Text

Initial Exam 2010-301 Final RO Written Exam
	ML100830628
Person / Time
Site:	Sequoyah
Issue date:	03/23/2010
From:	; NRC/RGN-II
To:	;
References
	IR-10-301
	Download: ML100830628 (82)
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ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet u.s. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: Facility/Unit: Sequoyah Nuclear Station 1&2 Region: I D II X III D IV D Reactor Type: W X CE D BW D GE D Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after the examination begins.

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

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Feb/2010 Sequoyah RO NRC Exam 3/3/2010-31312010-

1. Given the following:

- Unit 2 is starting up and is at 2% power with the Steam Dump Control System operating as follows:

- Steam Dump Mode Selector Switch (HS-1-1 (HS-1-103D):

03D): STEAM PRESS

- Steam Dump Pressure Controller (PIC-1-33): AUTO

- A spurious Reactor Trip occurs, however Reactor Trip Breaker B fails to open.

Which ONE of the following identifies the steam generator (SG) pressure setpoint immediately after the reactor trip and the required actions to adjust SG pressure with PIC-1-33 in AUTO?

A. SG pressure corresponding to Tavg of 54rF (- 1005 psig)

Use the lever at the bottom of the PIC-1-33 controller.

B. SG pressure corresponding to Tavg of 552°F (- 1047 psig)

Use the lever at the bottom of the PIC-1-33 controller.

C. SG pressure corresponding to Tavg of 54rF (- 1005 psig)

Use the setpoint up/down pushbuttons on the PIC-1-33 controller.

D. SG pressure corresponding to Tavg of 552°F (- 1047 psig)

Use the setpoint up/down push pushbuttons buttons on the PIC-1-33 controller.

Page 1

Feb/2010 Sequoyah RO NRC Exam 31312010-3/312010

2. Given the following:

- Unit 1 was operating at 100% power when a small break LOCA occurred.

- RCP's are tripped in accordance with the EOP network.

- The following plant conditions exist:

- SI pumps fail to start.

- RCS Pressure is 1200 psig.

- RCS Hot Legs and the Reactor Vessel Head have voided.

- All SG narrow range levels are 10%.

Which ONE of the following identifies the current method(s) of cooling the core?

A. Only break flow is providing core cooling.

B. Break flow and reflux boiling are providing core cooling.

C. Natural circulation and reflux boiling are providing core cooling.

D. Only natural circulation is providing core cooling.

Page 2

Feb/2010 Sequoyah RO NRC Exam

.. 3/3/2010

3. A large break LOCA occurred on Unit 1 and the crew is currently implementing ES-1.3, "Transfer to Containment Sump."

The following conditions currently exist:

- 80th RHR Pumps are running aligned to the Containment Sump.

- The charging pump suction from the RWST has been manually isolated.

- The crew is ready to close 1-FCV-63-5, SI Pump Suction from RWST.

RHR Pump 1A-A subsequently trips.

Which ONE of the following identifies the CCPIT Inlet Flow rate on 1-FI-63-170 and the required actions for the following step in accordance with ES-1.3?

"14. Monitor 80th RHR Pumps Running" A. Greater than zero; Ensure 18-8 CCP and 18-8 SI Pumps are running and then place the 1A-A CCP and 1 A-A SI Pumps control switches to the pull-to-Iock (P-T-L) position.

1A-A

8. Greater than zero; Close 1-FCV-63-72, Train A Containment Sump Valve C. Zero; Ensure 18-8 CCP and 18-8 SI Pumps are running and then place the 1A-A CCP and 1A-A SI Pumps control switches to the pull-to-Iock (P-T (P-T-L)

-L) position D. Zero; 1-FCV-63-72, Train A Containment Sump Valve Close 1-FCV-63-72,-Train Page 3

Feb/2010 Sequoyah RO NRC Exam

- 3/312010 3/3/2010

4. Given the following:

- The plant is tripped from full power due to a loss of Component Cooling Water.

- The crew transitions to ES-0.1, "Reactor Trip Response," while continuing to perform the actions of AOP-M.03, "Loss of Component Cooling Water."

Fifteen minutes after the trip, the following conditions exist:

- SG pressures are all approximately 1005 psig and stable.

- RCS pressure 2235 psig and stable.

- Thot is approximately 570°F in all loops and slowly lowering.

- Core exit TC's indicate approximately 575 OF and stable.

- Tcold is approximately 547°F 54rF in all loops and stable.

Which ONE of the following describes the status of RCS heat removal for the current plant conditions?

A. Natural circulation is NOT established. RCS subcooling inadequate.

B. Natural circulation is NOT established. Core exit TC's not dropping.

C. Natural circulation is established. Heat removal via condenser steam dumps.

D. Natural circulation is established. Heat removal via SG atmospheric reliefs.

Page 4

Feb/2010 Sequoyah RO NRC Exam 3/3/2010

5. Given the following:

Unit 2 is at 100% power.

Letdown was removed from service to repair a leak.

Excess Letdown is in service.

- The 2A-A CCP trips.

Which ONE of the following ...

(1) describes how excess letdown flow will be affected and (2) a condition that requires a reactor trip in accordance with AOP-M.09, "Loss of Charging?"

A. (1) Excess letdown will be automatically isolated.

(2) RCP lower bearing temperature >225°F.

>225 of.

B. (1) Excess letdown will be automatically isolated.

(2) LS-68-3350/E PRESSURIZER LEVEL HIGH-LOW (M5A, C-3) alarms.

C. (1) Excess letdown will continue until manually isolated.

(2) RCP lower bearing temperature >225°F.

O. (1) Excess letdown will continue until manually isolated.

(2) LS-68-3350/E PRESSURIZER LEVEL HIGH-LOW (M5A, C-3) alarms.

Page 5

Feb/2010 Sequoyah RO NRC Exam

. 3/3/2010

6. Given the following:

- Unit 1 is in Mode 5 with the pressurizer solid. Train "A" RHR is operating in Shutdown Cooling.

- The following alarm is received:

"FCV-74-1/2 TROUBLE OR RHR PRESS HI (M6-C, E-7)"

- The operator attempted to adjust letdown and charging; however, the alarm condition did not clear and RCS pressure continued to slowly rise.

- The operator subsequently stopped the 1A-A1A-A RHR Pump and noted that RCS Pressure was still slowly rising.

Which ONE of the following identifies the RCS Pressure at which the operator is directed to manually close FCV-74-1 and 74-2 in accordance with AOP-R.03, "RHR System Malfunction," including the reason for this required action?

A. 380 psig; prevent inventory loss B. 380 psig; prevent over-pressurization of the PRT C. 450 psig; prevent inventory loss D. 450 psig; to prevent over-pressurization of the PRT.

Page 6

Feb/2D1 D Sequoyah RO NRC Exam 3/3f2D10 3/3/2D10

7. Given the following:

- The unit is operating at 85% power and both Pressurizer Spray Valve Controllers (1-PIC-68-34DO & & 1-PIC-68-34DB) are in MANUAL with their output set to "D."

Which ONE of the following predicts the plant response if the Pressurizer Master Pressure Controller (1-PIC-68-34DA) output signal fails to 1DD%?

A. PS-68-34DF/G PRESSURIZER PRESS ABOVE REF SET POINT (M5-A, B-3) will alarm; Actual pressure will remain the same.

B. PS-68-34DF/G PRESSURIZER PRESS ABOVE REF SET POINT (M5-A, B-3) will alarm; Actual pressure will lower.

C. PS-68-34DG/F PRESSURIZER PRESSURE LOW BACKUP HTRS ON (M5-A, 0-4) will alarm; Actual pressure will rise.

O. PS-68-34DG/F PRESSURIZER PRESSURE LOW BACKUP HTRS ON (M5-A, 0-4) will alarm; Actual pressure will remain the same.

Page 7

Feb/2010 Sequoyah RO NRC Exam

--313/2010

~313/201 0 "

8. Given the following:

a.Given Unit 1 is at 100% power with Reactor Trip Breaker "A" open due to SSPS testing on Train "A."

- A transient occurs that initiates a reactor trip signal, but the reactor fails to trip from the main control room.

Which ONE of the following identifies; (1) the required immediate operator actions listed in FR-S.1, "Nuclear Power Generation/ATWS" and (2) the minimum local actions that will result in a reactor trip?

A. (1) Maintain rod insertion at maximum rate and trip the turbine only.

(2) Open either RTB or BYA BYA B. (1) Maintain rod insertion at maximum rate and trip the turbine only.

(2) Open both RTB and BYA C. (1) Maintain rod insertion at maximum rate and trip the turbine and start AFW.

(2) Open either RTB or BYA BYA D. (1) Maintain rod insertion at maximum rate and trip the turbine and start AFW.

(2) Open both RTB and BYABYA Page 8

Feb/2010 Sequoyah RO NRC Exam 3/3/2010 3f3f201-0

9. Given the following:

Unit 2 was operating at 100% rated thermal power.

- The plant was tripped and SI was actuated due to a SGTR in #3 SG.

- The crew is currently implementing ES-3.1, "Post-SGTR Cooldown Using Backfill."

- The following boron concentrations have just been reported by Chemistry:

- RCS required boron for Cold Shutdown - 1750 ppm

- Current RCS boron concentration - 1800 ppm

- Ruptured SG boron concentration - 1200 ppm Which ONE of the following identifies an action that is required to be performed BEFORE a cooldown can be commenced and the reason why the cooldown should be promptly initiated at a rate near 1OO°F/hr in accordance with ES-3.1?

A. Borate the RCS > 35 gpm from the BAT; Inadvertent criticality could occur during a slower cooldown rate.

B. Inject Boric Acid into the Secondary side of #3 SG using AFW; Longer operation of the RCPs is permitted C. Borate the RCS > 35 gpm from the BAT; Longer operation of the RCPs is permitted.

D. Inject Boric Acid into the Secondary side of #3 SG using AFW; Inadvertent criticality could occur during a slower cooldown rate.

Page 9

Feb/2010 Sequoyah RO NRC Exam

-*31312010 313/20'10

10. Given the following:

- A steam line rupture has occurred on Unit 2 Which ONE of the following points indicates a Pressurized Thermal Shock condition FR-P.1,,

and identifies how this condition affects the reactor vessel in accordance with FR-P.1 "Pressurized Thermal Shock," and EPM-3-FR-P.1, "Basis Document for FR-P.1?

Referenced Provided A. To the LEFT of Limit A on Curve 2; an existing flaw could propagate.

B. To the RIGHT of Limit A on Curve 2; new flaw can develop.

C. To the LEFT of Limit A on Curve 2; new flaw can develop.

D. To the RIGHT of Limit A on Curve 2; an existing flaw could propagate.

Page 10

Feb/2010 Sequoyah RO NRC Exam 313/2010 3-/3/2010

11. Given the following:

Unit 1 at 8% power, startup in progress in accordance with 0-GO-4, "Power Ascension from Less than 5 Percent Reactor Power to 30%

Reactor Power."

- SG levels are being controlled by the MFW Bypass Reg valves in AUTO.

Main Feed Pump (MFP) 1A in service.

Motor Driven Auxiliary Feedwater Pumps have been stopped and placed in A-P AUTO.

- A failure of the #2 SG level control program results in the #2 SG level rising to the P-14 setpoint.

Assuming no operator actions, which ONE of the following identifies how the MFW Bypass Reg Valves and the bar graph indications on the associated Bypass Reg Valve Controllers will initially respond?

A. ALL Bypass Reg Valves closed; All controller bar graphs dropping.

B. ONLY #2 Bypass Reg Valve closed; All controller bar graphs dropping.

C. ONLY #2 Bypass Reg Valve closed; ONLY #2 controller bar graph dropping.

D. All Bypass Reg Valves closed; ONLY #2 controller bar graph dropping.

Page 11

Feb/2010 Sequoyah RO NRC Exam

. 3/312010 313/2010 -..- -

12. Which ONE of the following identifies the pump that will be sequenced on first following a blackout Signal signal on a 6900v Shutdown board and a reason?

First Pump Reason A. CCP Largest blackout load on the board.

B. CCP Reactor Cooling Pump seal cooling restoration.

C. ERCW pump Largest blackout load on the board.

D. ERCW pump Diesel Generator cooling restoration.

Page 12

Feb/2010 Sequoyah RO NRC Exam

. 3/312fJ10 3/312(J10

13. Given the following:

Unit 1 is at 100% RTP.

Pressurizer Level Control Level Selector Switch is in the 339/320 position.

- A loss of the 120V Vital instrument Power Board 1-11 occurs.

Which ONE of the following identifies the required actions for controlling charging flow using 1-HIC-62-93A, Charging Flow Control, in MANUAL?

A. Control pressurizer level at or trending to 60% and maintain RCP seal injection between 6 gpm and 11 gpm per pump.

B. Control pressurizer level at or trending to 25% and maintain RCP seal injection between 6 gpm and 11 gpm per pump.

C. Control pressurizer level at or trending to 60% and maintain RCP seal injection between 3 gpm and 4 gpm per pump.

D. Control pressurizer level at or trending to 25% and maintain RCP seal injection between 3 gpm and 4 gpm per pump.

Page 13

Feb/2010 Sequoyah RO NRC Exam

- 3/3/2010

3/312010

14. Given the following:

- Unit 1 is operating at 100% rated thermal power.

- A total loss of ERCW occurs, and the reactor is manually tripped.

Which ONE of the following identifies the required procedures?"

A. E-O, "Reactor Trip or Safety Injection," will be implemented.

Cooldown will be implemented in accordance with 0-GO-7, "Unit Shutdown From Hot Standby To Cold Shutdown."

B. E-O, "Reactor Trip or Safety Injection," will NOT be implemented.

Cooldown will be implemented in accordance with 0-GO-7, "Unit Shutdown From Hot Standby To Cold Shutdown."

C. E-O, "Reactor Trip or Safety Injection," will be implemented.

Cooldown will be implemented in accordance with AOP-M.01, "Loss of ERCW."

D. E-O, "Reactor Trip or Safety Injection," will NOT be implemented.

Cooldown will be implemented in accordance with AOP-M.01, "Loss of ERCW."

Page 14

Feb/2010 Sequoyah RO NRC Exam 31312{) 1()

31312010

15. Given the following:

Both units are operating at 100% power.

- A loss of control air is occurring.

- All available Station Control & Service Air Compressors and both Auxiliary Air Compressors have started and loaded.

Which ONE of the following identifies the pressure that 0-FCV-32-82 "Train A Control Air Supply" and 0-FCV-32-85 "Train B Control Air Supply" will close as the pressure in the Station Control & Service Air System drops and why?

A. At 69 psig to ensure control air is provided to the essential components for safe shutdown.

B. At 69 psig to prevent exceeding containment design pressure in the event of a design bases accident when the air leak is inside containment.

C. At 50 psig to ensure control air is provided to the essential components for safe shutdown.

D. At 50 psig to prevent exceeding containment design pressure in the event of a design bases accident when the air leak is inside containment.

Page 15

Feb/2010 Sequoyah RO NRC Exam

~ 3/3/2010-3/3/2010 ..- .

16. Given the following:

Unit 1 is operating at 100% rated thermal power.

- liGEN EXCITER FIELD OVERCURRENT" (M-1A, A-6) alarms.

- The following indications are observed:

- Main Generator Voltage 24.6 kV

- Main Generator MVARS 310 MVARS (outgoing)

- Main Generator Exciter Amps 220 amps Which ONE of the following identifies the parameter that is out of limits and the required operator action in accordance with the alarm response procedure?

A. Main Generator MVARS Place the Exciter Voltage Auto Adjuster Switch to the LOWER Position B. Main Generator MVARS Trip the Reactor C. Main Generator Exciter Amps Place the Exciter Voltage Auto Adjuster Switch to the LOWER Position D. Main Generator Exciter Amps Trip the Reactor Page 16

Feb/2010 Sequoyah RO NRC Exam 313/2010 3/3/2010

17. Given the following plant conditions:

Following a reactor trip, abnormal radiation was noted in the Aux. Building due to a loss of RCS inventory outside containment.

Which ONE of the following identifies a required action and the subsequent check used to determine whether or not the leak is isolated in accordance with ECA-1.2, "LOCA Outside Containment?"

A. Isolate SI pump Cold Leg Injection; Pressurizer level rising B. Isolate SI pump Cold Leg Injection; RCS pressure rising C. Isolate RHR Cold Leg Injection; Pressurizer level rising D. Isolate RHR Cold Leg Injection; RCS pressure rising Page 17

Feb/2010 Sequoyah RO NRC Exam 3/3/2010

18. Given the following:

- The crew is implementing FR-H.1, "Loss of Secondary Heat Sink."

- CST level is 25%.

No Steam Generator is Intact.

Which ONE of the following identifies the preference for restoring a SG as a heat sink and the order in which the feed water sources are attempted in accordance with FR-H.1, "Loss of Secondary Heat Sink?"

A. Feed a ruptured SG before feeding a faulted SG; TDAFW, MFW, Condensate, MDAFW using ERCW B. Feed a ruptured SG before feeding a faulted SG; MDAFW, TDAFW, MFW, Condensate C. Feed a faulted SG before feeding a ruptured SG; TDAFW, MFW, Condensate, MDAFW using ERCW D. Feed a faulted SG before feeding a ruptured SG; MDAFW, TDAFW, MFW, Condensate Page 18

Feb/2010 Sequoyah RO NRC Exam 31312010 19.

Given the following plant conditions:

- Unit 1 is at 100% RTP.

- Pressurizer Level Control Selector Switch, 1-XS-339E, is selected to the LT-68-339/320 LT 339/320 position.

Which ONE of the following subsequent instrument failures will result in a reactor trip in the shortest time assuming all systems respond as designed and there is NO operator action?

(Consider each failure to occur independently)

A. 1-L 1-LT-68-339 T-68-339 fails LOW.

B. 1-LT-68-339 fails HIGH.

C. 1-LT 320 fails LOW.

D. 1-LT-68-320 fails HIGH.

Page 19

Feb/2010 Sequoyah RO NRC Exam

- _.- - ~ 31312010 3f31201() - - ---

20. Given the following plant conditions:

- Unit 2 is in MODE 6.

- "SOURCE/INTERMED RANGE CH-II TROUBLE," (M-4B, A-2) suddenly alarms.

- The OATC notices at the same time that a loss of the audio count rate signal has occurred.

- No other alarms associated with this failure have actuated.

Which ONE of the following describes the action necessary to restore the audio count rate signal to the control room in accordance with AOP-1.01, "Nuclear Instrument Malfunction?"

A. Place the audio count rate CHANNEL SELECTOR switch on the front of the Audio Count Rate Drawer to the SR N-31 position.

B. Place the audio count rate CHANNEL SELECTOR switch on the front of the Audio Count Rate Drawer to the SR N-32 position.

C. Place the AMPLIFIER SELECT switch on the rear of the audio count rate drawer assembly to the A A11 position.

D. Place the AMPLIFIER SELECT switch on the rear of the audio count rate drawer assembly to the A2 position.

Page 20

Feb/2010 Sequoyah RO NRC Exam

- - - 3/3/2010 3/3/2010- - .

21. Given the following:

- Unit 1 is in Mode 1 doing a power ascension following a refueling outage.

- During the power ascension the 1-M-4 Control Board indicators for N-35 and N-36 (1-X1-92-5003A & & 1-X1-92-5004A) have trended as follows:

2000 (6/18) 0800 (6/19) 2000 (6/19)

Which ONE of the following indicates the status of control board readings for N-35 and N-36?

REFERENCE PROVIDED A. maximum allowable channel deviation exceeded at 2000 (6/18)

B. maximum allowable channel deviation exceeded at 0800 (6/19)

C. maximum allowable channel deviation exceeded at 2000 (6/19)

D. maximum allowable channel deviation not exceeded.

Page 21

Feb/2010 Sequoyah RO NRC Exam

-3/3120tO 3/312010 - -

22. Given the following:

- Unit 1 is in Mode 6 with Refueling in progress.

- The refueling SRO in containment reports a large reactor cavity seal leak.

- The crew is implementing AOP-M.04, "Refueling Malfunctions."

- Per Section 2.1, "Reactor Cavity Seal Failure," two operators are dispatched to close the Transfer Tube Wafer Valve.

Which ONE of the following identifies:

(1) the location of the handwheel for 78-610 (Wafer Valve) and (2) the reason for performing this action?

A. Reverse Osmosis Room; to maintain SFP inventory.

B. Reverse Osmosis Room; to maintain Refueling Cavity inventory.

C. PASF Room; to maintain SFP inventory.

D. PASF Room; to maintain Refueling Cavity inventory.

Page 22

Feb/2010 Sequoyah RO NRC Exam 3/3/201-0 3/3/2010

23. Given the following:

- Unit 1 is operating at 100% rated thermal power.

- A 5 gpd SG tube leak has been confirmed on #1 SG.

Which ONE of the following identifies the preferred method and initial frequency for SG leak rate monitoring in accordance with AOP-R.01, "Steam Generator Tube Leak?"

A. SG samples; every 15 minutes B. SG samples; every 30 minutes C. Condenser vacuum exhaust radiation monitor; every 15 minutes D. Condenser vacuum exhaust radiation monitor; every 30 minutes Page 23

Feb/2010 Sequoyah RO NRC Exam 31312010

24. Given the following:

Unit 1 and Unit 2 are at 100% rated thermal power.

- A fire in the Control Building requires evacuating the Main 'Control Room (MCR) in accordance with AOP-C.04, "Shutdown from the Auxiliary Control (MeR)

Room."

Which ONE of the following identifies an action that is taken prior to evacuating the MCR in accordance with AOP-C.04 and the reason for this action?

A. Place one CCP in pull-to-Iock; Minimize PORV cycling.

B. Place one CCP in pull-to-Iock; Prevent common mode failure of both CCPs due to spurious closure of VCT outlet valves (FCV-62-132 & 133)

C. Isolate normal CVCS letdown flow path; Minimize inventory loss from RCS.

D. Isolate normal CVCS letdown flow path; Minimize the possibility of a loss of RCP seal cooling.

Page 24

Feb/2010 Sequoyah RO NRC Exam 31312010 3/312010

25. Given the following:

- At 1600, Unit 1 tripped from 100% power due to a Small Break LOCA.

- At 1625, the crew initiated an RCS cooldown using ES-1.2, "Post LOCA Cooldown and Depressurization."

- At 2200 the crew is evaluating the step to determine if RHR can be placed in service. The following plant conditions exist:

Both RHR pumps are stopped.

Normal charging has been established.

PZR level is 28% and stable.

RCP #2 is the only RCP running.

RCS pressure - 330 psig and slowly trending down.

RCS temperature - 340°F and slowly trending down.

Which ONE of the following identifies ...

(1) the initial starting time used to calculate if the cooldown rate is acceptable, and (2) if RHR can be placed in service with the current conditions in accordance ES-1 .2?

with ES-1.2?

A. (1) 1600 (2) Conditions do not allow RHR shutdown cooling to be established.

B. (1) 1600 (2) with TSC concurrence, RHR shutdown cooling is allowed.

C. (1) 1625 (2) Conditions do not allow RHR shutdown cooling to be established.

D. (1) 1625 (2) with TSC concurrence, RHR shutdown cooling is allowed.

Page 25

Feb/2010 Sequoyah RO NRC Exam 3/312010

26. Given the following:

- While operating at 100% power, Unit 1 has experienced a large steam break.

- The crew is responding to a Red Path on PTS using FR-P.1, "Pressurized Thermal Shock."

- Current plant conditions are:

- RCS Tcold is 250°F and slowly rising

- PZR pressure is 2000 psi

- PZR level is 90% and rising

- Total AFW flow to the intact SGs is 300 gpm

- CCPs are injecting via the CCPIT Which ONE of the following identifies a required action that will reduce the potential for damage to the reactor vessel in accordance with FR-P.1?

A. Raise AFW flow to greater than 440 gpm.

B. Reduce AFW flow to no greater than 50 gpm per SG.

C. Reset SI and stop both CCPs.

D. Reset SI, stop one CCP, and isolate the CCPIT.

Page 26

Feb/2010 Sequoyah RO NRC Exam 3/312010 3/3/2010* - _.

27. Given the following:

- A reactor trip from 100% power and loss of Offsite power occurred 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago.

ES-0.3, "Natural Circulation Cooldown with Steam Void in Vessel (with RVLlS)," is in progress.

PZR pressure is 785 psig and being lowered by auxiliary spray.

Core exit TCs indicate 520°F.

RVLlS upper plenum range reads 81 %.

81%.

Assuming NO additional operator action, which ONE of the following predicts the expected RVLlS and PZR level trends as the depressurization continues?

RVLlS PZR Level A. Decrease Increase B. Increase Decrease c.

C. Decrease Decrease D. Increase Increase Page 27

Feb/2010 Sequoyah RO NRC Exam 3/3/2010

28. Which one of the following completes both statements in accordance with Tech Spec 3.4.1, Reactor Coolant Loops and Coolant Recirculation?

The plant is designed to operate with all reactor coolant loops in operation which maintains above the safety analysis limits during all normal operations and anticipated transients.

With one reactor coolant loop not in operation, the plant is required to be _ _ __

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

A. QPTR; less than or equal to 5% power B. QPTR; in Hot Standby C. DNBR; less than or equal to 5% power D. DNBR; in Hot Standby Page 28

Feb/2010 Sequoyah RO NRC Exam 3/312010 31312010

29. Given the following:

Unit 2 is at 100% rated thermal power.

Rod control is in Manual.

- The OATC notices a slow decrease in RCS pressure and Tavg has decreased 1.5°F over the last several minutes.

PZR variable heaters are energized and spray valves are closed.

Which ONE of the following will result in these conditions?

A. CVCS letdown heat exchanger temperature control valve failed open.

2-FCV-62-138, Emergency Boration Flow Control valve is leaking by.

B. 2-FCV-62-138.

C. Primary water makeup flow was set at 70 gpm during the last manual makeup to the VCT.

D. A CVCS mixed bed demineralizer with new resin was put in service before being borated.

Page 29

Feb/2010 Sequoyah RO NRC Exam

. 3/3/2010 313/2010

30. Given the following:

Unit 1 is operating at 100% power.

- "LS-62-129A/B VOLUME CONTROL TANK LEVEL HI-LOW," (1-M-6C, A-3) has just gone into Alarm.

LI-62-129, VCT Level, indicates 35% decreasing.

LI-62-130, VCT Level, indicates 100% on ICS.

Which ONE of the following predicts the plant response assuming no operator action?

A. Suction to the operating CCP will align to the RWST when VCT level decreases to 7%.

B. Pressurizer level will decrease to 17% resulting in letdown system isolation and recovery of VCT level.

C. VCT level will continue to decrease until the charging pumps lose suction.

D. Auto makeup will initiate to the VCT when LT-62-129 decreases to 20% and will raise VCT level back to 41 %.

Page 30

Feb/2010 Sequoyah RO NRC Exam 313/2010 3/312010

31. Given the following:

Unit 1 is in Mode 5 with the RCS in solid water operation.

RHR pump 1A-A in service.

1-PCV-62-81, Letdown Pressure Control Valve, is in automatic.

Which ONE of the following completes the statement below if the 1A-A RHR Pump trips?

The RCS pressure will initially (1) because 1-PCV-62-81 will automatically throttle (2) when RHR pump trips.

ill ill

(£)

A. drop open B. drop closed C. rise open D. rise closed Page 31

Feb/2010 Sequoyah RO NRC Exam 3/3/2010 - -

32. Given the following:

Unit 2 was operating at 100% power when a LOCA occurred.

Hottest core exit thermocouples are stable at 400°F.

RCS pressure is 225 psig.

RVLlS Upper Plenum is 64%.

RVLlS Lower Range is 70%.

Containment pressure is 6 psig.

- All SG pressures are 500 psig.

Which ONE of the following conclusions can be determined from these indications?

A. Decay heat is being removed by Steam Generators.

B. RVLlS Upper range indication has failed.

C. Core cooling is inadequate. Additional ECCS flow is required.

D. Vessel level is adequate. ECCS flow should continue to ensure core cooling is maintained.

Page 32

Feb/2010 Sequoyah RO NRC Exam

3/312010 31312010

33. Given the following plant conditions:

- A reactor trip has occurred.

RCS pressure is 1810 psig and lowering.

- Containment Pressure is 1.55 psig and rising.

Which ONE of the following identifies the status of the RCP's #1 sealleakoff flowpath?

A. routed to the PRT B. routed directly to the VCT C. routed to the RCDT D. routed to the CCP suction Page 33

Feb/2010 Sequoyah RO NRC Exam 31312010

34. Given the following:

Unit 1 at 100% power.

- Component Cooling Water system is in the normal alignment.

Unit 2 in Mode 5.

Which ONE of the following describes the affect of closing 2-FCV-70-75, '2B ESF Header Return Isolation,' without closing 2-FCV-70-3, '2B ESF Header Supply Isol' in accordance with 0-SO-70-1, 'Component Cooling Water System "B" Train?'

A. Less than minimum required flow on the C-S CCS pump.

B. Inadequate suction supply path to 2B-B CCS pump.

C. Abnormal level changes in both CCS Surge Tanks.

D. Loss of flow on Unit 2 Reactor Building supply Header.

Page 34

Feb/2010 Sequoyah RO NRC Exam 31312010

35. Given the following:

Unit 1 is being cooled down and has been placed on shutdown cooling with 'A' Train RHR in service.

- "RHR HX A OUTLET TEMPERATURE HIGH" (M27-B-A, E-6) alarms.

- Temperature on 1-TI-70-157, "RHR Heat Exchanger 1A Outlet Temperature" reads 120°F and steady.

Which ONE of the following choices completes both statements below in accordance with the Annunciator Response Procedure?

It is to exceed the alarm setpoint when RHR is in service for shutdown cooling.

In order to reduce the RHR heat exchanger CCS outlet temperature _ _ __

A. allowed; either the CCS flow or the RHR flow through the heat exchanger is allowed to be adjusted.

B. allowed; only the CCS flow through the heat exchanger is allowed to be adjusted.

C. NOT allowed; either the CCS flow or the RHR flow through the heat exchanger is allowed to be adjusted.

D. NOT allowed; only the CCS flow through the heat exchanger is allowed to be adjusted.

Page 35

Feb/2010 Sequoyah RO NRC Exam

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36. Unit 1 was in Mode 3, Tave 54rF, PZR pressure 2235 psig.

A malfunction occurred which caused PZR pressure to drop to 2050 psig and PZR level to drop to 15%.

Currently PZR pressure is 2100 psig and PZR level is 30%.

Assuming no operator action, which ONE of the following predicts the current status of the PZR heaters?

A. All Backup and Control group heaters will be OFF.

B. All Backup and Control group heaters will be ON.

C. All Backup heaters will be ON and Control group D0 heaters will be OFF.

D. All Backup heaters will be OFF and Control group D0 heaters will be ON.

Page 36

Feb/2010 Sequoyah RO NRC Exam

.. - . 3131201 O~

31312010

37. Given the following:

Unit 1 is operating at 100% rated thermal power.

Rod control has been placed in MANUAL with Tavg at 578.0°F.

Which ONE of the following identifies how the actual RPS trip setpoint value will change if Tavg decreases by 1°F? Assume AFD remains constant.

A. Both OTDT and OPDT trip setpoint values will decrease.

B. OTDT trip setpoint value will increase and OPDT trip setpoint value will decrease.

C. OTDT trip setpoint value will increase and OPDT trip setpoint value will remain the same.

D. OTDT trip setpoint value will remain the same and OPDT trip setpoint value will decrease.

Page 37

Feb/2010 Sequoyah RO NRC Exam 31312010

38. Which ONE of the following identifies the plant board that provides power to a reactor trip breaker UV Trip coil?

A. 48V-DC Plant Battery Board B. 125V-Vital DC Battery Board C. 120V-AC Preferred Power Board D. 120V-AC Vital Instrument Power Board Page 38

Feb/2010 Sequoyah RO NRC Exam

~- 31312010-313/2010 > -

39. Given the following plant conditions:

- The operating crew is responding to a loss of 120V AC Vital Instrument Power 80ard 1-1.

Soard

- PZR pressure transmitter 1-PT-68-334 (Channel II) fails LOW.

Which ONE of the following predicts how SSPS and EGCS will respond?

80th trains of SSPS SI master relays will actuate AND both trains of ECCS A. Soth equipment auto start.

B. Soth S. 80th trains of SSPS SI master relays will actuate SUT BUT only "S" "8" train ECCS equipment auto starts.

"8" train SSPS SI master relays will actuate SUT G. Only the "S" BUT both trains of ECGS equipment auto start.

D. Only the "S" "8" train SSPS SI master relays will actuate AND only "S" "8" train ECCS EGGS equipment auto starts.

Page 39

Feb/2010 Sequoyah RO NRC Exam 3/3/2010

40. The following conditions exist on Unit 1:

- Reactor power is 100%.

- RWST level transmitter 1-LT 50 fails causing 1-Ll-63-50 to read off-scale High.

- All other RWST level indicators (1-Ll-63-51, -52, -53) are at 99%.

Which ONE of the following describes the impact of this failure and the required actions in accordance with AOP-1,09, "RWST Level Instrument Malfunction?"

Swapover Logic Status Required Action A. Train A swapover is disabled, Place the failed channel in tripped condition Train B swapover is operable.

B. Train A swapover is disabled, Place the failed channel in bypassed condition Train B swapover is operable.

C. Both trains of swapover are Place the failed channel in tripped condition operable.

D. Both trains of swapover are Place the failed channel in bypassed condition operable.

Page 40

Feb/2010 Sequoyah RO NRC Exam 31312010

41. Given the following:

- Both Units in service at 100% RTP.

- Upper Compartment Cooling Units A and B are in service on both units.

Compare the effects of the inadvertent closing of the Lower Compartment Cooling Unit (LCCU) valves listed:

Unit 1, LCCU 1A-A ERCW Inlet FCV (Outboard), 1-FCV-67-107 Unit 2, LCCU 2A-A ERCW Inlet FCV (Outboard), 2-FCV-67-107 If both of the valves were closed, which ONE of the following identifies the effect on the Upper Containment temperature on the respective unit(s) and the required actions, if any?

A. Upper containment temperature will remain the same on Unit 1 and 2.

No additional coolers are available on either Unit.

B. Upper containment temperature will RISE on Unit 1 and 2.

Place additional coolers in service on both Units.

C. Upper containment temperature will RISE on Unit 1 only.

No additional coolers are available on Unit 1.

D. Upper containment temperature will RISE on Unit 1 only.

Place additional coolers in service on Unit 1.

Page 41

Feb/2010 Sequoyah RO NRC Exam 3/3/2010 313/2010 -

42. Which ONE of the following describes a design feature of the Ice Condenser Glycol system that prevents over-pressurization of the piping when the glycol trapped between the containment isolation valves expands?

A. The penetration's INSIDE containment isolation valve disks are modified with a drilled hole.

B. The penetration's OUTSIDE containment isolation valve disks are modified with a drilled hole.

c. The penetration's INSIDE containment isolation valve has a bypass line and C.

check valve arrangement.

D. The penetration's OUTSIDE containment isolation valve has a bypass line and check valve arrangement.

Page 42

Feb/2010 Sequoyah RO NRC Exam 3/3/2010

43. Given the following conditions:

Unit 1 is operating at 100% power.

1A-A 1A-A Containment Spray (CS) Pump is out of service.

- A large break LOCA occurs.

60 minutes later, the following conditions exist:

- Containment pressure is 8.4 psig.

- FR-Z.1, "High Containment Pressure" is in progress.

- ES-1.3, "Transfer To RHR Containment Sump" has been completed.

- The crew observes 1B-B CS Pump running with a discharge flow of approximately 4000 gpm.

Which ONE of the following describes the condition of the Containment Spray System and the FR-Z.1 direction concerning RHR spray?

A. Containment spray flow is normal and RHR spray will be placed in service only if containment pressure rises to greater than 9.5 psig.

B. Containment spray flow is normal and RHR spray will be immediately placed in service.

C. Containment spray flow is LOWER than normal and RHR spray will be placed in service only if containment pressure rises to greater than 9.5 psig.

D. Containment spray flow is LOWER than normal and RHR spray will be immediately placed in service.

Page 43

Feb/2010 Sequoyah RO NRC Exam

- 313/2010 -

44. Given the following:

Unit 1 operating at 60% power.

- A Steam Generator safety valve begins to leak through.

Which ONE of the following identifies both ....

(1) the time in core life that will result in the largest addition of positive reactivity and (2) a condition which requires a manual reactor trip in accordance with AOP-S.05, "Steam or Feedwater leak?"

Time in Core Life Condition requiring reactor trip A. EOl Final Reactor power of 65%.

B. EOl TavglTref can not be maintained within 3°F.

C. BOl Final Reactor power of 65%.

D. BOl TavglTref Tavg/Tref can not be maintained within 3°F.

Page 44

Feb/2010 Sequoyah RO NRC Exam

- 3/312010 c 3/3/2010 -

45. Given the following:

Unit 1 is starting up from a refueling outage and is currently at 70% rated thermal power.

- "8" MFW pump tripped.

Prompt operator actions were taken to lower turbine load and stabilize the plant in accordance with AOP-S.01, "Loss of Normal Feedwater."

Assuming no additional operator actions, which ONE of the following identifies the current status of the AFW system?

A. Only "8" MDAFW pump running.

8. Only "A" and "8" MDAFW pumps running.

c.

C. "A" and "8" MDAFW pumps, and TDAFW pump running.

D. None of the AFW pumps running.

Page 45

Feb/2010 Sequoyah RO NRC Exam

--- . 3131201"0 313/2010 - --- -

46. Given the following:

- Unit 1 was initially at 100% RTP and a reactor trip occurred.

- The following steam generator levels and containment pressures are observed:

Time: 0200 0201 0202 0203 0205 SG Level:

1 S/G (% NR) 8 12 22 26 35

2 S/G (% NR) 7 12 24 27 36

3 S/G (% NR) 5 13 25 29 33

4 S/G (% NR) 5 16 28 31 35 Cntmt Qress gress {gsig}:

(Qsig): 1.5 3.5 2.5 1.5 0.6 Which ONE of the following identifies the EARLIEST time that AFW can be reset and throttled to less than 440 gpm in accordance with E-O, "Reactor Trip or Safety Injection?"

A. 0201 B. 0202 C. 0203 D. 0205 Page 46

Feb/2010 Sequoyah RO NRC Exam

. ~ - 3/3/2010 3/3/201 0 --

47. Given the following plant conditions:

- Unit 1 & 2 are operating steady-state at 100%.

Which ONE of the following identifies the degraded voltage set point that will automatically trip open the 1B-B 6.9 kV Shutdown Board Normal Feeder Breaker?

A. Voltage at 93.5% of nominal voltage for 30 seconds.

B. Voltage at 80% of nominal voltage for 30 seconds.

C. Voltage at 93.5% of nominal voltage for 5 minutes.

D. Voltage at 80% of nominal voltage for 5 minutes.

Page 47

Feb/2010 Sequoyah RO NRC Exam

-. . . 31312010 31312010 ... .. -

48. Given the following:

Unit 1 was operating at 100% rated thermal power when the following alarm was received:

- "125V DC VITAL BAT BD 1 ABNORMAL" (M1-C, A-5).

- No other abnormal alarms are lit.

Which ONE of the following identifies the reason for this alarm and an expected indication OR required operator action in accordance with alarm response procedure?

A. Charger has tripped; EI-57-92 "125V VITAL BATT BD BO AMPS" indicates steady current flow below zero.

B. Charger has tripped; EI-57-92 "125V VITAL BATT BD BO AMPS" indicates steady current flow above zero.

C. A ground exists; Locally adjust red flag set point to clear the control room alarm.

O. A ground exists; Sequentially open breakers (one at a time) on the battery board to D.

locate the ground.

Page 48

Feb/2010 Sequoyah RO NRC Exam 31312010*

3/312010

49. Given the following:

- The A-A Diesel Generator is being synchronized to its shutdown board for a surveillance test.

- When 1-HS-S7-47, "DG 1A Synchronize" is placed to the "SYN" position, the synchroscope pointer begins to rotate quickly in the counter-clockwise direction.

Which ONE of the following identifies ...

(1) the position of 0-HS-82-18, DG 1A-A MODE SELECTOR, at this time, and (2) the action required prior to closing the Diesel Generator output breaker?

A. (1) PARALLEL 0-HS-82-13, Speed Control, to the RAISE position.

(2) Place O-HS-82-13, B. (1) PARALLEL (2) Place 0-HS-82-13, Speed Control, to the LOWER position.

C. (1) PULL FOR LOCAL TRANSFER (2) Place 0-HS-82-13, Speed Control, to the RAISE position.

D. (1) PULL FOR LOCAL TRANSFER (2) Place 0-HS-82-13, Speed Control, to the LOWER position.

Page 49

Feb/2010 Sequoyah RO NRC Exam 3/3/2010 313/2010

50. Which ONE of the following choices completes the following statements?

Each DG air start system accumulator set has sufficient capacity to start the engine (1) times without recharging.

Anytime either of the B air receivers is less than (2) psig the DIG is inoperable.

ill A. 5 210 B. 5 150 c.

C. 10 210 D. 10 150 Page 50

Feb/2010 Sequoyah RO NRC Exam

- - 3/312010 313/2010 -

51. Given the following:

- U-1 operating at 100% power.

0900 -"1-RA-90-119A CNDS VAC PMP LO RNG AIR EXH MON HIGH RAD" (M12A, C-1) alarms.

0905 - The following radiation monitor trends are noted:

Condenser Vacuum Exhaust Rad Monitor, 1-RM-90-119 trending up.

SGBD Rad Monitor, 1-RM-90-120 stable.

0910 - Reactor Trip and Safety Injection are manually initiated due to rapidly lowering Pressurizer level.

Which ONE of the following identifies ...

(1) why 1-RM-90-120 trend is stable at 0905 and (2) where the SGBD sample lines tap off the SGBD system?

A. (1) SGBD isolates on High Radiation.

(2) Upstream of the inside SGBD CNMT isolation valves.

B. (1) SGBD isolates on High Radiation.

(2) Downstream of the inside SGBD CNMT isolation valves.

C. (1) SGBD piping transport time.

(2) Upstream of the inside SGBD CNMT isolation valves.

D. (1) SGBD piping transport time.

(2) Downstream of the inside SGBD CNMT isolation valves.

Page 51

Feb/2010 Sequoyah RO NRC Exam

- 313/2010

52. Given the following:

Boths units are at 100% rated thermal power with all components in normal alignment.

- A Safety injection occurs on Unit 1.

Which ONE of the following predicts the automatic response of the following ERCW System valves?

Note:

FCV-67-151, CCS Heat Exchanger 'OB1' Disch to Header A FCV-67-152, CCS Heat Exchanger 'OB2' Disch to Header B A. 0-FCV-67-151, automatically travels to 100% open.

0-FCV-67 -152, automatically throttles to 35% open.

0-FCV-67-152, B. 0-FCV-67-151, remains as is.

0-FCV-67-152, automatically travels to 100% open.

O-FCV-67-152, C. 0-FCV-67 -151, remains as is.

0-FCV-67-151, 0-FCV-67-152, automatically throttles to 35% open.

D. 0-FCV-67-151, automatically travels to 100% open.

0-FCV-67-152, automatically travels to 100% open.

Page 52

Feb/2010 Sequoyah RO NRC Exam 313120'f0 31312010 . -

53. The breaker for Auxiliary Air Compressor B is located on which ONE of the following electrical boards?

A. 480v Reactor Vent Board 1B-B B. 480v Reactor Vent Board 2B-B C. 480v C & A Vent Board 1B1-B 1B1-B D. 480v C & A Vent Board 2B1-B Page 53

Feb/2010 Sequoyah RO NRC Exam

... - - ' - 3/312010-3/312010

54. An irradiated fuel assembly has been dropped in containment during a refueling outage on Unit 11..

Which ONE of the following identifies required areas to be evacuated and required actions to be taken in accordance with AOP-M.04, "Refueling Malfunctions?"

A. Only personnel inside containment must be evacuated; At least ONE door must be closed in both Upper and Lower containment air locks.

B. All personnel inside containment AND the Aux Building must be evacuated; BOTH doors must be closed in both Upper and Lower containment air locks.

C. Only personnel inside containment must be evacuated; BOTH doors must be closed in both Upper and Lower containment air locks.

D. All personnel inside containment AND the Aux Building must be evacuated; At least ONE door must be closed in both Upper and Lower containment air locks.

Page 54

Feb/2010 Sequoyah RO NRC Exam

- 3/312010 31312010 - -

55. Which ONE of the following identifies the effect of a Phase B Containment Isolation signal on the Lower Compartment Cooling Fans and the Containment Air Return Fans?

Lower Compartment Containment Air Cooling Fans Return Fans A. Trip Start after 10 minute time delay B. Trip Start immediately C. Start Start after 10 minute time delay D. Start Start immediately Page 55

Feb/2010 Sequoyah RO NRC Exam 3/312010 3/3/2010

56. Given the following:

Unit 1 at 100% power.

- 480v Common Emergency Transformer out of service.

Which ONE of the following describes the effect on the Control Rod Drive MG Sets if 6900v Unit Board 1D is de-energized?

A. Both MG sets lose power to the motor.

B. Neither MG set loses power to the motor.

C. Only 1 1A A MG set loses power to the motor.

D. Only 1B MG set loses power to the motor.

Page 56

Feb/2010 Sequoyah RO NRC Exam Febf2010

. 3131201 a 3/312010 ~ .

57. Given the following:

- Unit 1 is at 100% rated thermal power.

- Control bank D 0 group 2 rod H-8 has dropped into the core.

- The operating crew is performing steps in AOP-C.01, "Rod Control System Malfunctions."

When ready to withdraw the rod, which ONE of the following identifies ...

is/are required to be adjusted to ZERO (1) the group step counter(s) that isfare and (2) the position 1-HS-85-511 0, Rod Control Mode Selector Switch, is required to be placed in?

A. (1) Group 2 ONLY (2) MAN B. (1) BOTH Group 1 and 2 (2) MAN C. (1) Group 2 ONLY (2) CBD D. (1) BOTH Group 1 and 2 (2) CBD Page 57

Feb/2010 Sequoyah RO NRC Exam

~c - 3131201U-3/3/2010

58. Which ONE of the following identifies how the Control Room Audio Count Rate sound is initiated following a reactor trip?

A. AUTOMATICALLY initiated only after both N-35 & N-36 are less than 10-4 % power.

B. AUTOMATICALLY initiated only after 3 out of 4 of the Power range detectors are less than 10%.

C. MANUALLY initiated only after the Level Trip Bypass Switches are placed in the Normal position.

D. MANUALLY initiated only after SRM Trip Reset Block Switches are placed to the RESET position.

Page 58

Feb/2010 Sequoyah RO NRC Exam

- . 31312010 j1312010- .. - .-

59. Which ONE of the following identifies the primary function of the Isolation Amplifier associated with the Pressurizer Pressure Transmitters?

A. Amplifies the pressure output signal between containment and the instrument rack.

B. Amplifies the pressure output signal between the instrument rack and the main control room.

C. Protects the Pressurizer Pressure Control circuit.

D. Protects the Pressurizer Pressure Protection circuit.

Page 59

Feb/2010 Sequoyah RO NRC Exam

. 31312010 31312010 .~ - --

60. Given the following:

Unit 1 is operating at 100% power

- The following alarm is received:

- "INCORE TEMP MONITORING SYSTEM TROUBLE" (M4-B, A-3)

Which ONE of the following identifies ...

(1) the indication on the Exosensor Plasma Display if an incore thermocouple was outside its electrical limit due to an electrical short in the circuit and (2) the minimum number of thermocouples, per core quadrant, required to be operable in accordance with Tech Specs without relying on an Action Statement?

Plasma Display Indication Tech Spec Requirement A. "?"

"? One in each train.

B. "XXX*

"XXX" I One in each train.

C. "?"

"? Two in each train.

D. "XXXII Two in each train.

Page 60

Feb/2010 8equoyah Sequoyah RO NRC Exam

- 31312010 - .

61. Given the following plant conditions:

- Unit 1 is operating at 100% power.

- A lower containment purge is in progress in accordance with 1-80-30-3, 1-S0-30-3, "Lower Containment Purge Operation."

Which ONE of the following identifies ...

(1) the minimum required logic to initiate an automatic containment ventilation isolation signal and (2) whether the 1-RM-90-1 06, Lower Containment Radiation Monitor control board indication remains valid after the isolation signal?

Note: 1-RM-90-130 & 131, Containment Purge Rad Monitors A. (1) Both rad monitors (90-130 & 131) must reach the high setpoint; (2) VALID.

B. (1) Both rad monitors (90-130 & & 131) must reach the high setpoint; (2) NOT VALID.

C. (1) ONLY one rad monitor (90-130 OR 131) must reach the high setpoint; (2) VALID.

D. (1)

(1 ) ONLY one rad monitor (90-130 OR 131) must reach the high setpoint; (2) NOT VALID.

Page 61

Feb/2010 Sequoyah RO NRC Exam

-.. 3/312010 31312010 .--

62. In accordance with AOP-M.06, "Loss of Spent Fuel Cooling," which ONE of the following identifies ...

(1) The basis for the 40°F minimum spent fuel pit (SFP) temperature limit and (2) The condition that could result if the SFP temperature exceeded 192°F?

A. (1) Criticality analysis.

(2) Excessive gassing from the SFP.

B. (1) Criticality analysis.

(2) Spent Fuel Pool Cooling pump cavitation.

C. (1) Fuel reliability.

(2) Excessive gassing from the SFP.

D. (1) Fuel reliability.

(2) Spent Fuel Pool Cooling pump cavitation.

Page 62

Feb/2010 Sequoyah RO NRC Exam

- -3/3/2010 31312010 .- -- -

63. Which ONE of the following describes the function of the Unit 1 Manipulator Crane SENSOTEC load system interlock, SEN 8H, "light assembly" overload limit switch?

A. Stops upward motion of the hoist and illuminates the overload light.

B. Prevents the gripper from disengaging at any bridge location.

C. Stops hoist travel in the down direction, if the bridge is over the reactor core and the gripper is not disengaged.

D. Stops bridge travel at the edge of the reactor until the trolley is aligned with the transfer system centerline.

Page 63

Feb/2010 Sequoyah RO NRC Exam 31312010

64. Which ONE of the following identifies ...

(1) the signal that is used to derive the SG level control program setpoint and (2) the basis for the zero load SG level setpoint?

A. (1) Main Steam header pressure.

(2) To prevent flooding the Moisture Separators if a rapid load increase occurred.

B. (1) Main Steam header pressure.

(2) To limit containment pressure rise resulting from a steam line break accident.

c. (1) Main Turbine impulse pressure.

C.

(2) To prevent flooding the Moisture Separators if a rapid load increase occurred D. (1) Main Turbine impulse pressure.

(2) To limit containment pressure rise resulting from a steam line break accident.

Page 64

Feb/2010 Sequoyah RO NRC Exam

-. 31312010---

313/2010

65. Which ONE of the following choices completes both statements?

The Main Feedwater Pump Seal Water Injection System taps off of the condensate system _ _ _ __

A sustained condition with low seal water ____ will cause a MFW Pump to automatically trip.

A. between the condenser and condensate booster pumps; injection pressure at 220 psig B. between the condenser and condensate booster pumps; differential pressure at 10 psid C. downstream of the condensate booster pumps; injection pressure at 220 psig D. downstream of the condensate booster pumps; differential pressure at 10 psid Page 65

Feb/2010 Sequoyah RO NRC Exam 313120tO**

31312010 . -- -

66. Using the attached ICS AFD TARGET DISPLAY screen printout, which ONE of the choices completes the following statements?

The AFD HIGH LIMIT is _ __ _ _

If was/were outside of the limit, TS LCO 3.2.1, "Axial Flux Difference," action statement will be entered.

REFERENCE PROVIDED A. 7.2; any NIS channel B. 7.2; at least 2 NIS channels C.4; any NIS channel D.4; at least 2 NIS channels Page 66

Feb/2010 Sequoyah RO NRC Exam

- - --3/31201

-31312010IT -

67. Given the following:

Unit 2 is in Mode 4 with plant heatup in progress.

- 2A-A Diesel Generator is being rolled in accordance with 0-SO-82-3, "Diesel Generator 2A-A." prior to the performance of a monthly surveillance.

Which ONE of the following identifies the status of the 2A-A Diesel Generator while it is being rolled and the maximum time frame that the start of the diesel generator can be delayed before the diesel generator pre-start roll must be re-performed?

DG Status Maximum time A. Operable 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 8.

B. Operable 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C. Inoperable 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months D. Inoperable 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Page 67

Feb/2010 Sequoyah RO NRC Exam

. - 3/312010- -

31312010-*--~---- -- ~- -- -- -- -- --- --- -----

68. Which ONE of the following identifies the reason the pressurizer manway must be open with air flow unobstructed whenever the reactor head is in place and the SG U-tubes are drained or pressurizer level is off scale low in accordance with O-GO-9, 0-GO-9, "Refueling Procedure?"

This ensures ....

A. that on a loss of level in the RCS rapid refill capability using RHR pumps would be available.

B. that a steam void in the RCS piping would not prevent natural circulation flow.

C. an adequate vent exists to allow gravity fill from RWST on a station blackout event.

D. an adequate vent exists to prevent a vacuum from being developed in the RCS piping on a rapid loss of RCS level.

Page 68

Feb/2010 Sequoyah RO NRC Exam 31312010 31312010*-

69. While performing a cooldown on Unit 1 from Mode 3 to Mode 4 the following parameters were logged:

Time RCS Temp PZR UQLlQ Space Temp 0200 553°F 650°F 0230 52rF 527°F 606°F 0300 505°F 560°F 0330 44rF 447°F 494°F 0400 402°F 440°F Which ONE of the following identifies the cooldown rate that was exceeded and the maximum time allowed to restore the parameter/temperature to within limits in accordance with TS 3.4.9.1, "RCS Pressure and Temperature Limits" or TR 3.4.9.2, "Pressurizer Temperature Limits?"

A. RCS cooldown rate limits were exceeded; TS 3.4.9.1 action is required within a maximum of 30 minutes.

B. RCS cooldown rate limits were exceeded; TS 3.4.9.1 action is required within a maximum of 60 minutes.

C. PZR cooldown rate limits were exceeded; TR 3.4.9.2 action is required within a maximum of 30 minutes.

D. PZR cooldown rate limits were exceeded; TR 3.4.9.2 action is required within a maximum of 60 minutes.

Page 69

Feb/2010 Sequoyah RO NRC Exam

- -. 31312010-3/312010

70. During a prejob brief, an operator discovers a procedure step meets the critical step criteria listed in SPP-2.2, "Administration of Site Technical Procedures"; however, it is not identified as a critical step.

Which ONE of the choices completes the following statements?

The procedure step (1)

Critical steps performed outside the control room require (2) ,in accordance with OPDP-1, "Conduct of Operations."

A. (1) can be marked or highlighted to identify the step as a Critical Step and the procedure performed prior to revision.

(2) a Peer Check B. (1) can be marked or highlighted to identify the step as a Critical Step and the procedure performed prior to revision.

(2) Independent Verification C. (1) will require a revision prior to performance. (cannot be performed as is)

(2) a Peer Check D. (1) will require a revision prior to performance. (cannot be performed as is)

(2) Independent Verification Page 70

Feb/2010 Sequoyah RO NRC Exam

. 3/312010 3131201 ()

71. Which ONE of the following identifies the incore flux detector requirements listed in O-SI-OPS-OOO-011.0, 0-SI-OPS-000-011.0, "Containment Access Control During Modes 1 - 4," for an entry into lower containment or the annulus?

Required Incore Flux Detector Placement Tagged with a ...

A. Storage position only Caution Order B. Storage position only Hold Order C. Storage position or inserted Caution Order to within 10 feet of the core D. Storage position or inserted Hold Order to within 10 feet of the core Page 71

Feb/2010 Sequoyah RO NRC Exam 310IL.010

-- 31S12010

72. Given the following:

- A source check is to be performed on CCS radiation monitor 1-RE-90-123.

Which ONE of the following identifies how the source check is verified and whether the isolation function of the Surge Tanks vent can be manually blocked during the source check in accordance with 1-S0-90-1, "Liquid Process Radiation Monitors?"

A. Observing the analog rate meter trending upscale; Isolation function can be manually blocked.

B. Observing the analog rate meter trending upscale; Isolation function can NOT be manually blocked.

C. Observing the bargraph display responds upscale; Isolation function can be manually blocked.

D. Observing the bargraph display responds upscale; Isolation function can NOT be manually blocked.

Page 72

Feb/2010 Sequoyah RO NRC Exam

- .- 31312010 3131201 0

73. Which ONE of the following completes the following statement in accordance with the General Requirements in RCI-10, "ALARA Program?"

The shall approve all Containment Building Entries during periods which are outside the pre-determined Containment Building entry schedule. Approvals shall be documented on an Attachment 6, "Containment Building Entry Request!Authorization."

Authorizatio n."

A. Plant Manager B. Radiation Operations Shift Supervisor C. Radiation Protection Manager D. Shift Manager Page 73

Feb/2010 Sequoyah RO NRC Exam

-31312010 31S12010

74. Which ONE of the following completes the following statement in accordance with EPIP-8, "Personnel Accountability and Evacuation?"

The "2-Person-Line-of-Sight Rule" is required _ _ _ _ and requires that - ----

A. any time EPIP-8 is implemented only persons in vital areas must remain in visual contact with another person.

B. any time EPIP-8 is implemented all persons in the protected area must remain in visual contact with another person.

C. when a Credible Insider Threat exists only persons in vital areas must remain in visual contact with another person.

D. when a Credible Insider Threat exists all persons in the protected area must remain in visual contact with another person.

Page 74

Feb/2010 Sequoyah RO NRC Exam 31312010

75. Given the following:

- A LOCA has occurred on Unit 1 resulting in a Reactor Trip and Safety Injection.

- The crew is responding in accordance with E-1, "Loss of Reactor or Secondary Coolant."

- Annunciator 'LS-63-50A RWST LVL La' LO' (M6E, E-3) alarms.

- Containment Sump Level indicates 50%.

1-FCV-74-3 and 1-FCV-74-21, RHR PUMP SUCTION ISOL valves are open.

1-FCV-63-72 and 1-FCV-63-73, CNTMT SUMP SUCT TO RHR PUMP valves are closed.

Which ONE of the following identifies the status of the RHR suction alignment and the required operator response in accordance with ES-1.3, "Transfer to RHR Containment Sump?"

A. The valves are NOT aligned correctly.

Place 1-HS-63-72 and 1-HS-63-73, 'CNMT SUMP SUCT TO RHR PUMP' valves to OPEN to initiate the transfer of the RHR pump suction to the containment sump.

B. The valves are NOT aligned correctly.

Place 1-HS-74-3 and 1-HS-74-21, 'RHR PUMP SUCTION ISOL' valves to CLOSE to initiate the transfer of the RHR pump suction to the containment sump.

C. The valves are aligned correctly.

Ensure that auto swapover occurs when annunciator 'LS-63-50B RWST LVL La-La' LO-LO' (M6E, E4) alarms.

D. The valves are aligned correctly.

Ensure that auto swapover occurs when annunciator 'LS-63-1 04 CONTAINMENT SUMP FULL' (M6C, E-3) alarms.

Page 75

Sequoyah 2010 NRC Examination RO Reference Package

1. Steam Tables

2. Mollier diagram

3. 1-SI-OPS-000-002.0 Shift Log pg 19 of 68

4. Unit 2 Curve 2 PTS Limits

5. ICS AFD TARGET DISPLAY

SON 1-SI-OPS-OOO-002.0 SHIFT LOG Rev. 94 1 Page,19 of 68 APPENDIX APPENDIXA A Page 9 of 27 Surveillance Ref. Mode Notes TS Limits Instrument Units 0630-1830 1830-0630 REMARKS No N-41 %

1,2 26 OPERABLE N-42 %

Nuclear 4.3.1.1.1.A.2 4.3.1.1.1A2 N-43 %

Instrumentation 4.3.1.1.1.A.5 N-44 %

1,2 27 OPERABLE N-35 %

N-36 %

UO/RO Review Initials NOTES

26. COMPARE the four power range channels to each other. This constitutes an adequate "channel check" and acceptable deviation between channels is equal to or less than 3.5%.

27. COMPARE the two intermediClte rClnge r,mge chClnnels channels located on paneI1-M-4. ReCldings on both chClnnels channels viill v.Jill provide evidence that the instruments are operable.

Agreement between the readings provides additional verification of channel oper8bility. Control Board Bomd indicators are verified operable if they are reading within 0.75 decades of each other. Use the following examples as a guide to determine the the..75 75 decade deviation. The following equation will convert the IRM Indicated

% RTP to a voltage value which can be used to determine the IRM indication difference and to determine if those readings are within the. 75 decades acceptance limit.

the .75 The IRM 10 decade scale is equal to 10 volts, thus each decade is equivalent to 1 volt.

N-35 is Log (% IRM RTP) :: ::: Voltage Log Difference between N-35 and N-36 EXLlmpie LOG (% IRM RTP) indic<lting indicZlting (30%)::

(30%)::: Voltage is 0.125 which is within the .75

1 il1 ::::: Voltage RTf' 30% RTf" 1.4771::

1.t1771 ::: 1.'1771 1.t1771 volts Diffcrnnn: = 1.G021 -1.4771::

Diffcrnncc:: -1.4771::: 0.125 decade acceptance range.

N-36 is Log (% IRM RTP) :: ::: Voltage Log indicating (40%) ::::: Voltage 40% RTP 1.6021 ::::: 1.6021 volts N-35 is Log (% IRM RTP) :: ::: Voltage Log Difference between N-35 and N-36 is Example LOG (% IRM RTP) indicating (15%) ::: Voltage (15%):: 0.753 which is outside the .75 decade

Voltage

15% RTP 1.176::

1.176::: 1.176 volts Difference::

Difference::: 1.929 - 1.176 :: ::: 0.753 acceptance range. Notify the UO and SRO f/2

2 of the deviation.

N-36 is Log (% IRM RTP) :: ::: Voltage Log indicating (85%) :: ::: Voltage 85% RTP 1.929 :: 1.929 volts 1.929:::

SQN UNIT 2 2-FR-O 2-FR-D Rev, Rev. 1 CURVE 2 PTS LIMITS 3000 II U I I i i i-I i LLlJ_iLLLLJ 1:_1 I I I I ! I : I i i i i I ! i I I 1--1 I I ! I I"i-I~I p'igr~+/-!T[b::t:LfjTH +I-'_L~dI-lIJ.. ILl I U I LLLLL! ! I I ! I i I I I I i i -rr-l LJ_!---LL.LJ-Li I i ! I I_LU I I I I I' II rTl"l I I 1 ~ 1,..+-

I I I i I I I L! LLU I . I II ! II 'I I I l::t:i !TTT-LLIL25GO t +~ I-I ,"" r- -i-f-J.. /--* ;"'<;I ..~~"?-! "': :'" ~! 1

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Page 8 of 16', 16

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- 02*FEB*2010 02-FEB-2010 14: l~:SQ.

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ML100830628

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