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V. C. Summer June 2007 Exam Nos. 05000395/2007301 Final SRO as Given Written Exam
	ML071930561
Person / Time
Site:	Summer
Issue date:	06/13/2007
From:	; South Carolina Electric & Gas Co
To:	; Office of Nuclear Reactor Regulation
References
	2007-301, 50-395/07-301 50-395/07-301
	Download: ML071930561 (104)
	v • d • e

Final Submittal (Blue Paper)

V t,. S)()()1/f)l?r 2(07- ~O/

.~f)e. /3/ 2,{)o7 AS Givw Senior Operator Written Examination

v. C. SUMMER JUNE 2007 EXAM EXAM NO. 05000395/2007301 JUNE 4 - 8, 2007 (OP TEST)

JUNE 13,2007 (WRITTEN EXAM)

u.s. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: ,- Facility/Unit:

JUne 13 2fJOlj V* ~ *SUfYI lner Region: II Reactor Type: W 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 overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to complete the combined examination, and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months if you are only taking the SRO portion.

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

Applicant's Signature Results RO/SRO-OnlylTotal Examination Values -- / -- / -- Points Applicant's Scores -- / -- / -- Points

-

Applicant's Grade -- / -- / -- Percent

Name: 2007 NRC Exam SRO

1. Given the following:

The unit is at 85% power at MOL.

A continuous uncontrolled control rod withdrawal occurs .

Which ONE (1) of the following parameters will DECREASE?

A. Steam Generator Pressure B. Main Generator Electrical Output C. Overpower Delta T setpoint D. VCT Level 1

2007 NRC Exam SRO

2. Given the following plant conditions:

A LOCA has occurred.

RCS pressure is 1750 psig and lowering .

Reactor Building pressure is 4 psig and rising.

Steam Generator pressures are 1000 psig and stable.

Which ONE (1) of the following describes the actuations that are a result of this condition?

A. Safety Injection ONLY.

B. Safety Injection and Containment Ventilation Isolation ONLY.

C. Safety Injection and Containment Isolation Phase A and Containment Ventilation Isolation ONLY.

D. Safety Injection and Containment Isolation Phase A and Containment Ventilation Isolation and Containment Isolation Phase B.

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2007 NRC Exam SRO

3. Given the following plant condit ions:

The crew is responding to an ATWS lAW EOP-13.0, Response to Abnormal Nuclear Power Generation, and is attempting an emergency borat ion of the RCS.

MVT-81 04, EMERG BORATE , valve will not open.

Which ONE (1) of the following describes the required actions to be performed and why?

A. Open the Charging Pump Suction Header Isolation valves as directed by AOP-1 06.1, Emergency Boration, to maximize Boric Acid flowrate.

B. Open LCV-115B/D, RWST to CHG PP Suet, as directed by AOP-106 .1, Emergency Boration, to borate via cold leg injection .

C. Open the Charging Pump Suction Header Isolation valves as directed by EOP-13.0 ,

Response to Abnormal Nuclear Power Generation, to maximize Boric Acid flowrate.

D. Open LCV-115B/D, RWSTto CHG PP Suet, as directed by EOP-13 .0, Response to Abnormal Nuclear Power Generation , to borate via cold leg injection.

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2007 NRC Exam SRO

4. Which ONE (1) of the following describes the setpoints for the two (2) annunciators below?

RCP AlBIC THERM BAR & BRG FLO LO CCBP DISCH HDR PRESS LO A. 90 gpm 30 psig B. 90 gpm 70 psig C. 50 gpm 30 psig D. 50 gpm 70 psig 4

2007 NRC Exam SRO

5. Given the following plant conditions:

The plant is in Mode 5.

The PZR is solid .

RCS temperature is 190°F.

RCS pressure is 315 psig .

Letdown Pressure Control Valve PCV-145 is in AUTO.

FCV-605A, "A" gyp, and FCV-605B, "B" BYP, are in MANUAL.

Which ONE (1) of the following describes a condition that will initially cause PCV-145 to CLOSE?

A. Lowering the output of the controller for the in-service RHR heat exchanger flow control valve.

B. Raising CCW flow through the in-service RHR Heat Exchanger.

C. Lowering the setpoint of PCV-145.

D. Starting an additional RHR Pump.

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2007 NRC Exam SRO

6. Given the following plant conditions:

The plant is in Mode 6.

"B" Train RHR is in service.

"A" Train RHR is out of service and expected to be returned to service in approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Refueling is in progress .

Cavity level is 23.5 feet above the reactor vessel flange.

"B" RHR Pump trips and cannot be restarted .

Which ONE (1) of the following describes the operational restriction(s) associated with this event?

A. Refueling Cavity level must be raised to greater than 24 feet above the reactor vessel flange prior to continuing refueling activities.

B. Refueling activities are permitted for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months while repairs are initiated to "B" RHR Pump.

C. All containment penetrations with a direct path to atmosphere must immediately be verified closed .

D. Suspend all activ ities that could result in a reduction in boron concentration of the RCS.

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2007 NRC Exam SRO

7. Given the following plant conditions:

The plant was operating at 100% power.

7.2 KV Transformer XTF-4 was lost due to a fault.

The associated DIG did NOT start as designed.

Subsequently, a LOCA caused a reactor trip and safety injection.

RCS pressure is currently 350 psig and trending down slowly.

Which ONE (1) of the following describes the operation of RHR Pumps for this condition?

A. RHR pump A running with its miniflow valve open B. RHR pump A running with its miniflow valve closed C. RHR pump B running with its miniflow valve open D. RHR pump B running with its miniflow valve closed 7

2007 NRC Exam SRO

8. Which ONE (1) of the following directly supplies power to Charging Pump "A" and RHR Pump "A"?

Charging Pump "A" RHR Pump "A" A. 1DA 1DA B. 1DA1 1DA C. 1DA 1DA1 D. 1DA1 1DA1 8

2007 NRC Exam SRO

9. Given the following plant conditions:

The plant is operating in Mode 1 at 100% power.

The following indications are reported by the RO.

TI-471, PRT Temperature is trending up and is now at 158°F.

PI-472, PRT Pressure is trending up and is now at 8 psig.

Which ONE (1) of the following components, if leaking, will cause this condition?

A. XVR-8708A, RHR Pump "A" Suction Relief Valve.

B. XVR-8121, RCP Seal Return Relief Valve.

C. XVR-7169, RCDT Pumps Suction Relief Valve.

D. XVS-8010, PZR Safety Valve.

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2007 NRC Exam SRO

10. Which ONE (1) of the following describes an immediate action and the basis for the action in accordance with EOP-1.0, Reactor Trip/Safety Injection Actuation?

A. Insert control rods in Manual; to insert negative reactivity by the most direct manner possible.

B. Insert control rods in Manual; to reduce or maintain RCS pressure to prevent lifting the Pressurizer safety valves.

C. Place EHC Pumps in PULL-TO-LK NON-A; to prevent uncontrolled cooldown of the RCS.

D. Place EHC Pumps in PULL-TO-LK NON-A; to minimize secondary makeup requirements.

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2007 NRC Exam SRO

11. Given the following plant conditions:

A reactor trip and safety injection have occurred.

RCS pressure is 1050 psig and lowering.

Tavg is 550°F and lowering.

Pressurizer level is 65% and rising rapidly.

Reactor Building pressure is 2 psig and rising.

Which ONE (1) of the following describes the cause of this event?

A. Letdown line break.

B. SBLOCA on an RCS cold leg.

C. Stuck open pressurizer PORV.

D. Stuck open pressurizer spray valve.

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2007 NRC Exam SRO

12. Given the following:

The plant is at 100% power.

All systems are in their normal alignments .

A leak occurs in the Letdown Heat Exchanger.

Assuming no action by the crew, which ONE (1) of the following describes the effect(s) on the CCW System?

A. RM-L2A/B indication rises . Surge Tank vent valve PW-7096 closes when the indication reaches the ALERT level.

B. RM-L2A1B indication rises . Surge Tank vent valve PW-7096 closes when the indication reaches the HI RAD level.

C. Surge Tank level lowers . CCW Booster Pumps will trip on low suction pressure.

D. Surge Tank level lowers. CCW Pumps will/ose suction when the Surge Tank empties.

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2007 NRC Exam SRO

13. Given the following plant conditions:

A LOCA occurred and RCS pressure reached 1380 psig.

All actions of EOP-1.0 were performed as required.

The crew is performing EOP-2 .1 , Post-LOCA Coo/down and Depressurization.

RCS pressure is currently 1335 psig.

RCS temperature is currently 496°F.

Two Charging pumps are running .

The crew is evaluating stopping 1 Charging Pump.

Given the above conditions, which ONE (1) of the following describes whether the Charging Pump may be stopped, and why?

A. No, because subcooling is not greater than 30°F.

B. Yes, because subcooling is greater than 30°F.

C. Yes, because subcooling is greater than 87.5°F.

D. No, because subcooling is not greater than 87.5°F.

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2007 NRC Exam SRO

14. Given the following plant conditions:

The Plant is in Mode 3.

A PZR PORV begins leaking to the PRT.

Pressurizer pressure is 985 psig.

PRT pressure is steady at 5 psig .

PRT temperature is steady at 90°F.

Assume:

Ambient heat losses are negligible.

Steam quality in the pressurizer is 100%.

Which ONE (1) of the following would be the approximate MCB indication on TI-463 ,

RELIEF TEMP OF?

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2007 NRG Exam SRO

15. Given the following plant conditions:

The Reactor has tripped from 100% power.

"A" and "G" Service Water (SW) pumps were running .

The crew implemented EOP-1 .0, Reactor Trip/Safety Injection Actuation, then transitioned to EOP-1 .1, Reactor Trip Recovery.

MDEFW pumps started on Lo-Lo SG levels after the trip.

Subsequently, an SI actuated due to a Large Break LOGA.

Which ONE (1) of the following describes the operation of equipment as a result of the SI?

A. MDEFW pumps will trip and be restarted by the sequencer. Service Water Pumps "A" and "G" will continue to run.

B. MDEFW pumps will continue to run. Service Water Pumps "A" and "G" will trip and be restarted by the sequencer.

G. MDEFW pumps will trip and be restarted by the sequencer. Service Water Pumps "A" and "G" will trip and be restarted by the sequencer.

D. MDEFW pumps will continue to run. Service Water Pumps "A" and "G" will continue to run.

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2007 NRC Exam SRO

16. Given the following plant conditions:

A load rejection has occurred from 100% power.

All control systems responded as designed.

Power level is now stable at 70%.

Which ONE (1) of the following conditions will exist during this event?

A. Charging Flow Control Valve, FCV-122 , will be throttling open.

B. Pressurizer Backup Heaters will be energized.

C. Pressurizer PORVs will be open.

D. Letdown Backpressure Control Valve PCV-145 will be throttling closed.

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2007 NRC Exam SRO

17. Given the following plant conditions :

A reactor trip has occurred from 100% power.

Reactor Trip Breaker "B" remains CLOSED.

Which ONE (1) of the following describes the effect on the Steam Dump System?

A. The steam dump valves will open and maintain Tavg at 55rF.

B. The steam dumps will remain closed following the reactor trip due to loss of the arming signal.

C. The steam dumps will remain closed following the reactor trip due to loss of the

'plant trip' modulation signal.

D. The steam dump valves will open and maintain Tavg at 559°F.

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2007 NRC Exam SRO

18. Which ONE (1) of the following describes the source of control power to Reactor Trip Breaker "B" and Reactor Trip Bypass Breaker "B"?

Reactor Trip Breaker B Reactor Trip Bypass Breaker B A. 125 VDC Bus 1HB 125 VDC Bus 1HB B. 125 VDC Bus 1HB 125 VDC Bus 1HA C. 120 VAC APN-5902 120 VAC APN-5902 D. 120 VAC APN-5902 120 VAC APN-5901 18

2007 NRG Exam SRO

19. Given the following plant cond itions:

A reactor trip has occurred coincident with a loss of off-site power.

While performing action in the EOPs, the following events occur :

RGS pressure is 1700 psig and lowering.

RB pressure is 4.7 psig and rising slowly.

Three minutes after these indications are observed , APN-5904 fails and becomes de-energized.

Which ONE (1) of the following describes the effect , if any, on plant equipment after the APN failure?

A. Train A and Train B EGGS equipment is operating as required ; Train A and Train B RB Spray Pump discharge valves are open.

B. Train A and Tra in B EGGS equipment is operating as required; Train A and Train B RB Spray Pump discharge valves are closed.

G. Train A EGGS equipment is operating as required; Train B EGGS equipment is NOT running; Train A and Train B RB Spray Pump discharge valves are open.

D. Train A EGGS equipment is operating as required ; Train B EGGS equipment is NOT running; Train A and Train B RB Spray Pump discharge valves are closed.

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2007 NRC Exam SRO

20. Given the following plant conditions:

A LOCA has occurred.

RCS pressure is 200 psig.

"A" Reactor Building Spray Pump is Out of Service.

Containment pressure has exceeded the High-3 setpoint.

Train "B" Phase A has failed to actuate.

All other actuations and Train "A" ECCS equipment is running as required.

The most recent Chemistry sample of the RCS indicated that RCS activity is 5X10-2 microcuries/ml Dose Equivalent Iodine.

Assuming no action by the crew, which ONE (1) of the following describes the effect on the plant?

A. Containment will exceed its design pressure.

B. Off-Site releases will exceed accident analysis assumptions.

C. Only 1 Containment Isolation Valve in each Phase A penetration will be closed.

D. Only half of the Containment penetrations required for isolation will receive isolation signals.

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2007 NRC Exam SRO

21. Given the following plant conditions:

A reactor startup is in progress.

SR Channel N-31 indicates 7X10 3 CPS.

SR Channel N-32 indicates 7X103 CPS.

IR Channel N-35 indicates 8.7X10- 6% power.

IR Channel N-36 indicates 6.0X10- 6% power.

Which ONE (1) of the following describes (1) the existing plant condition, (2) the status of P-6, and (3) the action required in accordance with AOP-401.8, Intermediate Range Channel Failure?

A. (1) N-36 is undercompensated ;

(2) P-6 should NOT be satisfied; (3) maintain power stable until N-36 is repaired.

B. (1) N-36 is overcompensated; (2) P-6 should be satisfied; (3) maintain power stable until N-36 is repaired.

C. (1) N-36 is undercompensated ;

(2) P-6 should be satisfied ;

(3) place the unit in Mode 3 until N-36 is repaired .

D. (1) N-36 is overcompensated ;

(2) P-6 should NOT be satisfied; (3) place the unit in Mode 3 until N-36 is repaired.

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2007 NRC Exam SRO

22. Given the following plant conditions:

The plant is operating at 8% power.

A Loss of Component Cooling Water has occurred.

"A" RCP motor bearing temperature is 189°F and rising slowly.

"A" RCP lower seal water bear ing temperature is 226°F and rising slowly.

The crew has entered AOP-118 .1, Loss of Component Cooling Water.

Which ONE (1) of the following actions is required?

A. RCP motor bearing temperature exceeds operating limits . Stop 'A' RCP and initiate a plant shutdown lAW GOP-4B, Power Operation (Mode 1-Descending).

B. RCP lower seal water bearing temperature exceeds operating limits. Stop 'A' RCP and initiate a plant shutdown lAW GOP-4B, Power Operation (Mode 1-Descending) .

C. RCP motor bearing temperature exceeds operating limits . Trip the reactor , stop 'A' RCP, and go to EOP-1.0, Reactor Trip/Safety Injection Actuation.

D. RCP lower seal water bearing temperature exceeds operating limits. Trip the reactor, stop 'A' RCP , and go to EOP-1 .0, Reactor Trip/Safety Injection Actuation.

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2007 NRC Exam SRO

23. Given the following plant conditions:

The plant is in Mode 3.

The following wide-range pressures are indicated:

PT-402 - 1335 psig

PT-403 - 1350 psig

PT-455A - 1285 psig

Subcooling indication on TI-499A and TI-499B indicates the following :

TI-499A TI-499B Which ONE (1) of the following describes the core exit temperature used to determine RCS subcooling for the indications above?

A. Train A - 550°F; Train B - 560°F.

B. Train A - 55rF; Train B - 550°F.

C. Train A - 55rF ; Train B - 560°F.

D. Train A - 560°F; Train B - 55rF.

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2007 NRC Exam SRO

24. Given the following plant conditions:

A Reactor Trip condition existed and the Reactor failed to trip.

RCS pressure now indicates 2350 psig.

Assuming no other events are in progress , which ONE (1) of the following describes the 1) appropriate action and the 2) reason for that action?

A. 1) Verify PZR PORVs and Block Valves open

2) To increase flow on FI-943 , CHG LOOP B CLO/HOT LEG FLOW GPM B. 1) Ver ify PZR PORVs and Block Valves open

2) To increase flow on FI-110, EMERG BORATE FLOW GPM C. 1) Place both ESFLS A(B) Resets to NON-ESF LCKOUTS

2) To increase flow on FI-943 , CHG LOOP B CLO/HOT LEG FLOW GPM D. 1) Place both ESFLS A(B) Resets to NON-ESF LCKOUTS

2) To increase flow on FI-110, EMERG BORATE FLOW GPM 24

2007 NRC Exam SRO

25. Given the following plant conditions:

The plant was at 100% power.

A reactor trip and safety injection occurred .

R8CUs XFN-0064A and XFN-00648 started in SLOW.

While performing the actions of EOP-1.0, Reactor Trip/Safety Injection Actuation, the following alarms are received in the control room:

XCP-605-3-1, SW FR R8CU 18/28 FLO LO

XCP-605-3-2, SW FR R8CU 18/28 PRESS LO Which ONE (1) of the following choices contains both of the conditions that could each independently cause these annunciators to alarm?

A. SW8P "8" tripped; MVG-31118, R8CU 648/658 TO IND COOLING going CLOSED.

8 . SW8P "8" tripped; MVG-3109C, R8CU 648 OUTLET ISOL going CLOSED.

C. XFN-00648 (18 R8CU SS FAN) tripped; MVG-3108C, R8CU 648 INLET ISOL going CLOSED.

D. XFN-00648 (18 R8CU SS FAN) tripped; MVG-3109D, R8CU 658 OUTLET ISOL going CLOSED.

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2007 NRC Exam SRO

26. Which ONE (1) of the following describes the power supplies that directly feed Containment Spray Header Isolation Valves XVG-3003A and XVG-3003B ,

respectively?

A. XSW1DA1 and XSW1DB1 B. XMC1 DA2X and XMC1 DB2Y C. XMC1 DB2X and XMC1 DA2Z D. XMC1 DA2Z and XMC1 DB2X 26

2007 NRC Exam SRO

27. Given the following plant conditions:

A LOCA has occurred.

RCS pressure is 450 psig .

Reactor Building pressure is 18 psig and lowering.

RWST level is lowering.

Reactor Building Sump level is rising.

"A" Reactor Trip Breaker remained closed.

Which ONE (1) of the following describes the operation of the Reactor Building Spray system as the event continues?

RB Spray Pump suction to the RB Sump Valves, MVG-3005A and B . . .

A. are manually opened when RWST level reaches its setpoint. RB Spray Pump suction valves from RWST, MVG-3001 A and B, are manually closed when MVG-3005A and B are fully open.

B. automatically open when RWST level reaches its setpoint. RB Spray Pump suction valves from RWST, MVG-3001A and B, automatically close when MVG-3005A and B are fully open .

C. are manually opened when Reactor Building Sump level reaches its setpoint. RB Spray Pump suction valves from RWST , MVG-3001A and B, are manually closed when MVG~3005A and B are fully open.

D. automatically open when Reactor Building Sump level reaches its setpoint. RB Spray Pump suction valves from RWST, MVG-3001A and B, automatically close when MVG-3005A and B are fully open.

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2007 NRC Exam SRO

28. With the unit at 100% power, which ONE (1) of the following describes the potential consequence of PCV-444C , PZR Spray Valve, failing open?

A. Loss of PZR pressure can result in an unwarranted OP Delta T runback and reactor trip.

B. PZR pressure will remain stable as PZR heaters will compensate for the pressure reduction.

C. Loss of PZR pressure may result in steam formation in the reactor vessel head and SG tubes.

I D. Loss of PZR pressure can result in an unwarranted OT Delta T runback and reactor trip.

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2007 NRC Exam SRO

29. Which ONE (1) of the following describes the purpose and function of the Reactor Building Charcoal Cleanup Units?

Designed for ...

A. primary means of long term post accident iodine removal from the RB atmosphere.

Discharge is aligned to the RB Purge system exhaust.

B. primary means of long term post accident iodine removal from the RB atmosphere.

Discharge is aligned to the RB atmosphere.

C. RB pre-entry reduction of airborne contaminants. Discharge is aligned to the RB Purge system exhaust.

D. RB pre-entry reduction of airborne contaminants . Discharge is aligned to the RB atmosphere.

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2007 NRC Exam SRO

30. Given the following plant conditions:

The unit was initially operating at full power.

A loss of ALL offsite power occurred in conjunction with a steam generator tube rupture.

All safeguards equipment functioned as required.

The following plant conditions now exist:

Ruptured S/G pressure = 1100 psig, stable

Core exit TC = 505°F, slowly decreasing

RCS Pressure =1600 psig , stable

PZR Level = 4%, stable

Total SI Flow = 600 gpm

The RCS has been cooled down to target temperature .

In accordance with EOP-4 .0, Steam Generator Tube Rupture, the RO opens one PZR PORV.

Soon after opening the valve, the operator observes that all channels of PZR level are rapidly increasing.

ECCS flow has increased from 600 gpm to 650 gpm.

Which ONE (1) of the following is the cause of this indication?

A. PZR level instruments are not calibrated for temperatures less than 600°F.

B. Safety injection flow is driving the RCS to a water - solid condition .

C. Voiding in the reactor vessel head is forcing water up the surge line.

D. Backflow has been established from the ruptured S/G to the RCS.

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2007 NRC Exam SRO

31. Given the following plant conditions:

A Large Break LOCA has occurred.

Reactor Building H2 concentration was at 2% and rising.

'A' Hydrogen Recombiner is INOPERABLE.

Which ONE (1) of the following describes the effect on the removal of Hydrogen from Containment?

A. Hydrogen concentration will remain below 4% with only one Recombiner in operation.

B. Hydrogen concentration will rise above 4% but remain below 6% with only one Recombiner in operation .

C. Hydrogen concentration will remain below 4% only if the Containment Purge System is placed in service in addition to the Recombiner.

D. Hydrogen concentration will remain below 4% only if Containment Spray is placed in service in addition to the Recombiner.

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2007 NRC Exam SRO

32. Which ONE (1) of the following describes a feature of the Spent Fuel Pool and/or Cooling system that will maintain radiation dose levels at acceptable limits during plant operations?

A. Spent Fuel Cooling Pumps will trip on low suction pressure prior to Spent Fuel Pool level dropping below 460'6" .

B. Boron concentration is maintained so that Spent Fuel Pool Keff is less than 0.95 and Spent Fuel Pool Radiation levels are maintained less than 2.5 mr/hr at the surface of the pool.

C. Anti-siphoning holes in the cooling system suction and return lines ensures that Spent Fuel Pool level will not drop below 460'6".

D. Interlocks on the Spent Fuel Pool Manipulator Crane prevent spent fuel assemblies from travelling closer than 23 feet from the surface of the Spent Fuel Pool.

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2007 NRC Exam SRO

33. Which ONE (1) of the following describes the initial SG Level Response and SGWLC

. System Response during a rapid increase in power?

SG Level Response SGWLC System Response A. Decreases Lag circuit on SG level input minimizes fluctuations B. Decreases Programmed DIP across the FRV minimizes fluctuations C. Increases Programmed DIP across the FRV minimizes fluctuations D. Increases Lag circuit on SG level input minimizes fluctuations 33

2007 NRC Exam SRO

34. Given the following plant conditions:

The plant is in Mode 6, core reload is in progress.

A fuel assembly is being inserted into the core when downward motion stops.

The Refueling SRO notes the following:

The SLACK CABLE light is ON

The LOWER SLOW ZONE light is OFF

The GRIPPER TUBE DOWN light is OFF Which ONE (1) of the following describes the reason that downward movement stopped and the subsequent operation related to the interlock?

A. Total load fell more than 150-300# below nominal full load; bypassing the interlock is not possible.

B. The fuel assembly approached 10" from the bottom of the core ; bypassing the interlock is not possible.

C. Total load fell more than 150-300# below nominal full load ; bypass the interlock to allow the assembly to be fully inserted.

D. The fuel assembly approached 10" from the bottom of the core; bypass the interlock to allow the assembly to be fully inserted.

34

2007 NRC Exam SRO

35. Given the following plant conditions:

Reactor power is 75%.

RCS leak rate data is as follows:

Total RCS leakage rate is 9.1 gpm.

Leakage to PRT is 7.0 gpm .

Leakage to the Reactor Coolant Drain Tank is 1.3 gpm .

Total primary to secondary leakage is 0.33 gpm.

SG 1 - 0.09 gpm

SG 2 - 0.17 gpm SG 3 - 0.07 gpm Which ONE (1) of the following describes RCS leakage in relation to Technical Specification limits?

A. Identified leakage exceeds the TS limit B. Unidentified leakage exceeds the TS limit C. Primary to Secondary leakage exceeds the TS limit D. All RCS leakage is within TS limits 35

2007 NRC Exam SRO

36. Given the following plant conditions:

The unit is in Mode 3.

A steam line break has occurred on "A" Steam Line in the Reactor Building.

Which ONE (1) of the following describes the plant response to this event?

A. "A" Main Steam Line pressure will drop. "B" and "C" Main Steam Line pressures will remain constant. All MSIVs will close when at least 2 Containment pressure transmitters indicate 3.6 psig.

B. "A" Main Steam Line pressure will drop . "B" and "C" Main Steam Line pressures will remain constant. All MSIVs will close when "A" Main Steam Line pressure indicates less than 675 psig.

C. All 3 Main Steam Line pressures will drop. All MSIVs will close when at least 2 Containment pressure transmitters indicate 3.6 psig.

D. All 3 Main Steam Line pressures will drop. All MSIVs will close when at least 2 Main Steam Lines indicate less than 675 psig .

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2007 NRC Exam SRO

37. Which ONE (1) of the following describes the purpose of C-9, Condenser Ava ilability, and C-16 , Condenser Pressure, permissive signals?

A. C-9 prevents 2 steam dump valves from operating during conditions that could damage the condensers.

C-16 arms ALL condenser dump valves when condenser is below 4.5" Hg abs and adequate eire water pumps are available.

B. C-9 arms ALL condenser dump valves when condenser is below 7.5" Hg abs and adequate eire water pumps are available.

C-16 prevents 2 steam dump valves from operating during conditions that could damage the condensers.

C. C-9 anticipates condenser heat load problems by blocking 2 condenser dump valves at 7.5 "Hg abs.

C-16 prevents ALL condenser steam dump valves from operating during conditions that could damage the condensers.

D. C-9 prevents ALL condenser steam dump valves from operating during conditions that could damage the condensers.

C-16 anticipates condenser heat load problems by blocking 2 condenser dump valves at 4.5 "Hg abs.

37

2007 NRC Exam SRO

38. Given the following plant conditions:

The plant is operating at 100% power.

A Feedwater Line Break occurs at the piping connection to "A" SG.

Which ONE (1) of the following describes the effect of this event?

A. RCS temperature rises prior to reactor trip . SG "A" continues to depressurize after FWIV closure .

B. RCS temperature lowers prior to reactor trip. SG "A" continues to depressurize after FWIV closure.

C. RCS temperatures lowers prior to reactor trip. SG "A" pressure stablilizes after FWIV closure .

D. RCS temperature rises prior to reactor trip . SG "A" pressure stablizes after FWIV closure.

38

2007 NRC Exam SRO

39. Given the following plant cond itions :

A Station Blackout has occurred.

The crew is restoring off-site power to Bus 1DA through the normal feed.

Prior to closing the normal feeder breaker to Bus 1DA, which ONE (1) of the follow ing sets of actions must be performed , in accordance with AOP-304.1 , Loss of Bus 1DA with Diesel Unavailable?

A. De-energize Train "A" ESFLS Ensure Bus 1DA TRANSFER INIT Switch is in OFF B. De-energize Train "A" ESFLS Ensure Bus 1DA TRANSFER INIT Switch is in ON C. Reset NON-ESF LCKOUTS & AUTO-START BLOCKS Ensure Bus 1DA TRANSFER INIT Switch is in OFF D. Reset NON-ESF LCKOUTS & AUTO-START BLOCKS Ensure Bus 1DA TRANSFER INIT Switch is in ON 39

2007 NRC Exam SRO

40. Given the following plant conditions:

A loss of off-site power has occurred.

Both EDGs have responded as designed.

Subsequently, safety injection occurs .

The following conditions exist on "A" EDG:

Frequency 59.9 Hz.

Voltage 7150 Volts

KW Output 2600 KW RB Pressure reaches an actuation setpoint requiring the start of "A" RB Spray pump Loads stabilize . . . . .

Which ONE (1) of the following describes the status of "A" EDG?

A. All listed parameters are within limits.

B. Frequency is below the limit.

C. Voltage is below the limit.

D. Output exceeds the continuous KW rating.

40

2007 NRC Exam SRO

41. Given the following plant conditions:

lAW GOP-4A, Power Operation (Mode 1-Ascending) , power has been stabilized between 12 and 15%.

Preparations are being made to roll the Main Turbine to 1800 rpm.

Reactor power indicates the following :

IR N 1X101%.

IR N 1X101%.

PR N 15%.

PR N 14%.

PR N 14%.

PR N 14%.

Inverter XIT-5902 output breaker trips open .

Which ONE (1) of the following describes the effect on the unit?

A. A Power Range Rod Stop (C-2) signal, with no change in reactor power.

B. A reactor trip due to the deenergization of Intermediate Range Channel N-35.

C. A reactor trip due to the deenergization of Intermediate Range Channel N-36.

D. An Intermediate Range Rod Stop (C-1) signal , with no change in reactor power.

41

2007 NRC Exam SRO

42. Given the following plant conditions:

The plant is operating at 100% power.

The following annunciators are received in the control room:

XCP-636, 4-6, DC SYS OVRVOLT/UNDRVOLT

XCP-637, 1-5, INV 3/4 TROUBLE Inverter output voltage indicates 120 vac .

Assuming NO other alarms are received, which ONE (1) of the following describes the common cause of both of the alarms?

A. Loss of Alternate Source 1FB.

B. Loss of Normal Source 1DB2Y.

C. Loss of voltage on Bus 1HB.

D. Inverter has transferred to Alternate Source 1FB.

42

2007 NRC Exam SRO

43. Given the following plant conditions:

The plant is operating at 100% power.

The following alarm is received:

XCP-624-1-5 , SG A LVL DEV

The RO determines that SG "A" level is rising slowly on L1-474, 475, and 476.

SG "B" and "C" levels are stable.

Which ONE (1) of the following describes the cause of the alarm and the action required?

Alarm was received on a .. .

A. 5% deviation from program due to a Feedwater Control Valve failure; Place "A" Feedwater Control valve in manual and restore level to normal.

B. 5% deviation from program due to a Steam Flow input to "A" SG level control failing low; Select the alternate feed flow and steam flow inputs.

C. 10% deviation from program due to a Feedwater Control Valve failure; Place "A" Feedwater Control valve in manual and restore level to normal.

D. 10% deviation from prog ram due to a Steam Flow input to "A" SG level control failing low; Select the alternate feed flow and steam flow inputs.

43

2007 NRC Exam SRO

44. Which ONE (1) of the following conditions will result in the most Emergency Feedwater System flow required to maintain SG levels constant following a reactor trip?

Core Burnup Initial Power Level A. 1,000 MWO/MTU 10%

B. 1,000 MWO/MTU 100%

C. 10,000 MWO MTU 10%

O. 10,000 MWO/MTU 100%

44

2007 NRC Exam SRO

45. Given the following plant conditions:

The plant is at 100% power during an A 1 maintenance week.

APN-5901 has been transferred to APN-1 FA while work is in progress on XIT-5901 .

The normal feeder breaker for bus 1DA trips open.

"A" DIG fails to start.

Which ONE (1) of the following describes the subsequent operation of the "A" Train ESFLS?

A. Output 1 will shed loads and the ESFLS will go through its normal sequence.

B. Output 1 will shed loads, but then the ESFLS will be prevented from operating.

C. Output 1 will NOT shed loads, but the ESFLS will go through its normal sequence.

D. Output 1 will NOT shed loads and the ESFLS will be prevented from operating.

45

2007 NRC Exam SRO

46. Which ONE (1) of the following describes the availability of Channell (Train A) 120 VAC vital safeguards power during a loss of the 115KV line from the Parr Generating Complex?

A. Is initially available from Battery 1A through inverter XIT-5901, then automatically returns to the normal source after Diesel Generator "A" starts.

B. The static switch initially transfers the supply to 1FA, then automatically returns to the normal source after Diesel Generator "A" starts.

C. Is initially available from Battery 1A through inverter XIT-5901, then is manually returned to the normal source after Diesel Generator "A" starts.

D. The static switch initially transfers the supply to 1FA, then is manually returned to the normal source after Diesel Generator "A" starts.

46

2007 NRC Exam SRO 47 . The plant is at 100% power .

A loss of 125 VDC control power to the will require entry to EOP-1.0, Reactor Trip/Safety Injection Actuation.

A. FWBP breakers B. MSIVs C. RCP breakers D. PZR Spray Valves 47

2007 NRC Exam SRO

48. Given the following plant conditions:

A loss of off-site power has occurred.

Both EDGs start as required.

Which ONE (1) of the following describes the operation of the EDG Room Ventilation system?

Automatically start when ...

A. Diesel Room temperature exceeds 88°F, to maintain room temperature below the Technical Specification limit of 120°F.

B. the associated Diesel Generator starts, to maintain room temperature below the Technical Specification limit of 88°F.

C. Diesel Room temperature exceeds 72°F, to maintain room temperature below the Technical Specification limit of 88°F.

D. the associated Diesel Generator starts , to maintain room temperature below the Technical Specification limit of 120°F.

48

2007 NRC Exam SRO

49. Given the following plant conditions:

Emergency Diesel Generator "A" is paralleled to its associated Bus.

A lagging power factor has been established.

Which ONE (1) of the following describes the operation of the diesel generator voltage control switch?

A. Lowering the voltage control setpoint will cause the generator to pick up a larger share of the real load.

B. Raising the voltage control setpoint will cause the generator to pick up a larger share of the real load.

C. Lowering the voltage control setpoint will cause the generator to pick up a larger share of the reactive load .

D. Raising the voltage control setpoint will cause the generator to pick up a larger share of the reactive load.

49

2007 NRC Exam SRO

50. Given the following plant conditions:

A loss of RB Instrument Air has occurred .

RB Instrument Air header pressure is currently 94 psig and lowering .

Assuming no operator action , which ONE (1) of the following describes the response of the Air System and why?

RB Instrument Air header pressure decreases until. ..

A. PVA-2659, INST AIR TO RB AIR SERV, automatically opens at 90 psig to ensure an air supply for AOVs inside the Reactor Building.

B. PVA-2659, INST AIR TO RB AIR SERV, automatically opens at 93 psig to ensure an air supply for AOVs inside the Reactor Building.

C. PVT-2660, AIR SPLY TO RB , closes at 90 psig to isolate the RB header to avoid a loss of Instrument Air outside the Reactor Building.

D. PVT-2660, AIR SPLY TO RB, closes at 93 psig to isolate the RB header to avoid a loss of Instrument Air outside the Reactor Building.

50

2007 NRC Exam SRO

51. Given the following plant conditions:

The plant is in Mode 6.

Reactor Building Purge is in operation .

Refueling activities are in progress.

A spent fuel assembly is dropped in the cavity.

Containment radiation monitor indications are all rising.

Which ONE (1) of the following describes the radiation monitors that will initiate isolation of all or part of the Containment Purge?

RM-A4, RB Purge Exhaust Particulate (Iodine) (Gas) Atmos monitor...

A. ONLY.

B. AND RM-G17A/B, RB Manipulator Crane Area Gamma ONLY.

C. AND RM-A2, RB Sample Line Particulate (Iodine) (Gas) Atmos monitor ONLY.

D. AND RM-G17A/B, RB Manipulator Crane Area Gamma , AND RM-A2, RB Sample Line Particulate (Iodine) (Gas) Atmos monitor.

51

2007 NRC Exam SRO

52. Given the following plant conditions:

An immediate discharge to the penstocks from both Waste Monitor tanks is required.

Current conditions are as follows.

RM-L5 and RM-L9 are out of service

Fairfield Hydro is in the "pumping" mode.

Which ONE (1) of the following statements will provide the MINIMUM conditions necessary for monitor tank release?

A. Either RM-L5 or RM-L9 must be restored to operability prior to release.

B. Both RM-L5 and RM-L9 must be restored to operability prior to release.

C. The Fairfield Hydro must convert to the generating mode and redundant samples performed prior to release. Two independent qualified individuals must verify release calculations and valve lineups.

D. The Fairfield Hydro must convert to the generating mode prior to release and either RM-L5 or RM-L9 must be restored to operability. Two independent qualified individuals must ver ify release calculations and valve lineups.

52

2007 NRC Exam SRO

53. Which ONE (1) of the following describes operation of XFN-30A(B), CONTR RM EMERG FILTERING SYS FAN A(B), and XFN-32A(B), CONTROL ROOM COOLING UNIT A(B) FAN upon receipt of a high radiation alarm on RM-A1, Control Bldg Supply Air?

A. Both XFN-32A & B and both XFN-30A & B start, all outside air sources are isolated.

B. Both XFN-32A & B and both XFN-30A & B start, return air is mixed with a small amount of makeup air.

C. Both XFN-32A & B trip and both XFN-30A & B start, all outside air sources are isolated.

D. Both XFN-32A & B trip and both XFN-30A & B start, return air is mixed with a small amount of makeup air.

53

2007 NRC Exam SRO

54. Given the following plant conditions:

The plant is in Mode 5.

RHR Train A is in service.

RCS temperature is 158°F.

RCS pressure is 175 psig .

Subsequently, a Loss of Service Water occurs.

The crew is performing actions contained in AOP-117.1, Total Loss of Service Water.

NEITHER Service Water loop can be restored.

Which ONE (1) of the following describes the effect on the RHR System, and the procedure that will mitigate the event?

A. Stabilize RHR/RCS system temperature using steam dumps lAW GOP-5, Plant Shutdown Mode 3 to Mode 5. Go to AOP-115 .3, Loss of RHR with the RCS Intact, for long-term mitigation.

B. Stabilize RHR/RCS system temperature using steam dumps lAW GOP-5, Plant Shutdown Mode 3 to Mode 5. Continue using AOP-117 .1 , Total Loss of Service Water, for long-term mitigation.

C. RHR/RCS system temperature will rise as a result of a loss of cooling to Component Cooling Water. Go to AOP-115.3, Loss of RHR with the RCS Intact.

D. RHR/RCS system temperature will rise as a result of a loss of cooling to Component Cooling Water. Continue using AOP-117.1, Total Loss of Service Water.

54

2007 NRC Exam SRO

55. Which ONE (1) of the following provides the electrical power supply to the Supplemental Air Compressor?

A. XSW1DA1

8. XSW1D81 C. XSW1A1 D. XSW181 55

2007 NRC Exam SRO

56. Given the following plant conditions:

The Fire Protection System actuated due to a Main Transformer Fire.

System pressure dropped to 80 psig before recovering due to the actuation of necessary equipment.

The fire is out.

The deluge valve is isolated and reset.

Which ONE (1) of the following describes the equipment that is running , and the method of shutting the equipment down?

A. ONLY theMotor Driven Fire Pump is running; must be stopped locally.

B. ONLY the Motor Driven Fire Pump is running ; may be stopped locally or in the control room.

C. The Motor Driven and Engine Driven Fire Pumps are running . Both must be stopped locally.

D. The Motor Driven and Engine Driven Fire Pumps are running. The Motor Driven Pump may be stopped locally or in the control room, the Engine Driven Pump must be stopped locally .

56

2007 NRC Exam SRO

57. Given the following plant conditions:

A LOCA has occurred.

Safety Injection is actuated .

Reactor Building pressure indicates 14 psig and rising slowly.

While performing actions of EOP-1 .0, Reactor Trip/Safety Injection Actuation, the following valves indicate OPEN:

RCP SL WfR ISOL 8100

LTDN ISOL 8152

RB AIR SERV ISOL 2660 Which ONE (1) of the following describes the failure that has occurred and the MINIMUM action necessary to mitigate the condition?

A. Phase A has partially failed. Place either Phase A actuation switches in the ACTUATE position .

B. Phase A has partially failed. Place both Phase A actuation switches in the ACTUATE position .

C. Phase B has partially failed . Place either Phase B actuation switches in the ACTUATE position .

D. Phase B has partially failed . Place both Phase B actuation switches in the ACTUATE position.

57

2007 NRC Exam SRO 58 . Given the following plant conditions:

The reactor has tripped . Safety Injection is actuated.

An RCS cooldown is in progress in accordance with EOP-2 .1, Post LOGA Goo/down and Depressurization.

The following table is a plot of the cooldown:

TIME RCS TCOLD TIME RCS TCOLD 0800 54rF 0945 425°F 0815 530°F 1000 395°F 0830 520°F 1015 382°F 0845 505°F 1030 364°F 0900 498°F 1045 340°F 0915 478°F 1100 310°F 0930 44rF 1115 280°F At which time was the Tech Spec RCS Cooldown rate limit FIRST exceeded?

A. 0915.

B. 0930.

C. 1000.

D. 1115 58

2007 NRC Exam SRO

59. Given the following plant conditions:

A LOCA outside containment has occurred.

The crew is performing the actions in EOP-2.5, LOCA Outside Containment.

Which ONE (1) of the following actions will be attempted to isolate the break and which indication is used to determine if the leak has been isolated in accordance with EOP-2.5?

A. Isolate low pressure Safety Injection piping.

RCS pressure is monitored, because SI flow will repressurize the RCS when the break is isolated.

B. Isolate low pressure Safety Injection piping.

PZR level is monitored, because when the break is isolated, RCS inventory will rapidly rise.

C. Isolate high pressure Safety Injection piping .

RCS pressure is monitored, because SI flow will repressurize the RCS when the break is isolated.

D. Isolate high pressure Safety Injection piping.

PZR level is monitored, because when the break is isolated, RCS inventory will rapidly rise.

59

2007 NRC Exam SRO

60. Which ONE (1) of the following describes the reason that a RED condition on the Integrity CSF Status Tree may develop while performing actions of EOP-14.1 ,

Response to Degraded Core Cooling?

A. Core Exit Thermocouple temperature will decrease rapidly when Low Head SI Pumps are started and SI flow is initiated .

B. Core Exit Thermocouple temperature will decrease rapidly when SG depressurization and SI Accumulator injection occur.

C. RCS Cold Leg temperature will decrease rapidly when Low Head SI Pumps are started and SI flow is initiated.

D. RCS Cold Leg temperature will decrease rapidly when SG depressurization and SI Accumulator injection occur.

60

2007 NRC Exam SRO

61. Given the following plant conditions:

A LOCA has occurred.

The crew is performing actions contained in EOP-2 .0, Loss of Reactor or Secondary Coolant.

The following conditions currently exist:

Integrity - RED

Containment - RED

Subcriticality - ORANGE

Core Cooling - ORANGE

Inventory - YELLOW

Heat Sink - YELLOW Which ONE (1) of the following describes the correct procedure flowpath for these conditions?

A. EOP-17.0 , Response to High Reactor Building Pressure, followed by EOP-16 .0, Response to Imminent Pressurizer Thermal Shock Condition.

B. EOP-16.0 , Response to Imminent Pressurizer Thermal Shock Condition, followed by EOP-17.0, Response to High Reactor Building Pressure.

C. EOP-14.1, Response to Degraded Core Cooling, followed by EOP-16.0, Response to Imminent Pressurizer Thermal Shock Condition.

D. EOP-16 .0, Response to Imminent Pressurizer Thermal Shock Condition, followed by EOP-14 .1, Response to Degraded Core Cooling.

61

2007 NRC Exam SRO 62 . Given the following plant conditions:

A reactor trip has occurred due to a loss of offsite power.

The crew is performing actions of EOP-1.4, Natural Circulation Cooldown with Steam Void in Vessel.

During the event, RCP seal cooling was lost, but subsequently restored .

The operating crew is preparing to initiate the RCS cooldown.

The following conditions are indicated:

RVLlS NR level is 89%.

RCS subcooling is 60°F.

PZR Level is 72% and stable .

Which ONE (1) of the following actions is required in accordance with EOP-1.4?

A. Use PZR Heaters as necessary to saturate PZR water and continue in EOP-1.4.

B. Initiate Safety Injection and go to EOP-1.0, Reactor Trip Or Safety Injection .

C. Start a RCP and go to the applicable portion of the appropriate GOP.

D. Return to EOP-1.3, Natural Circulation Cooldown.

62

2007 NRC Exam SRO

63. Given the following plant conditions:

A LOCA has occurred.

Due to low RHR Sump Level, the crew has transitioned from EOP-2.2, Transfer to Cold Leg Recirculation, to EOP-2.4, Loss Of Emergency Coolant Recirculation.

All automatic actions occurred as designed.

Two Charging pumps and two RHR pumps are running.

Both RB Spray Pumps are running.

RHR, Charging, and RB Spray pump amps and flow are stable.

RWST level is approximately 5% and continues to lower.

Which ONE (1) of the following describes how the Charging, RHR, and RB Spray pumps should be operated in accordance with EOP-2.4?

Charging Pumps RB Spray Pumps RHR Pumps A. Stop BOTH Leave BOTH running Leave BOTH running B. Stop ONE Stop BOTH Stop ONE C. Stop BOTH Stop BOTH Stop BOTH D. Leave BOTH running Leave BOTH Running Stop ONE 63

2007 NRC Exam SRO 64 . The crew is performing actions of EOP-3.1, Uncontrolled Depressurization ofAll Steam Generators.

Which ONE (1) of the following describes the Technical Specification implications of the event?

A. RCS cooldown rates above 100°F per hour may potentially result in non-ductile failure of the reactor vessel.

B. Pressurizer coo/down rates above 100°F per hour may potentially result in pressurized thermal shock to the pressurizer.

C. Loss of SG inventory may ultimately result in the RCS Pressure Safety Limit being exceeded.

D. Loss of SG inventory may ultimately result in the Reactor Core Safety Limit being exceeded.

64

2007 NRC Exam SRO

65. Which ONE (1) of the following describes the status of RB ventilation and RBCU's upon completion of the actions contained in EOP-17.2 , Response to High Reactor Building Radiation Level?

A. RB Purge isolated All RBCU fans in SLOW B. RB Purge isolated RBCU fans selected on switch RBCU TRAIN AlB EMERG , running in SLOW C. RB Mini Purge in service All RBCU fans in SLOW D. RB Mini Purge in service RBCU fans selected on switch RBCU TRAIN AlB EMERG , running in SLOW 65

2007 NRC Exam SRO 66 . In accordance with OAP-100A, Communication, which ONE (1) of the following communications should use the phonetic alphabet?

A. Communications involving safety system trains. (Train Alpha)

B. Communications involving manipulation of plant components. (Alpha Charging Pump)

C. Communications describing Containment Isolation (Phase Bravo)

D. All communications that are not 'information only'.

66

2007 NRC Exam SRO

67. Given the following plant conditions :

The plant is at 46% power and increasing lAW GOP-4A, Power Operation (Ascending) at 3% per hour.

A loss of Feedwater occurs .

All three S/G NR levels are at 5% and lowering.

It is now 60 seconds later.

Which ONE (1) of the following is the expected response of the ATWS Mitigation System Actuation Circuitry (AMSAC)?

A. AMSAC will NOT actuate because it is not armed .

B. AMSAC will TRIP the reactor and START the EFW pumps.

C. AMSAC will NOT actuate because the time delay on reactor power has not timed out.

D. AMSAC will TRIP the main turbine and START the EFW pumps.

67

2007 NRC Exam SRO

68. Given the following plant conditions:

An RCS leak is in progress.

The crew is performing the appropriate AOP for the plant condition .

Letdown is isolated .

Charging flow is maximized.

RCS pressure is 1990 psig and lowering.

Reactor Building pressure is 1.8 psig and rising.

Pressurizer level is 18% and lowering .

VCT level is 15% and lowering.

Which ONE (1) of the following describes the status of the plant and the action required?

A. An RPS setpoint has been exceeded. Trip the Reactor and initiate Safety Injection when immediate actions of EOP-1 .0 have been completed.

B. An RPS setpoint has been exceeded. Trip the reactor and concurrently perform actions of the in-use AOP when immediate actions of EOP-1.0 have been completed.

C. An RPS setpoint has NOT been exceeded, Trip the Reactor, perform the immediate actions of EOP-1.0, then initiate Safety Injection.

D. An RPS setpoint has NOT been exceeded, Trip the Reactor, perform the immediate actions of EOP-1 .0, continue to implement the AOP concurrently, then initiate Safety Injection when Pressurizer level is <12%.

68

2007 NRC Exam SRO

69. The unit is at 100% power.

All systems are in normal alignments.

Which ONE (1) of the following activities requires entry into a technical specification LCO action statement?

A. CCW Pump B mechanical seal repair.

B. Charging Pump A removal from service for oil change.

C. Boric Acid Transfer Pump recirc valve leak repair.

D. RHR Heat Exchanger Discharge flow control valve repair.

69

2007 NRC Exam SRO

70. Which ONE (1) of the following describes the MINIMUM Source Range Nuclear Instrumentation requ irement that must be met prior to off-loading fuel from the reactor vessel?

Visual in control room Audible in control room Audible in RB A. 1 1 1 B. 2 1 1 C. 2 2 1 D. 2 2 2 70

2007 NRC Exam SRO 71 . Given the following information:

A 27 year old new V.C Summer employee has a fully completed NRC Form 4 and a 2007 radiation exposure history as follows :

2650 millirem from previous employment with Progress Energy in 2007.

110 millirem since becoming a V.C. Summer employee.

Which ONE (1) of the following describes the MAXIMUM ADDITIONAL exposure the employee may receive prior to reaching his MAXIMUM Admin istrative Dose Control Limit, including any applicable extensions , lAW HPP-0153, Administrative Exposure Limits?

A. 1240 millirem B. 1350 millirem C. 2240 millirem D. 2350 millirem 71

2007 NRC Exam SRO

72. Given the following plant conditions:

A General Emergency exists.

The TSC is manned.

A valve in the Aux Building must be closed to prevent damage to valuable safety related equipment.

Radiation levels are extremely high.

Which ONE (1) of the following describes the maximum dose that is allowed to perform this operation and whose permission is required?

An individual may receive . . .

A. Up to 10 Rem with permission from the Duty SS B. 25 Rem, or more, with permission from the Duty SS C. Up to 10 Rem with permission from the ED D. 25 Rem, or more, with permission from the ED 72

2007 NRC Exam SRO

73. Given the following plant conditions:

A reactor trip and safety injection have occurred.

Off-Site power is lost subsequent to safety injection actuation.

Equipment failures during performance of EOP-2.0, Loss of Reactor or Secondary Coolant, resulted in the following conditions :

Bus 1DA is de-energized due to a fault.

CSF Status Trees indicate as follows :

Subcriticality GREEN

Core Cooling ORANGE

Heat Sink RED

Integrity GREEN

Containment YELLOW

Inventory YELLOW Which ONE (1) of the following describes the requirement for Critical Safety Function Status Tree Monitoring in accordance with OAP-103.04, EOPIAOP User's Guide?

A. Continuous monitoring is required.

B. Monitor every 5 - 10 minutes unless a change in status occurs.

C. Monitor every 10 - 20 minutes unless a change in status occurs .

D. Monitored for information only.

73

2007 NRC Exam SRO

74. Given the following plant conditions:

T=O A fire is occurring in the Aux Building 436'.

T+2 Fire Brigade Leader reports to the scene.

T+15 Notification of Unusual Event declared.

In accordance with EPP-013, Plant Fire, who, by title, is coordinating the fire fighting efforts with the Fire Brigade Leader?

A. Shift Supervisor B. Emergency Director C. OSC Supervisor D. Health Physics Shift Leader 74

2007 NRC Exam SRO

75. Given the following plant conditions :

The Unit is in Mode 5.

RCS Drain Down to Mid Loop is in progress in preparation for welding on a Hot Leg opening .

RHR Pump A is in service .

During the drain down , RHR amps and discharge pressure begin fluctuating erratically.

The crew enters AOP-115.1 , RHR Pump Vortexing.

The drain-down is stopped.

Which ONE (1) of the following describes the FIRST action that will be required in accordance with AOP-115.1?

A. Reduce RHR flow.

B. Align the RHR Pump to the RWST.

C. Raise RCS level.

D. Vent the operating RHR loop.

75

2007 NRC Exam SRO 76 . Given the following plant conditions:

The plant is at 50% power.

ALL controls are in automatic.

ALL MCB switches are in their normal position for this power level.

An event occurs resulting in the following indications:

RCS Tavg rising approximately 5°F above Tref.

Reactor Power is rising.

First Stage Pressure Transmitter PT-446 indicates 330 psig and stable.

First Stage Pressure Transmitter PT-447 indicates 800 psig.

Control Bank D is withdrawing at 16 steps per minute.

Which ONE (1) of the following describes the procedure entry required to mitigate the event and the reason for the procedural actions taken?

A. AOP-403.3 , Continuous Control Rod Motion; to minimize the impact on power distribution limits.

B. AOP-403.3, Continuous Control Rod Motion; to prevent an out of spec negative DELTA-I.

C. AOP-401.7, Turbine First Stage Pressure Transmitter Failure ; to minimize the impact on power distribution limits.

D. AOP-401.7 , Turbine First Stage Pressure Transmitter Failure; to prevent an out of spec negative DELTA-I.

76

2007 NRC Exam SRO

77. Given the following plant conditions:

Following a turbine runback, the crew is stabilizing the plant in accordance with the appropriate AOP.

Control Bank "0" Group Counters are at 180 steps.

On ORPI, one Control Bank "0" rod indicates 196 steps ; all others indicate 182 steps .

The affected rod has a blown movable gripper fuse and has been determined to be trippable.

Which ONE (1) of the following actions is appropriate for this event?

Realign the mispositioned rod to meet TS limits within ...

A. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to ensure Shutdown Margin is maintained.

B. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to ensure Shutdown Margin is maintained.

C. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to ensure acceptable power distribution limits are maintained.

O. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to ensure acceptable power distribution limits are maintained .

77

2007 NRC Exam SRO

78. Given the following plant conditions :

Reactor power is 100%.

Reactor Trip Breaker testing is being performed.

Reactor Trip Bypass Breaker 'A' and Reactor Trip Breaker 'B' are both RACKED IN and CLOSED .

Reactor Trip Bypass Breaker 'B' and Reactor Trip Breaker 'A' are both RACKED OUT and OPEN.

After completion of the testing , the Electricians RACK IN and Operations attempts to CLOSE Reactor Trip Bypass Breaker B.

Immediately upon attempting closure, Reactor Trip Bypass Breaker 'B' opens.

NO other breakers reposition .

Which ONE (1) of the following describes the response to this condition?

The reactor has ...

A. NOT tripped, immediately enter EOP-13.0, Response To Abnormal Nuclear Power Generation, and direct the NROATC to commence rod insertion.

B. NOT tripped, immediately enter EOP-1 .0, Reactor Trip/Safety Injection Actuation, direct the NROATC to manually trip the reactor.

C. tripped , have an operator "backup" the reactor trip, then verify the turbine/generator has tripped .

D. tripped, direct an operator to verify turbine/generator has tripped, when time permits, direct the IBAO to locally open both Reactor Trip Breaker 'B' and Reactor Trip Bypass Breaker 'A'.

78

2007 NRC Exam SRO 79 . Given the following plant conditions:

The plant is at 100% power.

The following alarms are received in the sequence listed, approximately 10 seconds apart:

XCP-616, 1-5, PZR LCS DEV HI/La

XCP-616, 1-2, PZR LVL HI

XCP-616, 1-1, PZR LVL HI

The RO determines that PZR level indicates the following :

L1-459 indicates 95% and rising

L1-460 indicates 56% and lowering

L1-461 indicates 55% and lowering

Trip Status light CHAN 1 PZR LVL HI is illuminated Which ONE (1) of the following describes the actions that will be directed by the CRS and the TS implications?

Select unaffected PZR level channels , operate PZR heaters, and ...

A. reduce charging flow to maintain PZR level.

Does not satisfy TS LCO 3.3.1, Reactor Trip System Instrumentation ONLY .

B. reduce charging flow to maintain PZR level.

Does not satisfy TS LCO 3.3.1, Reactor Trip System Instrumentation, AND does not satisfy TS LCO 3.3.3.6, Accident Monitoring Instrumentation .

C. raise charging flow to mainta in PZR level.

Does not satisfy TS LCO 3.3.1, Reactor Trip System Instrumentation ONLY .

D. raise charging flow to maintain PZR level.

Does not satisfy TS LCO 3.3.1 , Reactor Trip System Instrumentation , AND does not satisfy TS LCO 3.3.3.6 , Accident Monitoring Instrumentation.

79

2007 NRC Exam SRO

80. Given the following plant conditions:

A manual reactor trip was performed due to high turbine vibration.

The crew is making the appropriate transition from EOP-1.0, Reactor Trip/Safety Injection Actuation.

RCS pressure is 2175 psig and slowly lowering.

PT-444, CNTRL CHAN PRESS PSIG , has failed high.

The RO reports that PZR Spray Valve PCV-444C indicates open.

Which ONE (1) of the following describes the procedure that will be used and the action required to mitigate this event?

A. Refer to AOP-401 .5, Pressurizer Pressure Control Channel Failure, while performing the EOPs. Ensure PZR Spray valves are closed and energize PZR Heaters to stabilize RCS pressure.

B. Refer to AOP-401 .5, Pressurizer Pressure Control Channel Failure, while performing the EOPs. Trip all RCPs and energize PZR Heaters to stabilize RCS pressure.

C. Go to EOP-1.1 , Reactor Trip Recovery. Trip ONLY RCP "A" and energize PZR Heaters to stabilize RCS pressure.

D. Go to EOP-1.1, Reactor Trip Recovery. Trip ALL RCPs and energize PZR Heaters to stabilize RCS pressure.

80

2007 NRC Exam SRO

81. Given the following plant conditions :

The plant is currently at full power.

The following sequence of events occurred:

0200 The normal feeder breaker to 7.2kV bus 1DA tripped open . The A EDG started and the sequencer correctly started all loads .

0215 The A EDG tripped 0220 DC bus 1HA was lost No operator actions have been taken.

The A EDG has been repaired and the operating crew is preparing to restart the EDG and reenergize 7.2kV bus 1DA.

Which ONE (1) of the following describes (1) what action is required prior to re-energizing the bus , and (2) the time allowed , by Tech Specs , to be in Mode 37 A. (1) Open all load breakers on 7.2kV bus 1DA from the MCB .

(2) 2 Hours B. (1) Open all load breakers on 7.2kV bus 1DA from the switchgear room.

(2) 2 Hours C. (1) Open all load breakers on 7.2kV bus 1DA from the MCB.

(2) 1 Hour D. (1) Open all load breakers on 7.2kV bus 1DA from the switchgear room.

(2) 1 Hour 81

2007 NRC Exam SRO

82. Given the following plant conditions:

The plant is at 100% power with all systems in normal alignments.

The RO determines that actual Pressurizer level is trending DOWN and VCT level is trending UP.

CHG LINE FLO HI/LO annunciator has actuated.

FI-122A, CHG FLOW GPM, reads 0 gpm.

Charging pump current is 5 amps.

RCS temperature and pressure are stable.

Which ONE (1) of the following describes the procedure that should be implemented and the initial actions required?

A. AOP-102.2, Loss of Charging; stop the operating Charging Pump and isolate Letdown.

B. AOP-102.2, Loss of Charging; reduce letdown to 45 gpm and verify the charging system valve lineup.

C. AOP-101.1, Loss of Reactor Coo/ant Not Requiring Sf; stop the operating Charging Pump and isolate Letdown.

D. AOP-1 01 .1, Loss of Reactor Coo/ant Not Requiring Sf; open FCV-122 as necessary and reduce Letdown to 45 gpm.

82

2007 NRC Exam SRO

83. Given the following plant conditions:

Event 5/21 1230 BOTH Train A RBCUs declared inoperable due to common cause failure.

5/28 1230 RBCUs not returned to service. Plant shutdown to Mode 3 initiated .

5/28 1645 Plant in Mode 3.

Which ONE (1) of the following describes the LATEST time on 5/28 that an initial report to the NRC must be made?

A. , 1330 B. 1630 C. 1745 D. 2045 83

2007 NRC Exam SRO

84. Given the following plant conditions:

Reactor Building Purge is desired.

RB Equipment Hatch is OPEN.

Which ONE (1) of the following describes an acceptable alignment for Reactor Building Purge?

A. 2 supply fans and 1 exhaust fan running; RM-A2 operability desired but NOT required during purge .

B. 1 supply fan and 2 exhaust fans running; RM-A2 operability desired but NOT required during purge.

C. 2 supply fans and 1 exhaust fan running; RM-A2 operability required during purge.

D. 1 supply fan and 2 exhaust fans running; RM-A2 operability required during purge.

84

2007 NRC Exam SRO

85. Given the following plant conditions:

The plant is at 47% power.

The following alarm is received in the control room:

XCP-646-2-1, RM-G19 HI RAD

The RO confirms that RM-G19B is off-scale high.

Charging Pump flow is rising slowly.

Chemistry and Health Physics have confirmed that the alarm is valid .

Which ONE (1) of the following describes additional actions that will be required in accordance with the alarm response?

A. Remove Condensate Polishers from service; Go to AOP-1 01.1, RCS Leak not Requiring SI.

B. Remove Condensate Polishers from service; Go to AOP-112 .2, SG Tube Leak not Requiring SI.

C. Place Condensate Polishers in service; Go to AOP-1 01.1, RCS Leak not Requiring SI.

D. Place Condensate Polishers in service; Go to AOP-112.2, SG Tube Leak not Requiring SI.

85

2007 NRC Exam SRO

86. Given the following plant conditions:

A transient has occurred resulting in the following alarm:

PR FLUX HI ROD STP

Reactor power indicates the following:

N41 - 101 .9% and stable

N42 - 102.8% and stable

N43 - 101.9% and stable

N44 - 103.1 % and stable

Tavg is 578°F and stable Which ONE (1) of the following has occurred, and which action(s)/procedure(s) is/are required to be implemented?

A. A Rod Stop was initiated by 1 PR channel ONLY; initiate RCS boration to reduce power in accordance with the applicable alarm response .

B. A Rod Stop was initiated by 2 PR channels; reduce turbine load to reduce power in accordance with applicable alarm response procedures.

C. A Rod Stop was initiated by 2 PR channels; initiate RCS boration to reduce power in accordance with the applicable alarm response.

D. A Rod Stop was initiated by 1 PR channel ONLY; reduce turbine load to reduce power in accordance with applicable alarm response procedures.

86

2007 NRC Exam SRO

87. Given the following plant conditions:

The plant was operating at 98% power when a loss of off-site power occurred.

Eight minutes later, the following plant conditions exist:

1DA and 1DB Bus voltage is zero (0).

RCS pressure is 2235 psig and slowly increasing.

RCS Loop T HOT is 602°F in all 3 loops and stable .

RCS Loop TCOLD is 565°F in all 3 loops and stable.

Core exit TCs indicate approximately 610°F and rising slowly.

Steam Generator pressures are approximately 1100 psig and stable .

PZR level is 20% and stable Which ONE (1) of the following describes the current plant conditions and action that will be directed?

A. Heat removal is being maintained by steam line PORVs. Verify that Natural Circulation exists in accordance with EOP-6 .2, Loss of All ESF AC Power Recovery With SI Required.

B. Heat removal is being maintained by condenser steam dumps. Verify that Natural Circulation exists in accordance with EOP-6 .1, Loss of All ESF AC Power Recovery Without SI Required.

C. Natural Circulation does not exist. Heat removal may be established in accordance with EOP-6.2, Loss of All ESF AC Power Recovery With SI Required.

D. Natural Circulation does not exist. Heat removal may be established in accordance with EOP-6.1, Loss of All ESF AC Power Recovery Without SI Required.

87

2007 NRC Exam SRO

88. Given the following plant cond itions :

A reactor trip has occurred due to loss of off-site power.

ESF equipment responds as designed.

Off-Site power has NOT been restored.

CST level indicates 14 feet.

Assuming power will be unavailable for an extended period of time , (>4 hours) which ONE (1) of the following describes the event mitigation strategy upon exit from EOP-1.0, Reactor Trip/Safety Injection Actuation?

A. Go to EOP-1 .1, Reactor Trip Recovery; cooldown the RCS using EOP-1.3, Natural Circulation Cooldown .

B. Go to EOP-1.1, Reactor Trip Recovery; stabilize the primary and secondary plants, and remain in EOP-1.1 until power is restored.

C. Go To GOP-5 , Reactor Shutdown From Startup to Hot Standby (Mode 2 to Mode 3); refer to AOP-304.3, Loss of All Balance of Plant Buses , to restore service bus power.

D. Go To GOP-5, Reactor Shutdown From Startup to Hot Standby (Mode 2 to Mode 3); refer to SOP-211, Emergency Feedwater System , to swap EFW to Service Water.

88

2007 NRC Exam SRO 89 . Given the following plant conditions:

The plant is in a normal service water system alignment with 'A' and 'B' SW pumps running.

XCP-604-1-2 "SWP A/C TRIP" alarms.

Annunciator XCP-604-1-4 "SWP AlC DISCH PRESS LO" alarms.

Annunciator XCP-605-1-4 "SWP B/C DISCH PRESS LO" alarms.

PI-4402, Service Water Pump 'A' Discharge Pressure, indicates 5 psig.

PI-4422, Service Water Pump 'B' Discharge Pressure, indicates 48 psig.

'A' SW pump will not restart.

AOP-117.1, Total Loss of Service Water, has been entered.

Which ONE (1) of the following describes the actions that should be taken to mitigate this event?

A. Refer to SOP-117, Service Water System, and ensure the 'C' SW pump automatically started on low header pressure.

B. Continue in AOP-117.1, Total Loss of Service Water, trip the reactor, and trip all RCPs.

C. Refer to SOP-117 '. Service Water System, and start the 'C' SW pump on the 'A' train.

D. Continue in AOP-117.1, Total Loss of Service Water, and isolate all CCW loads.

89

2007 NRC Exam SRO

90. Given the following plant conditions:

The plant is in Mode 5.

Welding activities in the Cable Spreading Room are in progress.

The Simplex Panel indicates actuation of Fire Protection in the room .

Maintenance reports that Fire Suppression is actuated, but there is no actual fire.

Which ONE (1) of the following describes the fire suppression actuation and the action to be taken?

A. C02; Evacuate personnel from the area and stop the discharge in accordance with the associated Fire Emergency Procedure and Fire Pre-Plan.

B. C02; Evacuate personnel from the area and stop the discharge in accordance with SOP-509, Fire Suppression System.

C. Pre-Action Sprinkler; Terminate the actuation in accordance with the associated Fire Emergency Procedure and Fire Pre-Plan.

D. Pre-Action Sprinkler; Terminate the actuation in accordance with SOP-509, Fire Suppression System.

90

2007 NRC Exam SRO

91. Given the following plant conditions:

A Steam Generator Tube Rupture has occurred.

Due to equipment failures , the crew is performing actions contained in EOP-4.3, SGTR with Loss of Reactor Coolant - Saturated Recovery.

The Shift Engineer informs you that all CSF Status Trees are GREEN with the exception of the following:

Core Cooling - YELLOW due to RVLlS level

Inventory - YELLOW due to RVLlS level Which ONE (1) of the following describes the correct implementation of procedures for this event?

A. Select another post-SGTR cooldown method lAW EOP-4.0 . Implementation of Yellow Path procedures is not allowed while in EOP-4 .3.

B. Remain in EOP-4.3 while addressing BOTH Yellow Path procedures . You may choose to implement the actions of either Yellow Path procedure .

C. Select another post-SGTR cooldown method lAW EOP-4.0 and address ONLY the Core Cooling Yellow Path , due to its higher priority.

D. Remain in EOP-4.3 and address ONLY the Inventory Yellow Path due to conflict between the Core Cooling Yellow Path and EOP-4 .3 actions.

91

2007 NRC Exam SRO

92. Given the following plant conditions.

0547 A Reactor Trip occurred

0548 Tavg = 552°F and RCS pressure is 2080 psig

0748 Tavg = 379°F and RCS pressure is 1550 psig

0948 Tavg = 248°F and RCS pressure is 1850 psig Which ONE (1) of the following describes the limit that has been exceeded and the reason why?

(REFERENCE PROVIDED)

Limit Reason A. Plant Operational Limits Curve T1 RCS pressure is too high B. Plant Operational Limits Curve T1 RCS temperature is too low C. TS Cooldown Limit (Figure 3.4-3) RCS pressure is too high D. TS Cooldown Limit (Figure 3.4-3) RCS temperature is too low 92

2007 NRC Exam SRO

93. Given the following plant conditions:

A LOCA has occurred.

The crew has completed EOP-1.0, Reactor Trip/Safety Injection Actuation, to the point of transition to another procedure.

All ESF equipment is operating as designed.

The following conditions exist in the Reactor Building :

RB Pressure 10.5 psig and rising slowly .

RHR Sump Level 424 feet and rising slowly.

Which ONE (1) of the following describes the condition that exists, the procedure transition that will be made , and the strategy for recovery?

A. ORANGE condition on High Reactor Building Pressure . Enter EOP-17.0, Response to Reactor Building High Pressure, and attempt to locate and isolate the source of the leak; notify plant staff to obtain recommended action for disposal of waste.

B. ORANGE condition on RHR Sump Level. Enter EOP-17.1, Response to Reactor Building Flooding, and attempt to locate and isolate the source of the leak; notify plant staff to obtain recommended action for disposal of waste.

C. ORANGE condition on High Reactor Building Pressure . Enter EOP-17.0, Response to Reactor Building High Pressure, and ensure RB Isolation and Heat Removal functions are satisfied.

D. ORANGE condition on RHR Sump Level. Enter EOP-17 .1, Response to Reactor Building Flooding, and ensure RB Isolation and Heat Removal functions are satisfied.

93

2007 NRC Exam SRO

94. Given the following plant conditions:

The plant is in Mode 1.

Makeup to 'A' SI Accumulator was just completed.

'A' SI Accumulator parameters are as follows:

Boron Concentration 2197 ppm

Pressure 650 psig

Level 67%

Which ONE (1) of the following describes the action required in accordance with Technical Specifications and why?

A. Restore boron concentration to within limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

To minimize the potential for reaching unacceptable peak cladding temperatures during a LOCA with postulated failure of 1 other SI Accumulator.

B. Restore boron concentration to within limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

To maintain the calculated DNBR in the core at or above the design limit during short-term transients until core is reflooded .

C. Restore pressure to within limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

To minimize the potential for reaching unacceptable peak cladding temperatures during a LOCA with postulated failure of 1 other SI Accumulator.

D. Restore pressure to within limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

To maintain the calculated DNBR in the core at or above the design limit during short-term transients until core is reflooded.

94

2007 NRC Exam SRO

95. Given the following plant conditions:

You are the Control Room Supervisor.

An explosion occurs resulting in significant damage in the unit.

The Shift Supervisor was seriously injured in the explosion and is incapacitated.

There are no procedures or directives that provide adequate direction on control of the plant and rescue of injured people for this situation .

Immediate action is required.

Which ONE (1) of the following describes the requirement for performing this action?

A. You may approve this action in accordance with 10CFR50.54(x) and (y).

B. You must obtain concurrence from one other SRO prior to performing the action.

C. The NRC must be notified prior to the action and should concur with the action to be taken.

D. The Plant Manager must be notified and should concur prior to taking the action.

95

2007 NRC Exam SRO

96. Given the following plant conditions:

100% power.

All major controls are in AUTO.

Charging Pump "A" is running.

Charging Pump "B" has been out-of-service for Auxiliary Oil Pump replacement.

Charging Pump "C" is aligned to Train "B".

Charging Pump "B" is ready for post-maintenance testing .

Which ONE (1) of the choices correctly completes the following statement regarding the operability of Train "B" during the post-maintenance testing?

Train "B" must be declared inoperable when _

A. Charging Pump "B" breaker is racked up.

B. Charging Pump "B" control power is restored .

C. Charging Pump "C" breaker is racked down.

D. Charging Pump "C" control power is de-energized.

96

2007 NRC Exam SRO

97. The plant is in Mode 1.

RCS Temperature has gone below the Technical Specification MinimumTemperature for Criticality.

If the conditions CANNOT be corrected, which ONE (1) of the following describes the MAXIMUM time allowed prior to placing the plant in Mode 3 and the basis for the action in accordance with Technical Specifications?

A. 30 minutes ; RPS Instrumentation is no longer operating in its analyzed range.

B. 30 minutes; Analysis assumptions for calculation of Mode 1 Shutdown Margin are no longer valid .

C. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; RPS Instrumentation is no longer operating in its analyzed range.

D. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; Analysis assumptions for calculation of Mode 1 Shutdown Margin are no longer valid.

97

2007 NRC Exam SRO

98. Given the following plant conditions:

The plant is coming out of a refueling outage.

Operations Dept. is performing system valve lineups.

A valve alignment in the Reactor Building should take approximately 30 minutes in a radiation field of 6 Rem/l-it.

Which ONE (1) of the following descrtibes the MINIMUM review requirements that must be met prior to performing the alignment?

A. A Pre-Job Brief and review of RWP/SRWP for valve lineups ONLY B. A review of the RWP/SRWP for valve lineups and ALARA Commitee review ONLY C. A Pre-Job Brief and ALARA Commitee Review ONLY D. A Pre-Job Brief, Review of RWP/SRWP , and ALARA Commitee Review 98

2007 NRC Exam SRO

99. Given the following plant conditions:

Mode 5 with RHR Train "A" running in the shutdown cooling mode.

RCS subcooling is 45 of.

SG "B" and "C" are available for heat removal.

A total loss of CCW flow has occurred .

Seal Injection flow is normal.

The operating crew is in AOP-118.1 , TOTAL LOSS OF COMPONENT COOLING WATER, and has referred to AOP-115 .3, LOSS OF RHR WITH THE RCS INTACT.

Which ONE (1) of the following describes the correct action and the reason for that action?

A. Stop any running RCP and RHR Pump "A" with in 10 minutes to prevent pump seal damage.

B. Align RCS Feed and Bleed within 10 minutes to provide cooling and then stop any running RCP.

C. Stop RHR Pump "A" immediately and align for RCS Bleed and Feed to provide cooling.

D. Within 90 minutes stop "A" RHR pump to prevent system damage.

99

2007 NRC Exam SRO 100 . Given the following plant conditions :

The plant is operating at 100% power.

EDG "B" is out of service and is expected to return to service in two (2) hours.

Subsequently, the following events occur:

A loss of offsite power.

The reactor is tripped and the crew enters EOP-1.0, Reactor Trip or Safety Injection.

SI is NOT actuated.

The crew made a transition to EOP-15.0, Loss of Secondary Heat Sink, based on a CSFST RED Path.

EDG "A" output breaker subsequently trips on a differentia/lockout on Bus 1DA.

Which ONE (1) of the following describes the actions that will be taken and its bases?

A. Immediately transition to EOP-6 .0, Loss Of All ESF AC Power. All other procedures in the ERG network assume both 7.2 KV ESF busses are available.

B. Immediately transition to EOP-6 .0, Loss Of All ESF AC Power. All other procedures in the ERG network assume a minimum of ONE (1) 7.2 KV ESF bus is available.

C. Remain in EOP-15.0 until feed is restored and the RED condition is cleared , and then transition to EOP-6.0 , Loss of All ESF AC Power. RED path Function Recovery procedures must be performed until the condition is cleared.

D. Remain in EOP-15.0 until directed to return to procedure in effect, and then transition to EOP-6 .0, Loss of All ESF AC Power. RED path Function Recovery procedures must be finished to completion.

100

EO P-12 .0 REVI SION 12 ATTACHM ENT 4 PAGE 2 of 2 INTEGRITY PLANT OPERATIONAL LIMITS CURVE RCS PRESSURE (PSIG) 300 0 I

.' .

_ PSIG I

I (PZR SAFETY VALVE S ASSUMED FULL OPEN)

I 2500

-

2000 10-- ---

REGION OF ACC EPTABLE OPERATION 1500

-- ---01 LIMIT T2 1000

~--- - --I LIMIT T1 I I LIM IT A t- - .

500 II

~ - ~,j o I 100 150 20 0 250 300 350 400 RCS Tcol d (o F)

PAGE 9 OF 12

REACTOR COOLANT SYSTEM MATERIAL PROPERTY BASIS LIMITING MATERIAL: INTERMEDIATE SHELL PLATE A9154-1 LIMITING ART VALUES @ 56 EFPY : 1/4T, 153°F 3/4T, 138°F Q 50 100 150 200 250 300 350 400 450 500 550 Moderator Temperature (0 F)

FIGURE 3.4-3 V . C. Summer Unit 1 Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 100 oF/hr) Applicable for 56 EFPY (Without Margins for Instrumentation Errors) Using 1998 Appendix G Methodology SUMMER - UNIT 1 3/44-32 Amendment No. 53, 113, 133 ,143 ,174

@@ Line 17: / Line 17: @@
 =Text=
-{{#Wiki_filter:Final Submittal(BluePaper)
+{{#Wiki_filter:Final Submittal (Blue Paper)
-V t,.S)()()1/f)l?r 2(07-
+V t,. S)()()1/f)l?r 2(07- ~O/
-/3/2 ,{)o7 AS Givw Senior Operator Written Examination v.C.SUMMER JUNE 2007 EXAMEXAMNO.05000395/2007301 JUNE4-8,2007(OP TEST)JUNE 13,2007 (WRITTEN EXAM) u.s.Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name: Date: ,-Facility/Unit:
+.~f)e. /3/         2,{)o7 AS    Givw Senior Operator Written Examination
-JUne 13 j 2fJOl V* Region: II Reactor Type: W Start Time: Finish Time: InstructionsUsethe 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 overall, with 70.00 percent or better on the SRO-only items if given in conjunction with theROexam;SRO-only exams given alone require a final grade of 80.00 percent to pass.You have 8 hours to complete the combined examination, and 3 hours if you are only taking the SRO portion.Applicant Certification All work done on this examinationismy own.I have neither given nor received aid.Applicant's Signature Results RO/SRO-OnlylTotal Examination Values--/--/--Points Applicant's Scores--/--/--Points-Applicant's Grade--/--/--Percent Name:---------------1.Giventhe following:*Theunitisat85%
+: v. C. SUMMER JUNE 2007 EXAM EXAM NO. 05000395/2007301 JUNE 4 - 8, 2007 (OP TEST)
-poweratMOL.*Acontinuousuncontrolledcontrolrod withdrawal occurs.WhichONE(1)ofthe following parameters will DECREASE?A.Steam Generator Pressure B.Main Generator Electrical Output C.OverpowerDeltaT setpointD.VCTLevel2007NRCExamSRO 1
+JUNE 13,2007 (WRITTEN EXAM)
-NRCExamSRO 2.Giventhefollowingplant conditions:*ALOCAhas occurred.*RCSpressureis1750psigandlowering
+u.s. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
+Date:      ,-                                 Facility/Unit:
+JUne 13 2fJOlj                            V* ~ *SUfYI lner Region:     II                                Reactor Type:    W 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 overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours to complete the combined examination, and 3 hours if you are only taking the SRO portion.
+Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
+Applicant's Signature Results RO/SRO-OnlylTotal Examination Values                          -- /  -- / --       Points Applicant's Scores                                            -- / -- /   --      Points
+                                                                                         -
+Applicant's Grade                                         --   / -- / --       Percent
+Name:                                                                2007 NRC Exam SRO
+      ---------------
+: 1. Given the following:
+* The unit is at 85% power at MOL.
+* A continuous uncontrolled control rod withdrawal occurs .
+Which ONE (1) of the following parameters will DECREASE?
+A. Steam Generator Pressure B. Main Generator Electrical Output C. Overpower Delta T setpoint D. VCT Level 1
+NRC Exam SRO
+: 2. Given the following plant conditions:
+* A LOCA has occurred.
+* RCS pressure is 1750 psig and lowering .
+* Reactor Building pressure is 4 psig and rising.
+* Steam Generator pressures are 1000 psig and stable.
+Which ONE (1) of the following describes the actuations that are a result of this condition?
+A. Safety Injection ONLY.
+B. Safety Injection and Containment Ventilation Isolation ONLY.
+C. Safety Injection and Containment Isolation Phase A and Containment Ventilation Isolation ONLY.
+D. Safety Injection and Containment Isolation Phase A and Containment Ventilation Isolation and Containment Isolation Phase B.
+NRC Exam SRO
+: 3. Given the following plant condit ions:
+* The crew is responding to an ATWS lAW EOP-13.0, Response to Abnormal Nuclear Power Generation, and is attempting an emergency borat ion of the RCS.
+* MVT-81 04, EMERG BORATE , valve will not open.
+Which ONE (1) of the following describes the required actions to be performed and why?
+A. Open the Charging Pump Suction Header Isolation valves as directed by AOP-1 06.1, Emergency Boration, to maximize Boric Acid flowrate.
+B. Open LCV-115B/D, RWST to CHG PP Suet, as directed by AOP-106 .1, Emergency Boration, to borate via cold leg injection .
+C. Open the Charging Pump Suction Header Isolation valves as directed by EOP-13.0 ,
+Response to Abnormal Nuclear Power Generation, to maximize Boric Acid flowrate.
+D. Open LCV-115B/D, RWSTto CHG PP Suet, as directed by EOP-13 .0, Response to Abnormal Nuclear Power Generation , to borate via cold leg injection.
+NRC Exam SRO
+: 4. Which ONE (1) of the following describes the setpoints for the two (2) annunciators below?
+RCP AlBIC THERM BAR & BRG FLO LO               CCBP DISCH HDR PRESS LO A.          90 gpm                                                 30 psig B.          90 gpm                                                70 psig C.          50 gpm                                                30 psig D.          50 gpm                                                70 psig 4
+NRC Exam SRO
+: 5. Given the following plant conditions:
+* The plant is in Mode 5.
+* The PZR is solid .
+* RCS temperature is 190&deg;F.
+* RCS pressure is 315 psig .
+* Letdown Pressure Control Valve PCV-145 is in AUTO.
+FCV-605A, "A" gyp, and FCV-605B, "B" BYP, are in MANUAL.
+Which ONE (1) of the following describes a condition that will initially cause PCV-145 to CLOSE?
+A. Lowering the output of the controller for the in-service RHR heat exchanger flow control valve.
+B. Raising CCW flow through the in-service RHR Heat Exchanger.
+C. Lowering the setpoint of PCV-145.
+D. Starting an additional RHR Pump.
+NRC Exam SRO
+: 6. Given the following plant conditions:
+* The plant is in Mode 6.
+       *   "B" Train RHR is in service.
+       *   "A" Train RHR is out of service and expected to be returned to service in approximately 2 hours .
+* Refueling is in progress .
+* Cavity level is 23.5 feet above the reactor vessel flange.
+   "B" RHR Pump trips and cannot be restarted .
+Which ONE (1) of the following describes the operational restriction(s) associated with this event?
+A. Refueling Cavity level must be raised to greater than 24 feet above the reactor vessel flange prior to continuing refueling activities.
+B. Refueling activities are permitted for up to 1 hour while repairs are initiated to "B" RHR Pump.
+C. All containment penetrations with a direct path to atmosphere must immediately be verified closed .
+D. Suspend all activ ities that could result in a reduction in boron concentration of the RCS.
+NRC Exam SRO
+: 7. Given the following plant conditions:
+* The plant was operating at 100

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ML071930561: Difference between revisions

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