ _ __

2B21-F013M "Amber" indicating light will ILLUMINATE _ _ __

A. steam; immediately B. steam; after several seconds

c. water; immediately D. water; after several seconds 42

ILT-09 SRO NRC EXAM

43. 295014AA2.04 001 Unit 2 is operating at 65% RTP when an inadvertent initiation of HPCI occurs.

HPCI injects at rated flow for approximately 45 seconds before the NPO secures HPCI.

The STA generates a Process Computer Monitoring Case Report which indicates the following:

MFLCPR 1.013 MFLPD 0.974 MAPRAT 0.936 PCRAT 1.101 With the above conditions, The limit for _ _ _ _ has been EXCEEDED.

A. MFLCPR B. MFLPD C. MAPRAT D. PCRAT 43

ILT-09 SRO NRC EXAM

44. 295015AKI.02 001 Unit 1 was operating at 100% RTP when an ATWS occurred.

o SBLC System was initiated o SBLC Tank level is now 12%

Based on the current conditions, Cold Shutdown Boron Weight (CSBW) been injected.

If a RPV pressure reduction occurs, Reactor power to the point of Criticality.

A. has NOT; can increase B. has NOT; can NOT return C. has; can increase D. has; can NOT return 44

ILT-09 SRO NRC EXAM

45. 29501602.4.l I 001 An evacuation of the Main Control Room has occurred.

o The Unit 1 Reactor was NOT scrammed prior to leaving the Control Room o SPDS is NOT available IAW 31RS-OPS-001-l, Shutdown From Outside Control Room, Guidance is given to LOCALLY scram the reactor by tripping the Scram Discharge Volume (SDV) _ __

This procedure provides guidance to confirm the Reactor is shutdown by visually verifying that each _ _ __

A. Thermal Level Switches; SDV Vent and Drain valve is CLOSED B. Thermal Level Switches; HCU Scram Inlet and Outlet valve is OPEN C. Float Level Switches; SDV Vent and Drain valve is CLOSED D. Float Level Switches; HCU Scram Inlet and Outlet valve is OPEN 45

ILT-09 SRO NRC EXAM

46. 295018AA2.02 001 Unit 2 is operating at 100% RTP.

CONDENSER ROOM FLOODING, 650-164, alarm is received.

o 2P41-F316A-D, Turbine Bldg Isolation Valves, indicate closed Based on the above conditions, RBCCW suction temperature will _ _ __

2P41-F316A-D _ _ _ _ be overridden and re-opened from the MCR.

A. start increasing; can B. start increasing; can NOT C. remain approximately the same; can D. remain approximately the same; can NOT 46

ILT-09 SRO NRC EXAM

47. 295019AAI.02001 Unit 2 is operating at 100% RTP when a complete (100%) rupture on the Non-Essential Instrument Air Header, down stream of 2P52-F015, occurs.

This line breaks Alier Filler 1>102A FOi iA FOIS FO ll B F565 With NO operator action, the 2P52-F015, Turb. Bldg Inst Air To RW Bldg lsol valve, will _ _ __

The setpoint for 2P52-F565, Rx Bldg Inst N2 To Non-Int Air EL 185 lsol Vlv, to automatically open is _ _ __

A. close and remain closed; 70 psig B. close and remain closed; 80 psig C. continously cycle open and closed; 70 psig D. continously cycle open and closed; 80 psig 47

ILT-09 SRO NRC EXAM

48. 295020AAI.02 001 Nitrogen (N2) is being added to the Unit 2 Drywell (DW) from the Unit 1 N2 Storage Tank IAW 34SO-T48-002-2, Containment Atmosphere Control and Dilution System.

o 2T48-Fl 13, Nitrogen to DW isolation valve, is OPEN o 2T48-Fl 14, Nitrogen to DW isolation valve, is OPEN o DW venting using Standby Gas Treatment is in progress An inadvertant loss of the 2A Reactor Protection System (RPS) bus occurred.

N2 addition to the DW will _ _ __

A loss of DW cooling _ _ _ _ IMMEDIATELY occur.

A. continue; will NOT B. continue; will C. automatically isolate; will NOT D. automatically isolate; will 48

ILT-09 SRO NRC EXAM

49. 295021AK3.01 001 With the plant shutdown in Mode 4 and RHR loop "B" operating in Shutdown Cooling (SOC),

a leak occurs resulting in a SOC isolation due to low RWL.

Recirc suction temperature is 170°F.

IAW 34AB-El 1-001-2, Loss of Shutdown Cooling, RWL will be raised to a MINIMUM of 53 inches as indicated on _ _ __

The reason RWL is raised is to _ _ __

A. 2B21-R605, Floodup Range; increase coolant inventory ONLY B. 2B21-R605, Floodup Range; increase coolant inventory AND ensure a flow path for natural circulation C. 2C32-R606A, Narrow Range; increase coolant inventory ONLY D. 2C32-R606A, Narrow Range; increase coolant inventory AND ensure a flow path for natural circulation 49

ILT-09 SRO NRC EXAM

50. 295023AK1.03 001 Unit 1 is in Mode 5 with fuel movement in progress.

o RPS Shorting Links INSTALLED o A fuel bundle is on the Main Grapple in the Normal Up position The Reactor Cavity and Fuel Pool water levels start to decrease.

The fuel bundle on the Main Grapple is lowered back into the RPV core and seated.

o The count rate on SRM A increases to 300 cps with a stable positive period indicated Based on the above conditions:

IA W 34AB-G41-002- l, Decreasing Rx Well/Fuel Pool Water Level, the grappled fuel bundle was required to be placed in-core location.

If SRM A continues to increase, SRM A _ _ _ _ automatically initiate a FULL Scram.

A. ONLY in its proper; will B. ONLY in its proper; will NOT

c. into ANY; will D. into ANY; will NOT 50

ILT-09 SRO NRC EXAM

51. 295024EA2.08 001 Unit 2 was operating at 55% RTP, due to a fuel leaker, when a steam line break inside containment occurs.

Plant conditions are below:

o Drywell pressure is 10.5 psig and slowly increasing o Drywell radiation is 2.0 E2 R/hr and steady o Torus pressure is 10.0 psig and slowly increasing o Neither Drywell or Torus sprays have been initiated With the above conditions, At this time, ____ Sprays are REQUIRED to be placed in service.

The AMBER light above 2T48-F3 l 8, Torus Vent Valve, will be _ _ __

A. BOTH Drywell and Torus; extinguished B. BOTH Drywell and Torus; illuminated C. ONLY Torus; extinguished D. ONLY Torus; illuminated 51

ILT-09 SRO NRC EXAM

52. 203000A2.14 001 Unit 2 is operating at 25% RTP with the following alarm status:

RHR RHR RELAY LOGIC B RELAY LOGIC A POWER FAILURE POWER FAILURE I(601-201)1 I(601-211) I Illuminated Extinguished Subsequently, Drywell pressure increases and stabilizes at 4.5 psig.

IAW 34SO-Ell-010-2, RHR System, and with the current status of the above alarms and plant conditions, RHR pump 2B _ _ __

If RHR Pump 2B is subsequently secured and then the RHR Pump 2B RESET pushbutton is depressed and released, RHR Pump 2B automatically start.

A. must be manually started; will B. must be manually started; will NOT C. will automatically start; will D. will automatically start; will NOT 52

ILT-09 SRO NRC EXAM

53. 295026EK1.02 001 Unit 2 is operating at 100% RTP when a leak occurs inside the Orywell (OW).

Steam condensation from the leak will cause Torus water temperature to heat up _ _ _ __

IA W 3IEO-EOP-012-2, PC Primary Containment Control, the LOWEST listed Torus temperature requiring entry into RC Point A of 31EO-EOP-010-2, RC RPV Control (NON-ATWS), is _ _ __

A. uniformly throughout the Torus due to the design of the downcomers; lll°F B. uniformly throughout the Torus due to the design of the downcomers; 121°F C. directly under the area of the OW leak due to the energy being distributed directly to the Torus water in that area; 111°F

0. directly under the area of the OW leak due to the energy being distributed directly to the Torus water in that area; 121°F 53

ILT-09 SRO NRC EXAM

54. 29502802.1.25 001 Unit 2 has experienced a LOCA.

The following conditions exist:

o RTD 2T47-N001A 300°F o RTD 2T47-N001K 275°F o RPV pressure 700 psig and steady o 2B21-R623B, Wide Range (compensated) -90 inches Based on the above conditions, and IAW 34AB-B21-002-2, RPV Water Level Corrections, Corrected RWL is _ _ __

Reference Provided A. -27 inches B. -40 inches C. -99 inches D. -102 inches 54

ILT-09 SRO NRC EXAM

55. 295030EAI.05 001 Unit 1 was scrammed from 80% RTP.

o RPV pressure is being controlled by LLS o RWL is -50 inches and steady o HPCI is the ONLY high pressure injection source o Torus level is 116 inches and decreasing at 2 inches/minute IAW 31EO-EOP-012-l, Primary Containment Control, One (1) minute later, the HPCI System _ _ _ _ ALLOWED to continue injecting into the RPV.

Ten (10) minutes later, the Ring Header DOWNCOMER openings are _ _ __

A. is NOT; COVERED B. is NOT; UNCOVERED

c. is; COVERED D. is; UNCOVERED 55

ILT-09 SRO NRC EXAM

56. 295031 EK2.09 001 Unit 2 is at 60% RTP with the following conditions:

o 2A RFP is in AUTOMATIC o 2B RFP has just been transferred to the M/A Station Subsequently, RFP 2A experiences a malfunction that results in RFP 2A speed lowering to 2100 rpm and stabilizes.

o RWL is recovered to normal using the RFP 2B o LOWEST RWL reached was 0 inches With the above conditions, Of the listed RWL values, the HIGHEST RWL at which a Recirc Pump runback signal will FIRST be generated is _ _ __

The FINAL Recirc Pump speed will be _ _ __

A. 29 inches; 22%

B. 29 inches; 33%

c. 31 inches; 22%

D. 31 inches; 33%

56

ILT-09 SRO NRC EXAM

57. 295032EK3.03 001 Unit 2 is operating at 100% RTP when a pipe ruptures in the Torus Area.

The RCIC System has automatically isolated due to high temperatures in the Torus Area.

IAW 34SO-E51-001-2, Reactor Core Isolation Cooling (RCIC) System, the time delay for the RCIC isolation is _ _ __

The reason for the RCIC System isolation at this setpoint is _ _ __

A. 29 minutes; because the Max Safe Operating temperature limit has been exceeded B. 29 minutes; to limit radioactive release to the public C. 14 minutes; because the Max Safe Operating temperature limit has been exceeded D. 14 minutes; to limit radioactive release to the public 57

ILT-09 SRO NRC EXAM

58. 295033EK2.02 001 Maintenance is in the process of removing the Unit 2 Steam Dryer from the RPV when the Steam Dryer momentarily becomes partially uncovered.

Radiation Protection (RP) reports NO Airborne Contamination exists.

ALL Unit 2 Refueling Floor Area Radiation Monitors (ARMs) increase to 17 mr/hr before lowering to their pre-event value.

With the above conditions and NO operator actions, The Unit 2 SBGT System fans will _ _ __

The Main Control Room Environmental Control (MCREC) System will _ _ __

A. have automatically started; have aligned to Pressurization Mode B. have automatically started; remain in the Normal Mode C. remain in Standby; have aligned to Pressurization Mode D. remain in Standby; remain in the Normal Mode 58

ILT-09 SRO NRC EXAM

59. 295036EA1.04 001 On a loss of 2R25-S064, Instrument Bus 2A, Secondary Containment (SC) radiation levels be monitored by using area radiation monitoring (ARM) instrumentation located in the Main Control Room.

Personnel _ _ _ _ to determine that Max Normal SC Water level has been exceeded.

A. canNOT; can use the Main Control Room SC sump alarms by themselves B. can NOT; must be dispatched LOCALLY C. can; can use the Main Control Room SC sump alarms by themselves D. can; must be dispatched LOCALLY 59

ILT-09 SRO NRC EXAM

60. 295037EK3.03 001 Unit 2 was operating at 100% RTP when an ATWS occurred.

RC-1 actions are completed.

Reactor power stabilizes at 8% RTP.

Based on the above conditions, the Recirc pumps are _ _ __

IA W the EOPs, RWL will be intentionally lowered in order to _ _ __

A. tripped; DECREASE core inlet subcooling by UNCOVERING feedwater spargers B. tripped; INCREASE void fraction inside the core shroud ONLY C. operating at minimum speed; DECREASE core inlet subcooling by UNCOVERING feedwater spargers D. operating at minimum speed; INCREASE void fraction inside the core shroud ONLY 60

ILT-09 SRO NRC EXAM

61. 295038EAl.Ol 001 The Shift Manager has declared an Emergency.

The following Main Stack annunciators are illuminated on Unit 1:

o OFF GAS VENT RADIATION HIGH-HIGH (601-412) o OFF GAS VENT RADIATION HIGH (601-418)

The SS has directed NMP-EP-104-F07, Offsite Dose Assessment Hatch Prompt Offsite Dose Assessment, (PODA), to be performed.

The current normal average daily site dose rate is 1.0 E-3 mR/hr.

The result from the PODA is a peak TEDE dose rate of 2.0 E-2 mR/hr.

Based on the above conditions, The Main Stack Effluent Accident Range Gas Monitors (KAMANs) _ _ __

IAW NMP-EP-104-F07, a radioactive release from the Main Stack _ _ _ _ in progress.

A. have automatically started; is B. have automatically started; is NOT C. are in standby; is D. are in standby; is NOT 61

ILT-09 SRO NRC EXAM

62. 30000002.2.44 001 Unit 2 is operating at 100% RTP when 34AB-P51-001-2, Loss of Instrument or Service Air System or Water Intrusion into the Service Air System, is entered due to lowering air pressure.

The following conditions exist, o 2P52-F565, Rx Bldg Inst N2 To Non-Int Air El. 185 Isol Viv, Danger Tagged CLOSED o SCRAM VLV PILOT AIR HOR PRESS HIGH/LOW (603-131) is illuminated o CRD HYO TEMP HIGH (603-140) is illuminated Based on the above conditions and IA W 34AB-P51-001-2, A Reactor scram _ _ _ _ required to be inserted at this time.

If the crosstie between Unit 1 and Unit 2 Service Air Systems CANNOT be opened, the MSIVs will drift close as air pressure continues to lower.

A. is; Inboard B. is; Outboard

c. is NOT; Inboard D. is NOT; Outboard 62

ILT-09 SRO NRC EXAM

63. 400000K4.01 001 Unit 2 is operating at 30% RTP.

o Two (2) RBCCW pumps are running o One ( 1) RBCCW pump is Danger tagged out of service The following sequence of events occur:

At 11:00- A loss of a 600V bus results in one (1) of the running RBCCW pumps being de-energized At 11 :03 - RBCCW system pressure decreases below the RBCCW pump auto start setpoint At 11 :05 - Power is restored to the 600V bus Based on the above plant conditions, After power is restored to the 600V bus, the Non-Essential Load Lockout pushbutton REQUIRED to be depressed prior to the restart of the associated RBCCW pump.

Prior to restarting the associated RBCCW pump, its control switch _ _ _ _ REQUIRED to first be placed in the STOP position and then released.

A. is; is B. is; is NOT

c. is NOT; is D. is NOT; is NOT 63

ILT-09 SRO NRC EXAM

64. 600000AKI.02 001 Which ONE of the following plant fire locations REQUIRES a manual reactor scram IAW 34AB-X43-001-2, Fire Procedure, when a major fire exists?

A. Turbine Building East Cableway B. Unit Auxilary Transformer C. Oil Storage Tank Room D. Intake Structure 64

ILT-09 SRO NRC EXAM

65. 70000002.2.44 001 Following a grid disturbance, all Unit 2 4160 VAC Emergency Bus voltages indicate 4000 VAC.

IAW 34AB-S 11-001-0, Operation With Degraded Voltage; The 4160 VAC Emergency Bus voltages are _ _ _ the MINIMUM ACCEPTABLE voltage.

If ALL Unit 2 4160 VAC Emergency Bus voltages are less than the MINIMUM ACCEPTABLE voltage for one (1) hour, required to be manually started and connected to the respective Unit 2 Emergency Bus(es).

A. less than; one (1) EDG is B. less than; two (2) EDGs are

c. greater than; one (1) EDG is D. greater than; two (2) EDGs are 65

ILT-09 SRO NRC EXAM

66. G2.1.23 001 Unit 2 is performing Low Pressure Feedwater Injection IAW 34SO-N21-007-2, Condensate and Feedwater System, during a Reactor startup.

The following conditions exist:

o One Condensate Pump is running o One Condensate Booster Pump running o Condensate/Feed system is lined up for injection o Turbine Bypass valves are controlling RPV pressure o 2N21-F165, Cleanup Recirc FCV, is throttled open to maintain RWL IAW 34SO-N21-007-2 and based on the above conditions, To avoid excessive vibration on the associated piping, the MAXIMUM throttled position allowed for 2N21-F165 is _ _ __

As RPV pressure increases, 2N21-F165 will be throttled in the _ _ _ _ direction.

A. 55%;

close B. 55%;

open

c. 70%;

close D. 70%;

open 66

ILT-09 SRO NRC EXAM

67. G2.1.40 001 Unit 2 is performing fuel movement in the RPV.

IRM A and IRM B are bypassed.

IAW 34FH-OPS-001-0, Fuel Movement Operation, The Reactor Mode Switch is REQUIRED to be LOCKED in the _ _ _ _ position.

The MINIMUM RPV water level for fuel movement to continue is _ _ _ _ above the top of the irradiated fuel assemblies seated in the RPV.

A. REFUEL; 21 feet B. REFUEL; 23 feet C. SHUTDOWN; 21 feet D. SHUTDOWN; 23 feet 67

Il..T-09 SRO NRC EXAM

68. G2.2.21 001 Given the following:

lEll-FOl 7A, RHR Injection valve, was declared INOPERABLE for preventative maintenance (PM).

Following the PM, operators performed the stroke test on 1Ell-F017A IAW 34SV-Ell-002-l, RHR Valve Operability.

The stroke test data is shown below:

Column1 Colurm2 Cokml 3 Collmn4 Columns CALCUl.AlID Al..L<JNABl..E Refeience S1roke CFERATING ThES MAXMl.JM TIME LIMIT llMES VALVE NO. OPER TIME (SEC) (SEC) (SEC) (SEC)

OPEN CLOSE OPEN CLOSE OPEN CLOSE OPEN CLOSE 1E11.f017A WO/ 242 NA 20.6 27.8 t-IA NIA 30.5 NA ~34 t-IA IA W 34SV-El 1-002-l, To time 1Ell-F017A OPEN, the NPO will START the stopwatch when the _ _ __

Based on the above data, the opening stroke time for 1Ell-F017A _ _ _ _ satisfactory.

A. control switch is placed to OPEN; is B. control switch is placed to OPEN; is NOT C. red light FIRST illuminates; is D. red light FIRST illuminates; is NOT 68

ILT-09 SRO NRC EXAM

69. G2.2.36 00 l Unit 1 and Unit 2 are operating at 100% RTP. On your Control Room tour during turnover, you note the change in status in the Standby Gas Treatment System (SBGT) as shown below:

FLTR DISCH FLTR DISCH 2T46-F002A 2T46-F002B With the above status of SBGT, if a troubleshooting activity resulted in tripping the feeder breaker to , an additional LCO entry would be required for the SBGT System.

A. 2R24-S011, Rx. Bldg. MCC 2C B. 2R24-S012, Rx. Bldg. MCC 2B C. 2R24-S013, Rx. Bldg. MCC 2A D. 2R24-S014, Rx. Bldg. MCC 2D 69

ILT-09 SRO NRC EXAM

70. G2.3.l l 001 Which ONE of the following is the BASIS for restarting the Turbine Building (TB) Ventilation when executing 31EO-EOP-014-2, SC Secondary Containment Control - RR Radioactivity Release Control?

Restarting the TB Ventilation AND assures a release from the TB Ventilation System is monitored prior to exiting the _ _ __

A. preserves personnel accessibility; Main Stack B. preserves personnel accessibility; Reactor Building Stack C. maintains equipment operability; Main Stack D. maintains equipment operability; Reactor Building Stack 70

ILT-09 SRO NRC EXAM

71. G2.3.13 001 Two NPOs and a RP Tech are entering a room to perform a tagout.

o The dose rate in this area is 1200 mR/hr IA W 62RP-RAD-016-0, Control Of High Radiation Areas, This room will be posted as a Area.

After exiting this Radiation Area, the door be concurrently verified secure by one of the NPOs.

A. Locked High Radiation; can B. Locked High Radiation; can NOT

c. Very High Radiation; can D. Very High Radiation; can NOT 71

ILT-09 SRO NRC EXAM

72. G2.3.14 001 34SV-E51-002-l, RCIC Pump Operability, will be performed within the next hour.

RCIC is located in the _ _ _ _ diagonal.

IA W 34SV-E51-002-l, the RCIC diagonal _ _ _ _ REQUIRED to be posted as a High Radiation Area during the RCIC run.

A. Southwest; is NOT B. Southwest; is

c. Northwest; is NOT D. Northwest; is 72

ILT-09 SRO NRC EXAM

73. G2.4.21 001 Unit 2 is cooling down with RHR Loop "B" in Shutdown Cooling Mode.

o RPV pressure is 115 psig Subsequently, a leak occurs in the Drywell resulting in Drywell pressure increasing to 1.9 psig.

Based on the above conditions and with NO operator actions, RHR Loop "B" REMAIN in the Shutdown Cooling Mode.

HPCI AUTOMATICALLY start and inject into the RPV.

A. will; will B. will; will NOT

c. will NOT; will D. will NOT; will NOT 73

ILT-09 SRO NRC EXAM

74. G2.4.32 001 Unit 2 was operating at 100% RTP when a loss of electrical power results in a loss of a significant number of Main Control Room annunciators (P603, P602 & P601) with a Reactor scram.

o An Alert Emergency classification is declared IAW NMP-EP-111-002, Emergency Notification Network Communicator Instructions - Hatch, The LATEST that the INITIAL Plant Page Announcement can be made is _ _ __

after the Emergency classification is declared.

Subsequent Plant Page Announcements are REQUIRED to be performed at _ _ __

intervals after the INITIAL Plant Page Announcement is made.

A. 14 minutes; 30 minute B. 14 minutes; 15 minute

c. 29 minutes; 30 minute D. 29 minutes; 15 minute 74

ILT-09 SRO NRC EXAM

75. G2.4.49 001 Unit 2 is at 100% RTP when a loss of Feedwater Heating event occurs.

IA W 34AB-N21-001-2, Loss Of Feedwater Heating, The Immediate Operator Action is to depress the _ _ __

The feed water temperatures (4) shown on SPDS _ _ _ _ to determine Final Feedwater Temperature.

A. Individual Recirc Flow Control LOWER FAST pushbuttons; can be read directly B. Individual Recirc Flow Control LOWER FAST pushbuttons; must be averaged C. Master Recirc Flow Control LOWER FAST pushbutton; can be read directly D. Master Recirc Flow Control LOWER FAST pushbutton; must be averaged 75

ILT-09 SRO NRC EXAM ANSWER KEY 1.

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NRC RO REFERENCES RO EXAM

1. 34AB-B21-002-2, RPV Water Level Corrections, Att. 1, Att. 3 & Att. 4

SNC PLANT E. I. HATCH Pg 5 of 14 DOCUMENT TITLE: DOCUMENT NUMBER: Ver No:

RPV WATER LEVEL CORRECTIONS 34AB-B21-002-2 6.15 ATTACHMENT 1 Att. Pg.

TITLE: DRYWELL RTD GROUPS AND CAUTION 1 AND 2 1 of 3 RTD INDICATOR PANEL RTD GROUP 1

• 2T47-N001K 2T47-R627, Point 8 2H11-P650

• 2T47-N010 2T47-R627, Point 13 2H11-P650

• 2T47-N014 2T47-R620 2H11-P657 RTD GROUP 2

• 2T47-N001A 2T47-R626, Point 7 2H11-P657

• 2T47-N002 2T47-R626, Point 10 2H11-P657

• 2T47-N015 2T47-R621 2H11-P654 RTD GROUP 3

• 2T47-N003 2T47-R627, Point 10 2H11-P650

• 2T47-N001M 2T47-R627, Point 9 2H11-P650 RTD GROUP 4

• 2T47-N001L 2T47-R626, Point 9 2H11-P657

• 2T47-N009 2T47-R626, Point 14 2H11-P657 SPDS Indications may be used for RTD temperature indications

SNC PLANT E. I. HATCH Pg 6 of 14 DOCUMENT TITLE: DOCUMENT NUMBER: Ver No:

RPV WATER LEVEL CORRECTIONS 34AB-B21-002-2 6.15 ATTACHMENT 1 Att. Pg.

TITLE: DRYWELL RTD GROUPS AND CAUTION 1 AND 2 2 of 3 CAUTION 1 RPV WATER LEVEL INSTRUMENT MAY BE USED ONLY WHEN BOTH OF THE FOLLOWING CONDITIONS ARE MET FOR THAT INSTRUMENT:

1. THERE IS NO INDICATION OF ERRATIC INSTRUMENT BEHAVIOR (BOILING COULD OCCUR WHEN THE HIGHEST TEMPERATURE IN THE RTD GROUP IS ABOVE THE RPV SATURATION TEMPERATURE (ATTACHMENT 2 OR SPDS).

INCREASE INSTRUMENT MONITORING WHEN RPV SATURATION TEMPERATURE FOR INSTRUMENT IS REACHED.

INSTRUMENT RTD GROUP NARROW RANGE (0 to +60 IN.)

- 2C32-R606A & C 1

- 2C32-R606B 2 WIDE RANGE (-150 to +60 IN.)

- 2B21-R604A & R623A 1

- 2B21-R604B & R623B 2 FLOODUP RANGE (-0 to +400 IN.)

- 2B21-R605 1&2 FLOODUP RANGE (0 to +200 IN.)

- 2C32-R655 1&2 FUEL ZONE RANGE (-317 TO -17 IN.)

- 2B21-R623B 2&3

- 2B21-R623A 1&4

SNC PLANT E. I. HATCH Pg 7 of 14 DOCUMENT TITLE: DOCUMENT NUMBER: Ver No:

RPV WATER LEVEL CORRECTIONS 34AB-B21-002-2 6.15 ATTACHMENT 1 Att. Pg.

TITLE: DRYWELL RTD GROUPS AND CAUTION 1 AND 2 3 of 3 CAUTION 1 (CONTINUED)

2. FOR THE FOLLOWING TABLE, THE WATER LEVEL INSTRUMENT READS ABOVE MINIMUM INDICATED LEVEL FOR THE ASSOCIATED MAXIMUM RUN TEMPERATURE MEASURED BY THE HIGHEST TEMPERATURE IN THE ASSOCIATED RTD GROUP.

MINIMUM

a. NARROW RANGE (0 TO +60 IN.) INDICATED MAXIMUM RUN LEVEL (IN.) TEMPERATURE (°F)

INSTRUMENT RTD GROUP 0 UP TO 273 6 274 TO 350 2C32-R606A & C 1 2C32-R606B 2 9 351 TO 399 27 400 OR ABOVE MINIMUM

b. WIDE RANGE

(-150 TO +60 IN) INDICATED MAXIMUM RUN LEVEL (IN.) TEMPERATURE (°F)

- 150 UP TO 197 INSTRUMENT RTD GROUP - 130 198 TO 350 2B21-R604A & R623A 1 - 122.5 351 TO 399 2B21-R604B & R623B 2 - 90 400 OR ABOVE MINIMUM

c. FLOODUP RANGE INDICATED MAXIMUM RUN LEVEL (IN.) TEMPERATURE (°F)

INSTRUMENT RTD GROUP 0 UP TO 190 2B21-R605 1 16 191 TO 250 (0 TO +400 IN.)

46 251 TO 350 2C32-R655 2 (0 TO +200 IN.) 60 351 TO 399 102 400 OR ABOVE

d. FUEL ZONE

(-317 TO -17 IN.) MINIMUM INDICATED MAXIMUM RUN INSTRUMENT RTD GROUP LEVEL (IN.) TEMPERATURE (°F)

- 317 UP TO 280 2B21-R623B 2

- 299 281 AND ABOVE 2B21-R623A 1

SNC PLANT E. I. HATCH Pg 9 of 14 DOCUMENT TITLE: DOCUMENT NUMBER: Ver No:

RPV WATER LEVEL CORRECTIONS 34AB-B21-002-2 6.15 ATTACHMENT 3 Att. Pg.

TITLE: 2B21-R623A AND B FUEL ZONE UNCOMPENSATED SIGNAL LEVEL 1 of 2 CORRECTION TABLE CORRECTED LEVEL IND IND 0 200 400 600 800 LEVEL LEVEL PSIG PSIG PSIG PSIG PSIG

-17 -28 11 31 48 65 -17

-20 -31 7 28 45 61 -20

-25 -36 2 22 39 55 -25

-30 -41 -4 16 33 48 -30

-35 -46 -9 10 27 42 -35

-40 -51 -15 4 21 36 -40

-45 -56 -20 -1 15 30 -45

-50 -61 -26 -7 9 23 -50

-55 -66 -31 -13 3 17 -55

-60 -71 -37 -19 -4 11 -60

-65 -76 -42 -25 -10 5 -65

-70 -81 -48 -30 -16 -2 -70

-75 -86 -54 -36 -22 -8 -75

-80 -91 -59 -42 -28 -14 -80

-85 -96 -65 -48 -34 -20 -85

-90 -101 -70 -54 -40 -27 -90

-95 -106 -76 -59 -46 -33 -95

-100 -111 -81 -65 -52 -39 -100

-105 -116 -87 -71 -58 -46 -105

-110 -121 -92 -77 -64 -52 -110

-115 -126 -98 -83 -70 -58 -115

-120 -131 -103 -88 -76 -64 -120

-125 -136 -109 -94 -82 -71 -125

-130 -141 -114 -100 -88 -77 -130

-135 -146 -120 -106 -94 -83 -135

-140 -151 -125 -112 -100 -89 -140

-145 -156 -131 -117 -106 -96 -145

-150 -161 -136 -123 -112 -102 -150

-155 -166 -142 -129 -118 -108 -155

-160 -171 -147 -135 -124 -114 -160

-165 -176 -153 -141 -130 -121 -165

SNC PLANT E. I. HATCH Pg 10 of 14 DOCUMENT TITLE: DOCUMENT NUMBER: Ver No:

RPV WATER LEVEL CORRECTIONS 34AB-B21-002-2 6.15 ATTACHMENT 3 Att. Pg.

TITLE: 2B21-R623A AND B FUEL ZONE UNCOMPENSATED SIGNAL LEVEL 2 of 2 CORRECTION TABLE CORRECTED LEVEL IND IND 0 200 400 600 800 LEVEL LEVEL PSIG PSIG PSIG PSIG PSIG

-170 -181 -158 -146 -136 -127 -170

-175 -186 -164 -152 -142 -133 -175

-180 -191 -170 -158 -148 -139 -180

-185 -196 -175 -164 -154 -146 -185

-190 -201 -181 -170 -161 -152 -190

-195 -206 -186 -175 -167 -158 -195

-200 -211 -192 -181 -173 -164 -200

-205 -216 -197 -187 -179 -171 -205

-210 -221 -203 -193 -185 -177 -210

-215 -226 -208 -199 -191 -183 -215

-220 -231 -214 -204 -197 -189 -220

-225 -236 -219 -210 -203 -196 -225

-230 -241 -225 -216 -209 -202 -230

-235 -246 -230 -222 -215 -208 -235

-240 -251 -236 -228 -221 -214 -240

-245 -256 -241 -234 -227 -221 -245

-250 -261 -247 -239 -233 -227 -250

-255 -266 -252 -245 -239 -233 -255

-260 -271 -258 -251 -245 -240 -260

-265 -276 -263 -257 -251 -246 -265

-270 -281 -269 -263 -257 -252 -270

-275 -286 -274 -268 -263 -258 -275

-280 -291 -280 -274 -269 -265 -280

-285 -296 -286 -280 -275 -271 -285

-290 -301 -291 -286 -281 -277 -290

-295 -306 -297 -292 -287 -283 -295

-300 -311 -302 -297 -293 -290 -300

-305 -316 -308 -303 -299 -296 -305

-310 -321 -313 -309 -305 -302 -310

-315 -326 -319 -315 -311 -318 -315

-317 -328 -321 -317 -314 -311 -317

SNC PLANT E. I. HATCH Pg 11 of 14 DOCUMENT TITLE: DOCUMENT NUMBER: Ver No:

RPV WATER LEVEL CORRECTIONS 34AB-B21-002-2 6.15 ATTACHMENT 4 Att. Pg.

TITLE: WIDE RANGE (YARWAY) UNCOMPENSATED AND COMPENSATED 1 of 1 SIGNAL DRYWELL TEMPERATURE CORRECTION