Text

Initial Exam 2011-301 Final SRO Written Exam
	ML111260719
Person / Time
Site:	Vogtle
Issue date:	05/04/2011
From:	; NRC/RGN-II/DRS/OLB
To:	; Southern Nuclear Operating Co
References
	05-424/11-301, 05-425/11-301
	Download: ML111260719 (121)
	v • d • e

HL-16 NRC SRO Exam 2011-301

1. 001G2.4.9 002/1/2/CONT ROD W/D/3.8/4.2 C/AINEW/RO/SRO/NRC/TNT/GCW Reactor power is stable at 2 X 10

- 3 % with critical data being taken when the following indications occur.

- Red RODS OUT light illuminates on QMCB vertical panel C.

- Control Bank D begins stepping at 72 steps per minute.

- SR and lR SUR meters indicate positive SURs.

Which ONE of the following:

(1) is/are the FIRST action(s) the OATC is required to take for these indications lAW AOP-1 8003-C, Rod Control System Malfunction and (2) if no operator action is taken, which automatic function will mitigate this event?

A.

(1) Place rods in MANUAL and Rod Motion Switch in hold, verify rod motion stops.

(2) Source Range Hi Flux Trip B (1) Place rods in MANUAL and Rod Motion Switch in hold, verify rod motion stops.

(2) Intermediate Range Hi Flux Trip C. (1) Manually trip the reactor, enter 19000-C, E-O, Reactor Trip or Safety Injection.

(2) Source Range Hi Flux Trip D. (1) Manually trip the reactor, enter 19000-C, E-O, Reactor Trip or Safety Injection.

(2) Intermediate Range Hi Flux Trip Page 1 of 85

HL-16 NRC SRO Exam 2011-301

2. 001K2.05 002/2/2/CONTROL RODS-MG SETSI3. 1/3.5 MEMJHL-15R NRC/RO/SRO/NRC/TNT/GCW Which ONE of the following describes the power supplies to the Rod Drive Motor Generator (MG) sets and the breakers that are required to be locally tripped during an ATWT per 19211-C, FR-S.l, Response to Nuclear Power Generation /ATWT, if the Reactor Trip breakers will NOT open locally?

MG Set Power Supplies Breakers to Trip A.

1NBO9 and 1NB1O M/G set motor breakers B.

1NBO9 and 1NB1O M/G set output breakers C.

1 NBO8 and 1 NBO9 M/G set motor breakers D 1 NBO8 and 1 NBO9 M/G set output breakers

3. 002K5. 11 002/2/2/RCS-SECONDARY/4.0/4.2 C/AJBANKJRO/SRO/NRC/TNT/GCW Which ONE of the following symptoms is unique to a Secondary Steam Leak as compared to a Primary Coolant Leak?

A Reactor Power rising.

B. Pressurizer Level lowering.

C. Containment Pressure rising.

D. Pressurizer Pressure lowering.

Page 2 of 85

HL-16 NRC SRO Exam 2011-301

4. 003K5.03 002/2/1 /RCP-TAVE INDICATION/3. 1/3i C/A/LOIT BANK/RO/SRO/NRC/TNT/GCW Unit 1 reactor power is 6% Rated Thermal Power with all four RCPs running. The following Loop 2 and 3 RCP indications are noted by the Control Room Staff.

Loop 2 RCP: Motor Bearing Temperature = 195 °F Motor Stator Winding Temperature = 312 °F Seal Water Inlet Temperature = 224 °F RCP Shaft Vibration = 14 mils RCP Frame Vibration = 3 mils Loop 3 RCP: Motor Bearing Temperature = 185 °F Motor Stator Winding Temperature = 300 °F Seal Water Inlet Temperature = 226 °F RCP Shaft Vibration = 16 mils RCP Frame Vibration = 4 mils Based on the above indications, assuming the required operator actions are taken, which ONE of the following describes the response of the affected loop Tave and the reason for the affect on Tave?

A Loop 2 Tave will initially decrease due to securing Loop 2 RCP.

B. Loop 2 Tave will initially increase due to securing Loop 2 RCP.

C. Loop 3 Tave will initially decrease due to securing Loop 3 RCP.

D. Loop 3 Tave will initially increase due to securing Loop 3 RCP.

Page 3 of 85

HL-16 NRC SRO Exam 2011-301

5. 003K6.02 00I/2/IIRCP SEALS/2.7/3.1 MEM/LOIT BANKIRO/SRO/NRC/GCW Which ONE of the following is the CORRECT basis for closing the below listed valves while performing 19100-C, Loss of all AC Power?

1) HV-8103A, B, C, D the RCP Seal Injection Isolation valves.

2) HV-1979 ACCW Supply Header ORC Isolation valve.

A.

1) prevents seal leakage to the VCT which could relieve to the Auxiliary Building.

2) minimizes steam formation in ACCW system due to Thermal Barrier heating.

B 1) prevents potential damage to the RCP seals and shaft on CCP restarts.

2) minimizes steam formation in ACCW system due to Thermal Barrier heating.

C.

1) prevents seal leakage to the VCT which could relieve to the Auxiliary Building.

2) prevents runout of the ACCW pump as voids collapse in Thermal Barrier piping.

D.

1) prevents potential damage to the RCP seals and shaft on CCP restarts.

2) prevents runout of the ACCW pump as voids collapse in Thermal Barrier piping.

6. 004A3.06 002/2/1 /CVCS-TAVE/TREF/3.9/3.8 C/A/NEW/RO/SRO/NRC/GCW Unit 1 is at 50% power with PRZR level control system in auto.

- RCS Loop 3 NR Tcold fails high.

Which ONE of the following describes the effect on Charging Flow and RCP Seal Injection flows, with NO operator actions.

Charging Flow Seal Iniection Flows A.

Go up No Change B

Goup Goup C.

Go down No Change D.

Go down Go down Page 4 of 85

HL-16 NRC SRO Exam 2011-301

7. 005A 1.02 001/2/1 /RHR-FLOW/3.3/3.4/NEW/RO/SROINRC/TNT/GCW Given the following conditions:

- Reactor Core is de-fueled.

- 13005-1, Reactor Coolant System and Refueling Cavity Draining is in progress.

- Upper Internals are removed.

- Drain down of the Reactor Cavity and RCS to RWST using RHR is in progress.

While draining down at an elevation of> 195 feet, RHR drain down flow rate is required to be limited to (1) maximum.

When draining down at an elevation of < 194 feet, RHR drain down flow rate is required to be limited to (2) maximum.

A. (1)l500gpm (2) 500 gpm B. (1)l500gpm (2)1000 gpm C (1)3000 gpm (2) 500 gpm D. (1)3000gpm (2) 1000 gpm Page 5 of 85

IiL-16 NRC SRO Exant2011-301

8. 005A4.03 002/2/1 /RE-IR-TEMP-HTRS-FLOW/2.8/2.7 MEM!LOIT BANKIRO/SRO/NRC/GCW Given the following Unit 1 conditions:

- Both Trains of RHR are in service.

- HV-0606 and HV-0607 (RHR Hx outlets) are 50% open.

- RHR flow is throttled to 3000 gpm per train (FV-061 8 / FV-061 9 RHR Hx Bypasses).

- RCS is stable at 180°F and 340 psig.

The Shift Supervisor has directed an RCS heatup to 330°F to begin.

Which ONE of the following:

1) describes the CORRECT actions to take to commence the heatup, and

2) what is the MAXIMUM heatup rate allowed in accordance with UOP 12001-C Unit Heatup to Hot Shutdown (Mode 5 to Mode 4)?

A.

1) Adjust FV-0618 / FV-0619 to establish a heatup rate.

2) 50°F per hour.

B 1) Adjust HV-0606 / HV-0607 to establish a heatup rate.

2)100°F per hour.

C.

1) Adjust FV-0618 / FV-0619 to establish a heatup rate.

2)100°F per hour.

D.

1) Adjust HV-0606 / HV-0607 to establish a heatup rate.

2) 50°F per hour.

Page 6 of 85

HL-1 6 NRC SRO Exam 2011-301

9. 006A 1.07002/2/1 IECCS-PRESS HI-LOW/3.3/3.6 MEMINEW/RO/SROINRC/GCW Unit 1 is at 100% power.

The following is the status of each ECCS accumulator:

- Accumulator # 1 N2 pressure

- 631 psig Cb

- 1911 ppm Level

- 30%

- Accumulator # 2 N2 pressure

- 651 psig Cb

- 2100 ppm Level

- 69%

- Accumulator #3 N2 pressure -615 psig Cb -2000 ppm Level

- 51%

- Accumulator # 4 N2 pressure

- 674 psig Cb

- 2590 ppm Level

- 59%

Per Tech Spec 3.5.1, Accumulators, the ECCS accumulator parameters above are A.

within Tech Spec limits.

B.

not within Tech Spec limits due to level.

not within Tech Spec limits due to N2 pressure.

D. not within Tech Spec limits due to boron concentration.

Page 7 of 85

HL-16 NRC SRO Exam 2011-301

10. 006G2. 1.30 002/2/1/ECCS CONTROLS/4.4/4.0 CIAIMOD BANKJRO/SRO/NRC/GCW A Control Room evacuation has taken place.

- All Shutdown Panel B (PSDB) handswitches are in LOCAL.

- All Shutdown Panel A (PSDA) handswitches are in REMOTE.

- An automatic Safety Injection occurs on both trains.

Which ONE of the following is CORRECT regarding:

1) the status of the SI pumps, and

2) when SI Termination criteria is met, WHERE the SI pump(s) are required to be stopped per the procedure?

SI Pumr status Location to shutdown the SI ums A. Train A only running B Train A only running C. Both Train A and B running D. Both Train A and B running Locally at 41 60V Swgr 1 AAO2 Locally at PSDA Locally at 4160V Swgrs 1AAO2 and 1BAO3 Locally at PSDA and PSDB Page 8 of 85

HL-16 NRC SRO Exam 2011-301

11. 007A1.03 002/2/IIPRT TEMP MONITORING/2.6/2.7 MEMINEW/RO/SRO/NRC/GCW The following alarm has illuminated:

PRZR REL TANK HI TEMP Which of the following would have caused the PRT Hi Temperature and what would be the FASTEST method to restore the tank temperature to normal?

A CVCS Letdown Relief Valve (downstream of orifice isolation valves).

Cooldown using RMWST fill valve and Recirc valve to the RCDT.

B. CVCS Letdown Relief Valve (downstream of Letdown Hx).

Cooldown using RMWST fill valve and Recirc valve to the RCDT.

C. RHR Pump Suction Relief Valves.

Cooldown using recirculation method through the RCDT Hx.

D. RHR Pump Discharge Relief Valves.

Cooldown using recirculation method through the RCDT Hx.

12. OO8AK1.01 001/1/1/PZR VAPOR SPACE ACC/3.2/3.7 C/A/LOIT BANKJROISROINRCIGCW With the Unit operating at 100% power, the Reactor Trips on low Pressurizer pressure.

Pressurizer Relief Tank (PRT) pressure indicates 35 psig. The crew suspects that a PORV opened inadvertently and is now stuck partially open.

Which ONE of the following confirming indications could be expected if a PORV is stuck partially open?

A PORV relief line temperature stabilized at 281 °F. The opposite PORV and the Code Safety Valves tail pipe temperatures slowly rising.

B. PORV relief line temperature stabilized at 281 °F. The opposite PORV and the Code Safety Valves tail pipe temperatures indicate ambient temperature and stable.

C. PORV relief line temperature stabilized at 259 °F. The opposite PORV and the Code Safety Valves tail pipe temperatures slowly rising.

D. PORV relief line temperature stabilized at 259 °F. The opposite PORV and the Code Safety Valves tail pipe temperatures indicate ambient temperature and stable.

Page 9 of 85

HL-16 NRC SRO Exam 2011-301

13. 009G2.4.8 002/1/1/SB LOCA/3.8/4.5 C/AJNEW/RO/SRO/NRC/GCW A Reactor trip is performed from full power per AOP direction.

Which ONE of the following AOPs would NOT be performed concurrently while in 19000-C, Reactor Trip or Safety Injection?

A 18004-C, Reactor Coolant System Leakage due to inability to maintain PRZR level.

B.

18028-C, Loss of Instrument Air with Instrument Air pressure less than 70 psig.

C. 18034-C, Loss of Class 1 E 125V DC Power following a loss of DC bus 1AD1.

D. 18040-C, Partial Loss of Condenser Vacuum due to vacuum <23 inches Hg.

14. 01 0K6.04 002/2/1 /PRZR PRESS-PRT/2.9/3.2 C/A/LOIT BANKIRO/SRO/NRC/GCW Given the following:

- HV-8000B is closed and de-energized.

- A total loss of 1 25V DC bus AD1 results in a Reactor trip.

- SI actuates due to inadequate throttling of AFW flow post trip.

- 15 minutes later, PRZR level is now rapidly rising.

Which ONE of the following would be available to mitigate RCS pressure rise?

A.

Both PRZR sprays and one PRZR PORV.

B Only PRZR Code Safeties.

C. Only one PRZR PORV.

D. Both PRZR sprays.

Page 10 of 85

1-IL-i 6 NRC SRO Exam 2011 -3G1

15. 01 lEA!.03 002/1/1/LB LOCA-RCP TRTPI4.014.0 MEMJMOD BANKJRO/SRO/NRC/GCW Based on the following events:

- Safety Injection has been manually actuated.

- No CCPs are currently running or available.

- SIP A is running, SIP B is tripped.

- RCS pressure has lowered to 1350 psig.

- CETCs indicate 560° F and are slowly rising.

- 19010-C, Loss of Reactor or Secondary Coolant has just been entered.

Which of the following is the CORRECT action to take at this time and why?

A. RCPs should remain running, one SIP running is NOT adequate.

B. RCPs should remain running, at least one CCP running is required.

C RCPs should be tripped, to prevent excessive depletion of RCS inventory.

D. RCPs should be tripped, the pump heat may lead to uncovering the core earlier.

16. 01 1K4.03 004/2I2IPZR LEVEL DENSITY C012.612.9 MEM/BANK CALLAWAY 07/RO/SRO/NRC/GCW Which ONE of the following Pressurizer Level instruments is COLD calibrated, and how does its indication differ from the other pressurizer level instruments at normal operating temperature and pressure?

A LT-462; indicates lower.

B. LT-462; indicates higher.

C. LT-461; indicates lower.

D. LT-461; indicates higher.

Page 11 of 85

HL-16 NRC SRO Exam 2011-301

17. 012A4.07 OO1/2/1/RPS-MG SET BRKRS/3.9/3.9 C/AJLOIT BANKJRO/SROINRC/GCW Given the following conditions at 100% power:

- All systems in normal alignment except for the following.

- Reactor Trip Breaker testing is in progress.

- RTB A QMCB light indication is green.

- RTB Bypass Breaker A QMCB light indication is red.

During testing, the following QMCB annunciator illuminates.

- ROD DRIVE M-G SET TROUBLE

- Motor Generator (MG) Set # 1 Output Breaker has tripped open.

Which ONE of the following is CORRECT regarding the MG Set Output Breakers and the Reactor Trip Breakers?

A. Reactor trip occurs.

Reactor Trip Breakers are in series, power is lost to the Rod Control Power Cabinets.

B. Reactor trip occurs.

MG Set Output breakers are in series, power is lost to the Rod Control Power Cabinets.

C. Reactor trip does NOT occur.

Reactor Trip Breakers are in parallel, power is maintained to the Rod Control Power Cabinets.

D Reactor trip does NOT occur.

MG Set Output breakers are in parallel, power is maintained to Rod Control Power Cabinets.

Page 12 of 85

HL-16 NRC SRO Exam 2011-301

18. 01 3K5.01 002/2/1 IESFAS-SAFETY TRAIN/2.8/3.2 MEM/LORQ BANK/RO/SRO/NRC/GCW is divided into 2 distinct input, logic, and output bay.b_____

with 3 or 4 of process control equipment used for the signal processing of unit parameters measured by the field instruments.

Which ONE of the following CORRECTLY describes the above mentioned instrumentation?

A.

a-Reactor Protection System (RPS) b-Trains c-Channels B a-Solid State Protection System (SSPS) b-Trains c-Channels C. a-Reactor Protection System (RPS) b-Channels c-Trains D. a-Solid State Protection System (SSPS) b-Channels c-Trains Page 13 of 85

HL-16 NRC SRO Exam 2011-301

19. 014A102 00212/2/DRPI INDICATION/3.2/3.6 CIA/LORQ BANK/RO/SRO/NRC/GCW While performing 12003-C, Reactor Startup (Mode 3 to Mode 2), the following notes states:

ALB1ODO4 ROD BANK LO-LO LIMIT and ALB1OCO4 ROD BANK LO LIMIT should normally reset when Control Bank C exceeds 48 +/-2 steps and 58 +/-2 respectively.

The OATC withdraws Control Bank C rods and observes the following:

Prior to the rod withdrawal the following conditions existed:

DRPI: 42 Steps Group 1 Step Counter: 42 Steps Group 2 Step Counter: 41 Steps After the rod withdrawal the following conditions exist:

DRPI: 42 Steps Group 1 Step Counter: 56 Steps Group 2 Step Counter: 55 Steps With no other operator action, immediately after the rod withdrawal, the Rod Bank LO-LO-Limit annunciator (1) and the Rod Dev annunciator..(2).

A (1) resets (2) illuminated B. (1) remains illuminated (2) illuminated C. (1) remains illuminated (2) does not alarm D. (1) resets (2) does not alarm Page 14 of 85

HL-16 NRC SRO Exam 2011-301

20. 01 7K6.0 1 00 1/2/2/IN-CORE DETECTORS/2.7/3.0 C/A/BANK/RO/SRO/NRC/GCW Given the following:

- The crew is implementing 19001-C, Reactor Trip Response.

- Natural circulation verification is in progress.

- 2 Core Exit Thermocouples are failed due to open circuits.

The input from these CETCs to the Subcooling Monitor are (1) and the calculated subcooling margin will be (2)

A. (1)failed low (2) higher Bk (1) failed low (2) unaffected C. (1)failed high (2) lower D. (1) failed high (2) unaffected Page 15 of 85

HL-16 NRC SRO Exam 2011-301

21. 022A4.05 002/2/1 /CC-TEMP/PRESSIHUMID/3.8/3.8 MEM/BANK SUMMER2009/RO/SRO/NRC/GCW Unit 2 is in Mode 1 with the following Containment Parameters:

Temperature Pressure T2501 =115°F Pl-0935=1.5psig T2502 = 123°F P1-0937 = 1.7 psig T2503 = 117°F P1-0934 = 1.6 psig UT2501(AVG) = 118.3°F P1-0936 = 1.4 psig Based on Tech Spec limiting conditions for operation, which ONE of the following is correct?

A.

(1) Temperature has exceeded limits.

(2) Pressure has exceeded limits.

B.

(1) Temperature is within limits.

(2) Pressure has exceeded limits.

C. (1) Temperature has exceeded limits.

(2) Pressure is within limits.

Dv (1) Temperature is within limits.

(2) Pressure is within limits.

Page 16 of 85

HL-16 NRC SRO Exam 2011-301

22. 022AA2.03 004/1/1/LOSS RX MJUI3.l/3.6 C/AJLORQ BANKRO/SRO/NRC/GCW With the unit at 100% power and all control systems in automatic, the OATC observes the following:

- ALBO7BO6 Charging Line Hi/Lo Flow is alarming

- ALBO7AO5 Regen HX LTDN Hi Temp is alarming

- FI-132 letdown flow is oscillating between 0 & 100 gpm

- RCP seal injection flowmeters are off scale high Using the above indications which ONE of the components failures below has occurred.

A. Controlling PRZR level channel Ll-459 has failed high.

B. Charging Flow control valve FV-121 has failed closed.

C Seal Flow Control control valve HV-182 has failed closed.

D. Letdown Pressure Control Valve PV-1 31 has failed closed.

Page 17 of 85

HL-16 NRC SRO Exam 2011-301

23. 022K3.02 002/2/1 /CCS-CNMT INST/3.0/3.3 MEM/MOD BANK SANOFRE/RO/SRO/NRC/GCW Given the following conditions:

- A feedline break has occurred inside Containment.

- SI actuation has occurred.

- Only three Containment Coolers are available and running in low speed.

- Containment Pressure peaked at 7.8 psig.

- Containment Pressure is currently 2.6 psig.

The crew is currently evaluating ECCS termination criteria with the following values:

- Subcooling is 32 °F.

- Pressurizer level is 29% and slowly rising.

- All intact Steam Generator NR levels are 27% and rising.

- Both MDAFW Pumps running with flow throttled to 400 gpm total.

Which ONE of the following is true concerning SI termination criteria?

A SI termination is met.

B. SI termination is not met due to subcooling.

C. SI termination is not met due to Pressurizer level.

D. SI termination is not met due to Steam Generator levels.

Page 18 of 85

HL-16 NRC SRO Exam 2011-301

24. 025AK 1.01 002/1/1fLOSS OF RHRJ3.9/4.3 C/A/BANK/ROISROJNRCIGCW The following conditions exist on Unit 1:

- The plant is 37 days and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months into a refueling outage.

- The unit is in Mode 5 at mid-loop conditions.

- RHR 1 A heat exchanger inlet temperature is stable at 100 °F.

- Core offload has NOT yet commenced.

- Subsequently the lA RHR Pump trips.

- 18019-C, Loss of Residual Heat Removal is entered.

Which ONE of the following is correct if the loss of RHR continues without mitigation?

REFERENCE PROVIDED A The time to boiling is less than 50 minutes. The FIRST action to take is evacuate Containment and establish containment closure, then align SI pumps for Hot Leg Injection.

B. The time to boiling is more than 60 minutes. The FIRST action to take is evacuate Containment and establish containment closure, then align SI pumps for Hot Leg Injection.

C. The time to boiling is less than 50 minutes. The FIRST action to take is to align SI pumps for Hot Leg Injection, then evacuate Containment and establish containment closure.

D. The time to boiling is more than 60 minutes. The FIRST action to take is to align SI pumps for Hot Leg Injection, then evacuate Containment and establish containment closure.

Page 19 of 85

HL-1 6 NRC SRO Exam 2011-301

25. 026K3.02 002/2/! ICSS-RECIRCI4.2/4.3 C/A/NEW/RO/SRO/NRC/GCW Containment Spray has actuated due to a LOCA.

Containment Spray pump A shaft shears upon startup.

Containment Pressure is 15 psig.

Both Containment Emergency Sump Levels read 10 inches.

RWST level currently reading 5%.

19111-C, Loss of Emergency Coolant Recirculation has been entered from 19013-C, Cold Leg Recirculation.

Which ONE of the following is CORRECT regarding:

1) the Containment Spray system status, and

2) the actions the crew should take regarding the Containment Spray pump?

A 1) Only one Containment Spray ring is receiving flow.

2) Stop Containment Spray pump B.

B.

1) Both Containment Spray rings are receiving flow.

2) Leave Containment Spray pump B running.

C.

1) Only one Containment Spray ring is receiving flow.

2) Leave Containment Spray pump B running.

D.

1) Both Containment Spray rings are receiving flow.

2) Stop Containment Spray pump B.

Page 20 of 85

HL-16 NRC SRO Exam 2011-301

26. 027AK2.03 002/1/IIPZR PRESS CNTRL/2.6/2.8 C/AJLORQ BANKIRO/SROINRC/GCW Given the following:

- The unit is at 100% power.

- All control systems are in their normal alignments.

- The Pressurizer Master Pressure Controller output demand fails LOW.

Assuming no action has been taken by the crew, which ONE of the following describes the effect on the Pressurizer heaters, and the resulting effect on the plant?

A PZR heaters energize.

PZR pressure rise is controlled by PZR PORV operation.

B.

PZR heaters energize.

PZR pressure rise is controlled by PZR spray valve operation.

C. PZR heaters de-energize.

ONLY the PZR spray valves open.

D. PZR heaters de-energize.

PZR spray valves and one PZR PORV open.

Page 21 of 85

HL-16 NRC SRO Exam 2011-301

27. 028AK 1.01 002/ 1/2IPZR LEVEL REF LEG/2.8/3. I C/A/LORQ BANK/RO/SRO/HL-16 NRC/GCW The Unit is operating at 100% with all control systems in automatic.

Pressurizer level control is selected to the 459/460 position when the following occurs:

- A small Pressurizer level reference leg leak occurs on the controlling channel.

Which ONE of the following would be CORRECT regarding the response of the Pressurizer level control system?

A. LT-460 level would read lower than actual, charging flow would increase.

B. LT-459 level would read lower than actual, charging flow would increase.

C. LT-460 level would read higher than actual, charging flow would decrease.

D LT-459 level would read higher than actual, charging flow would decrease.

28. 029EK3.02 002/1 / 1/ATWT/3.1/3.1 MEMJBANK/RO/SRO/NRC/GCW Given the following:

- ATWT in progress.

- 19211-C, Response to Nuclear Power Generation / ATWT in effect.

- SI has NOT actuated at this time.

- Pressurizer level is 15%.

- The NCP is running.

Step 4.b states verify a charging pump is running.

Which ONE of the following is CORRECT regarding the performance of this step?

At The NCP can be left running, purpose is to provide emergency boration flow.

B.

A CCP is required to be started, purpose is to provide emergency boration flow.

C. The NCP can be left running, purpose is to provide for RCS inventory control.

D. A CCP is required to be started, purpose is to provide for RCS inventory control.

Page 22 of 85

HL-16 NRC SRO Exam 2011-301

29. 029K 1.02 002/2/2/CNMT PURGE-RAD MONIT/3.3/3.6 C/A/NEW/RO/SROINRC/GCW A containment pressure relief is in progress at full power.

- The following alarm illuminates:

ALBO5 window C05 for HIGH RADIATION ALARM An investigation has revealed:

- RE-002, CNMT Low Range Area monitor indicates normal levels.

- RE-003, CNMT Low Range Area monitor indicates normal levels.

- RE-2562A1C CNMT Air Process monitor indicates normal levels.

- RE-2565A1B, CNMT Vent Rad monitor indicates normal levels.

- RE-2565C CNMT Vent Rad monitor has failed High.

The Containment Pressure relief path has A. remained in service and can remain in service.

B. remained in service but must be manually isolated per ARP.

C. automatically isolated due to the receipt of a CIA signal.

D automatically isolated due to the receipt of a CVI signal.

Page 23 of 85

HL-16 NRC SRO Exam 2011-301

30. 033AK3.01 002/1/2/LOSS OF IRJ3.2/3.6 C/A/LOIT BANK/RO/SRO/NRC/GCW Unit 1 is at 8% power when the following events occur:

- Annunciator ALB34, C02 INVERTERS 1BD1I2 1BD1I12 TROUBLE illuminates.

- Annunciator ALB34, 001 1 20V AC PANELS 1 BY1 B 1 BY2B TROUBLE illuminates.

- All channel II trip status lights illuminate.

- Reactor power remains stable.

Which ONE of the following is the correct action(s) for the crew to take?

A. Control SG NR levels in MANUAL from 60

- 70% NR.

B. Reduce reactor power to < P-6 within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

C Manually trip the reactor and go to 19000-C, E-O Reactor Trip or Safety Injection.

D. Suspend all operations involving positive reactivity changes, maintain power stable.

31. 033G2.4.49 002/2/2/SFPC ACTIONS/4.6/4.4 MEM!NEW/RO/SRO/NRC/GCW A refueling outage is in progress with movement of irradiated fuel assemblies occuring in the Spent Fuel Pools.

Which ONE of the following conditions would ALLOW movement of irradiated assemblies in the Spent Fuel Pool to continue?

A. Spent Fuel Pool boron concentration is 1969 ppm.

B. Spent Fuel Pool level is 216 feet, 4 inches on local reading.

C Both SR NIS audio count rate channels have been lost.

D. Both FHB Post Accident Ventilation systems have been declared INOPERABLE.

Page 24 of 85

HL-16 NRC SRO Exam 2011-301

32. 035A4.06 002/2/2/SO-ISOL SGTL/4.514.6 C/A/LOIT BANK/RO/SRO/NRC/GCW Given the following:

- A Steam Generator Tube Rupture has occurred on Steam Generator # 4.

- The crew is performing actions of 19030-C, Steam Generator Tube Rupture.

- Steam Generator # 4 NR level is 7%.

- Steam Generators # 1, 2, and 3 are reading 0% NR.

- AFW flow to each SG is 200 gpm.

The crew should isolate AFW flow to SG # 4.(1).. and the reason is to A. (1)immediately (2) prevent overfilling of the Steam Generator.

B.

(1) immediately (2) to minimize offsite dose due to lifting of the ARV.

C. (1) when SG #4 NR level> 10%

(2) to ensure a secondary side Heat Sink.

D (1) when SG #4 NR level> 10%

(2) to promote thermal stratification for SG pressure control.

Page 25 of 85

HL-16 NRC SRO Exam 2011-301

33. 038EK3.0 1 002/1/1 ISGTR/4.1/4.3 FUNH/BANK HARRIS2007/RO/SRO/HL-1 6/EMT/GCW Unit 2 was at 100% power

- A SGTR has occurred and 19030-C, E-3 Steam Generator Tube Rupture actions are in progress.

- The RCS cooldown to target temperature has just been completed.

Which ONE of the following describes the reason(s) for reducing RCS pressure to match ruptured SG pressure at this point?

A To restore RCS inventory and reduce break flow prior to SI termination.

B. To prevent damage to secondary side steam piping due to overfill.

C. To minimize the probability of a Pressurized Thermal Shock event when RCS cooldown is recommenced.

D. To prevent any release of radioactivity through the SG Atmospheric Dump valves.

Page 26 of 85

HL-1 6 NRC SRO Exam 2011 -301

34. 039G2239 002/2/I/MAIN/REHEAT STM -TSI3.9/4.5 MEM/NEWIRO/SRO/NRC/GCW Given the following:

- The unit is at full power.

- A loss of external load without a direct reactor trip occurs.

- RCS pressure is currently 2800 psig.

In accordance with Technical Specifications and Bases, which one of the following are,

1) Main Steam components that should have prevented exceeding a Safety Limit, and

2) the maximum time limit required by Tech Specs for restoration of compliance.

Main Steam Component Restore Compliance Within A. Atmospheric Relief Valves one hour B. Atmospheric Relief Valves 5 minutes C Main Steam Safety Valves one hour D. Main Steam Safety Valves 5 minutes Page 27 of 85

HL-16 NRC SRO Exam 2011-301

35. 054G2.4.49 001/1/1/LOSS OF MFW/4.6/4.4 C/A/NEW/RO/SRO/NRC/GCW Given the following:

- The Plant is at 67% when the following annunciators/indications occur.

-ALB15 D03, MFPTA TRIPPED

- ALB15 B05, MFPT DISCH HDR LO PRESS

- ALB13 STM GEN FLOW MISMATCH on all loops.

- MFPT B is at 5900 rpms with discharge pressure at 650 psig.

- S/G levels are 46% NR and rapidly lowering.

Which ONE of the following is the !Jrt CORRECT action(s) for the crew to perform per AOP 18016-C, Condensate and Feed Water Malfunction?

A. Trip the Reactor and go to E-0 due to S/G levels.

B. Trip the Reactor and go to E-0 due to power level.

C Trip the Reactor and go to E-0 due to MFP indications.

D. Reduce Turbine load to lower MFP speed to 5300 rpm.

36. 055EA 1.01 003/1 / 1/STATION B/O/3.7/3.9 MEMJBANK SUMMER2009/RO/SRO/HL-I 6/EMT/GCW Which ONE of the following describes a condition that will require the crew to transition out of 19100-C,Loss Of All AC Power prior to restoring power to at least one AC ESF Bus?

A CETCs indicate greater than 1200°F and rising.

B. The Tcolds for all RCS loops lower to less than 280°F.

C. Both Intermediate and Source Range startup rates are positive.

D. ALL S/Gs levels drop below 40% WR with no AFW flow available.

Page 28 of 85

HL-16 NRC SRO Exam 2011-301

37. 055K3.01 002/2/2/COND AIR REMOVAL/2.5/2.7 MEM/NEWIRO/SRO/NRC/GCW Given the following:

- Reactor power is 100%.

- The Instrument Air supply is lost to the Condenser Vacuum Breakers.

Which ONE of the following is CORRECT?

A Condenser pressure is unaffected, Vacuum breakers can be opened from the Control Room.

B. Condenser pressure is unaffected, Vacuum breakers cannot be opened from the Control Room.

C. Condenser pressure rises and Main Turbine Mw output remains constant.

D. Condenser pressure rises and Main Turbine Mw output lowers.

38. 056AK3.0 1 003/1 / 1ILOSP/3.5/3.9 MEMJMOD BANK/RO/SROINRC/GCW Which ONE of the following is correct regarding the response and the reason for the Containment Cooling fans loading sequence following a simultaneous UV on both trains of SSPS?

A. Eight Containment Cooling fans start in low speed at 30.5 seconds.

Reason: High moisture and density air could damage motor windings.

B. Eight Containment Cooling fans start in high speed at 30.5 seconds.

Reason: High moisture and density air could damage motor windings.

C. Four Containment Cooling fans start in low speed at 30.5 seconds, then four more start in low speed at 50.5 seconds.

Reason: To prevent overloading the DG during loading.

D Four Containment Cooling fans start in high speed at 30.5 seconds, then four more start in high speed at 50.5 seconds.

Reason: To prevent overloading the DG during loading.

Page 29 of 85

HL-16 NRC SRO Exam 2011-301

39. 057AA2.02 001/1/1/LOSS OF VITAL AC/3.713.8 MEM/NEW/RO/SRO/NRC/GCW The following indications occur with the unit at full power:

- Accumulator # 1 level and pressure indications both fail due to a loss of power.

Which ONE of the following would be correct regarding:

1) power supply to accumulator level and pressure indicators, and

2) the direction the instruments would fail?

power supply failure direction A.

125 VDC fails low B.

125 VDC fails high C

120 VAC fails low D.

120 VAC fails high Page 30 of 85

HL-16 NRC SRO Exam 2011-301

40. 058G2.4.49 002/1/1/LOSS OF DC/4.6/4.4 MEM/NEW/RO/SRO/NRC/GCW Unit 1 core offload is in progress.

- A fault occurs on BD1, 125 VDC Vital Bus.

- The required DC sources for the present mode are NOT met.

Considering the following Technical Specification actions:

1) Suspend CORE ALTERATIONS.

2) Suspend movement of irradiated fuel assemblies.

3) Initiate actions to suspend operations involving positive reactivity additions.

Which ONE of the following contains ALL actions that are required to be IMMEDIATELY performed for the present Mode and DC source status?

A.

1 only B. #1 and #2only C. #land#3only D # 1, # 2, and # 3 Page 31 of 85

HL-16 NRC SRO Exam 2011-301

41. 059K4.18 002/2/1/MFW-FW REDUCTION/2.8/3.O CIAJMOD BANK/RO/SRO/NRC/GCW Reactor trip has occurred from 100% power with the following conditions:

- Reactor Trip Breaker B has remained closed.

- Loop 1 Tave = 563°F

- Loop 2 Tave = 563°F

- Loop 3 Tave = 566°F

- Loop 4 Tave = 564°F

- All SG levels are 35% NR.

The crew is performing 19001-C, Reactor Trip Response step for Check FW Status.

With no operator action, which ONE of the following is CORRECT regarding the current status of FWI?

A. MFRVs-OPEN, BFRVs-OPEN B. MFRVs-SHUT, BFRVs-OPEN C MFRVs

- OPEN, BFRVs

- SHUT D. MFRVs-SHUT, BFRVs-SHUT Page 32 of 85

HL-1 6 NRC SRO Exam 2011-301

42. 059K4. 19003/2/ 1/MFW-FWJJ3.2/3.4 MEM/NEW/RO/SRO/NRC/GCW A plant feedwater transient at 100% power has resulted in ALB13-E04 annunciator illuminating:

FW I SI or P-14 SG HI-HI LVL Which ONE of the following is correct regarding:

1) Impact on MEW system, and

2) actions necessary to reset FWI, after SG levels are returned to normal?

A.

1) only closes all FWI valves.

2) cycle reactor trip breakers, then reset FWI.

B.

1) only closes all FWI valves.

2) reset EWI. Reactor trip breakers are NOT required to be cycled.

C 1) closes all FWI valves and trips both MFPTs.

2) cycle reactor trip breakers, then reset FWI.

D.

1) closes all FWI valves and trips both MFPTs.

2) reset FWI. Reactor trip breakers are NOT required to be cycled.

Page 33 of 85

HL-16 NRC SRO Exam 2011-301

43. 060AK2.O 1 002/1/2/GASEOUS RELEASE/2.6/2.9 MEMINEW/RO/SRO/NRC/GCW During core offload, a dropped assembly results in a gas bubble rising from the cavity into Containment atmosphere.

- RE-2562C, Containment Air

- Radiogas goes into HIGH alarm.

- RE-002 & RE-003, Containment

- Low Range monitor readings are not in alarm.

1) How can the operators check the High and Alert setpoints for the Containment Low Range monitors, and

2) what indication would inform the operators if RE-002 and RE-003 have failed?

A 1) can be checked on the SRDC in Control Room

2) the amber Equipment Trouble light would be illuminated.

B.

1) can be checked on the SRDC in Control Room

2) the blue Bypass light would be illuminated.

C.

1) can only be checked locally on the DPM

2) the amber Equipment Trouble light would be illuminated.

D.

1) can only be checked locally on the DPM

2) the blue Bypass light would be illuminated.

Page 34 of 85

HL-16 NRC SRO Exam 2011-301

44. 061 K2.0 1 002/2/1 /AFW/3.2/3.3 MEM/LOIT BANK/RO/SRO/NRC/GCW The UO notices the following indications for AFW valves:

- HV-5106, TDAFW Steam Admission Valve, red and green lights are out.

- FV-5132 & 5134, MDAFW SG 2 & 3 Discharge Throttle Valves, red, green, and white lights are out.

Which ONE of the following is the cause of these conditions?

A. Loss of C train 1 E 480 VAC and B train 1 E 125 VDC power.

B. Loss of C train 1 E 125 VDC and B train 1 E 125 VDC power.

C. Loss of C train 1 E 480 VAC and B train 1 E 480 VAC power.

D Loss of C train 1 E 125 VDC and B train 1 E 480 VAC power.

Page 35 of 85

HL-16 NRC SRO Exam 2O113O1 45 061 K6.02 002/2/1 /AFW PUMPS-LOSS/2.6/2.7 C/AJNEW/RO/SRO/NRC/TLH While the TDAFW pump was tagged out for governor replacement, a spurious Reactor Trip from 100% occurred.

The Unit Operator monitoring AFW flow reports the following:

- Steam Generator #1 = 0 gpm.

- Steam Generator #2 = 300 gpm.

- Steam Generator #3 = 300 gpm.

- Steam Generator #4 = 0 gpm.

Which ONE of the following is CORRECT concerning the MDAFW pumps status and their associated mini-flow valve position?

MDAFW Pump Status Mini-flow Valve Status A.

A RUNNING OPEN B STOPPED CLOSED B.

A STOPPED CLOSED B RUNNING OPEN C.

A RUNNING CLOSED B STOPPED OPEN D

A STOPPED OPEN B RUNNING CLOSED Page 36 of 85

HL-16 NRC SRO Exam 2011-301

46. 062K4.02 002/2/ 1/AC-BREAKER TRIPS/2.5/2.7/MOD BANKJRO/SROINRC/GCW The Maintenance! Normal switch located on the QEAB for a 4160V AC bus has been placed in the Maintenance position to support bus inspection.

When the switch is returned to the Normal position, this switch will...

A. enable the instantaneous overcurrent trips on the bus load breakers.

B. enable the instantaneous overcurrent trips on the bus supply breakers.

C. enable the time delay on the overcurrent trips on the bus load breakers.

D enable the time delay on the overcurrent trips on the bus supply breakers.

47. 063A2.0 1 002/2/1/DC GROUNDS/2.5/3.2 C/A/BANK/RO/SRO/NRC/GCW While at 100% power, the following annunciator illuminates:

- ALB34-B01, 1 25V DC SWGR BD1 TROUBLE

- The Control Building Operator (CBO) has been dispatched to investigate.

Which ONE of the following is CORRECT regarding indications! actions to take if a GROUND has occurred?

A. There are no local bus ground detection targets associated with BD1, the CBO would have no indication of a ground, maintenance would determine the cause.

B.

A bus ground detection target would be dropped on BD1, de-energize panels BD1 M, BD1 1, and BD1 2 one at a time to locate the panel with the ground.

C. There are no bus ground detection targets associated with BD1, de-energize selected loads on BD1M, BD11, and BD12 one at a time until the alarm clears.

D A bus ground detection target would be dropped on BD1, de-energize selected loads on BD1 M, BD1 1, and BD12 one at a time to locate the source of the ground.

Page 37 of 85

HL-16 NRC SRO Exam 2011-301

48. 064G2.2. 12 002/211/DG SURVEILLANCES/3.714. 1 CIA/BANK FARLEY 20101R0/SRO/NRC/GCW During the performance of the surveillance test, 14980A-2, Diesel Generator 2A Operability Test:

The DG will be logged as INOPERABLE while performing a _(1 )__.

The DG will be OPERABLE when the A (1) slow start (2) EXCITER ENABLE pushbutton is depressed.

B. (1)slow start (2) EXCITER PERMISSIVE switch is placed in NORMAL.

C. (1)fast start (2) EXCITER ENABLE pushbutton is depressed.

D. (1)faststart (2) EXCITER PERMISSIVE switch is placed in NORMAL.

Page 38 of 85

HL-1 6 NRC SRO Exam 2011 -301

49. 064K3.03 002/2/1 /DG-MANUAL LOADS/3.6/3.9 C/A/NEWIRO/SROJNRC/TLH Unit 1 has experienced a loss of power to 1 AAO2 while at 100% RTP.

D/G-lA automatically started but immediately tripped on Overspeed when the CCW pumps started.

While the investigation and repairs are in progress on the D/G-lA, the Control Room crew was able to re-energize 1 AAO2 from the SAT.

When 1AAO2 was re-energized from the SAT, the Sequencer (1)

. The reason the Sequencer Reset must be performed in this case is to (2)

A.

(1) will start its UV loads.

(2) remove Block Auto/Manual signal.

B (1) will NOT start its UV loads.

(2) remove Block Auto/Manual signal.

C. (1) will start its UV loads.

(2) reset the Loss of Offsite Power (LOP) Monitor.

D. (1) will NOT start its UV loads.

(2) reset the Loss of Offsite Power (LOP) Monitor.

Page 39 of 85

HL-16 NRC SRO Exarn2Ol1-301

50. 067AA1.07 002/1/2/FIRE PANEL RESET/2.9/3.0 MEMINEW/RO/SRO/NRC/GCW The Fire Alarm Computer (FAC) has an alarm displayed on the alarm overview page.

(1) The computer for primary Fire Alarm response is located in 1),

and (2) an unacknowledged alarm is a 2) icon.

Av (1) the Main Control Room (2) FLASHING B.

(1) C & T (EBI workstation)

(2) FLASHING C. (1) the Main Control Room (2) SOLID D. (1) C & T (EBI workstation)

(2) SOLID Page 40 of 85

HL-16 NRC SRO Exam 2011-301

51. 068A3.02 002/2/2/LIQUID RW-ISOLATION/3.6/3.6 C/AILOIT BANK/RO/SRO/NRC/GCW Waste Monitor Tank 009 release is in progress on Unit 1 when power to the DPM for RE-Ol 8 (Liquid Waste Monitor) is lost and subsequently restored.

Liquid Radwaste Isolation Valve RV-018 __(1L_ and the release _(2)__.

A.

(1) closes (2) can be restarted using the original release permit.

B (1) closes (2) cannot be restarted until a new release permit is obtained.

C. (1) remains open (2) may continue using the original release permit.

D. (1) remains open (2) may continue provided additional grab samples are obtained.

52. 068AK3.08 002/1/2/CONTROL RM EVACUATIO/3.4/3.9 MEM/NEW/RO/SRO/NRC/GCW The control room has been evacuated due to a fire which posed a personnel hazard and the operators did not trip the MFPT5.

Later, the Shift Supervisor has opted to locally trip the MFPT5. Regarding the Condensate pumps, which of the following is correct regarding the required final Condensate pump status and the reason?

Condensate Pump final status Reason for pump status A.

all pumps stopped prevents overfilling the steam generators.

B. all pumps stopped prevents an excessive cooldown of the RCS.

C. one pump running maintains hotwell reject capability to the CSTs.

D one pump running cools equipment needed to maintain vacuum.

Page 41 of 85

HL-16 NRC SRO Exam 2011-301

53. 073K 1.01 002/2/IIPRM SYSTEMS/3.6/3.9 MEMJLOIT BANK/RO/SRO/NRC/GCW HIGH radiation has been detected in the Steam Generator Blowdown System (SGBD).

Regarding the following rad monitors:

RE-0019, SG Sample Liquid RE-0021, SG Blowdown Liquid Which ONE of the following would (1) initiate a SGBD isolation on High Radiation and (2) which valve listed below would automatically close to isolate the system on High Radiation?

A. (1)RE-0019 (2) FV-1 150, Blowdown Inlet Isolation Valve B. (1)RE-0019 (2) HV-7600, Blowdown Recycle Isolation Valve C (1) RE-0021 (2) FV-1 150, Blowdown Inlet Isolation Valve D. (1) RE-0021 (2) HV-7600, Blowdown Recycle Isolation Valve Page 42 of 85

HL-1 6 NRC SRO Exam 2011-301

54. 073K5.02 002/2/1/PRM-SOURCE DISTANCE/2.5/3. 1 CIAJBANK SURRY 09/RO/SRO/NRC/GCW Initial conditions:

- Radiography is in progress on a section of main steam piping.

- The radiographers want to verify the correct position of the camera by using a main steam line radiation monitor located on the same elevation and close to the area where the radiography needs to take place.

- To obtain a baseline reading, the camera source was placed 3.21 feet away from the radiation monitor detector.

- The radiation monitor reads 5.92 RIhr.

Current conditions:

- The camera has been moved into position to image the piping section.

- Engineering calculations show that the camera should be placed 17.46 feet away from the radiation monitor detector.

The distances listed above include the difference in height from the camera to the radiation monitor detector. Consider the radiography camera as a radiation point source. Carry all calculations to three (3) decimal places.

Based on current conditions, which ONE of the following correctly identifies the expected reading on the radiation monitor, if the camera was positioned correctly?

A. 0.037 A/hr B 0.200 R/hr C. 1.088 A/hr D. 2.538 R/hr Page 43 of 85

HL-16 NRC SRO Exam 2011-301

55. 076A3.02 OOI/2/1INSCW HEAT LOADSII7/3.7 MEM/MOD BANK/RO/SRO/NRC/GCW Given the following:

- A Reactor Trip and Safety Injection (SI) occur.

Which ONE of the following is CORRECT regarding NSCW cooling water status to the Containment Cooling system?

A. Auxiliary Coolers - open Containment Coolers

- open B. Auxiliary Coolers

- closed Containment Coolers

- closed C Auxiliary Coolers

- closed Containment Coolers

- open D. Auxiliary Coolers - open Containment Coolers

- closed Page 44 of 85

HL-16 NRC SRO Exam 2011-301

56. 076AA2.03 002/1 /2IHTGH RCS ACTIVITY/2.5/3.0 MEMJLOIT BANK/RO/SROINRC/GCW Initial conditions:

- Unit at full power with all systems in automatic.

Current conditions:

- CVCS letdown radiation monitor RE-48000 is off-scale high.

- Chemistry has validated the alarm with a sample.

Which ONE of the following choices correctly describes the cause for this indication and the appropriate actions to take per the ARP?

A. CVCS letdown mixed bed demineralizer over temperature.

Bypass the CVCS mixed bed demineralizer and divert letdown to the RHT.

B Fuel rod cladding leak.

Dispatch HP personnel to measure dose rates in the penetration room area and determine RCS Activity levels.

C. CVCS letdown mixed bed demineralizer over temperature.

Isolate CVCS normal letdown and then place excess letdown in service.

D. Fuel rod cladding leak.

Maximize CVCS and excess letdown flows and limit any future power changes until RE-48000 reading lowers to normal background.

Page 45 of 85

HL46 LIRC SRO Exam 2011-301

57. 076K 1.05002/2/1 INSCW-DG/3.8/4.0 C/AJNEW[RO/SROINRC/GCW Given the following:

- DG 1A has been fully loaded per 14980A-1 Diesel Generator 1A Operability Test.

- During the surveillance run, the following alarms illuminated:

NSCW TRAIN A DG CLR LO FLOW NSCW TRAIN A LO HDR PRESS NSCW PMP HOUSE TRN A DRN SUMP HI LVL Which ONE of the following has occurred and what will be the effect on the 1A DG if no operator actions are taken?

A. NSCW Pump trip.

DG will trip on Hi Jacket Water Temperature.

B NSCW leak.

DG will trip on Hi Jacket Water Temperature.

C. NSCW Pump trip.

DG will remain running.

D. NSCW leak.

DG will remain running.

Page 46 of 85

HL-16 NRC SRO Exam 2011-301

58. 077AA2.07 002/1 / 1/GRID DISTURBANCES/3.6/4.0 C/A/MOD BANK ROBINSON/RO/SRO/NRC/GCW Given the following:

- Plant is in Mode 1 at 100% RTP.

- The Load Dispatcher reports several major generating stations have tripped and grid voltage is degrading.

- For the last 30 seconds 1 E 41 60V bus voltage has been reading 3740 volts.

Following the above conditions, the operator would expect the emergency busses to be energized from A. offsite power, the Diesel Generators will not start until bus voltage reaches the Loss of Voltage setpoint.

B. offsite power, the Diesel Generators will not start until bus voltage reaches the Degraded Voltage setpoint.

C. the Diesel Generators, due to reaching the Loss of Voltage setpoint.

D the Diesel Generators, due to reaching the Degraded Voltage setpoint.

59. 103K 1.08002/2/1 /CNMT-SI-RESET/3.6/3.8 C/AILOIT BANK/RO/SRO/NRC/GCW Unit 1 has the following conditions:

- A LOCA has occurred and SI actuation.

- Containment Pressure is 5 psig and slowly lowering.

- SI has NOT been reset.

- Instrument Air to Containment has been isolated.

Which ONE of the following describes the minimum action(s) that must be performed to re-establish Instrument Air to Containment?

Ak Reset CIA only.

B. Reset SI, then reset CIA.

C. Containment pressure < 3.8 psig, then reset CIA.

D. Containment pressure <3.8 psig, then reset SI, then reset CIA.

Page 47 of 85

HL-16 NRC SRO Exam 2011-301

60. WEO4EK 1.1002/1/1 ILOCA ORC/3.5/3.9 C/AJBANK/RO/SRO/NRC/GCW Given the following:

- A LOCA outside Containment has occurred.

- The crew is performing 19112-C, LOCA Outside Containment.

Which ONE of the following is:

1) the FIRST system to be isolated from the RCS to attempt leak isolation, and

2) the parameter monitored to determine if the leak has been isolated?

1) First System Isolated

2) Parameter Monitored A.

RHR RVLIS level B

RHR RCS pressure C.

SI RVLIS level D.

SI RCS pressure

61. WEO5EAI.1 002/1/1/LOSS OF HEAT SINK/4. 1/4.0 C/A/LOIT BANK/RO/SROfNRC/GCW Given the following:

- A transition from E-0 19000-C to 19231-C Response To Loss of Secondary Heat Sink has occurred.

- All Steam Generator Wide Range levels are approximately 5%.

- RCS temperature is approximately 580°F and stable.

Per 19231-C, which ONE of the following describes the preferred method of initiating Auxilary Feed flow for these conditions?

A Feed a selected SG at 30

- 100 gpm until WR level > 9%.

B. Feed a selected SG with no flow restrictions until NR level is> 10%.

C. Feed all SGs at 30

- 100 gpm until WR level > 9%.

D. Feed all SGs with no flow restrictions until NR level is> 10%.

Page 48 of 85

HL-16 NRC SRO Exam 2011-301

62. WEO8EA 1.1 002/1 /2IPTS-RCS OVERCOOLING/3.8/3.8 C/A/LOIT BANK/RO/SRO/NRC/GCW Given the following:

- Unit 1 Reactor tripped and a natural circulation cooldown was required.

- The COPs system was placed in service in accordance with 19002-C, Natural Circulation Cooldown.

- Subsequently, a faulted Steam Generator resulted into entry into 19241-C, Pressurized Thermal Shock.

- All RCS temperatures have been stablized at approximately 290°F.

- RCS pressure is 650 psig.

- Loop 3 WR Cold Leg temperature fails to bottom of scale LOW.

Which ONE of the following describes the effect on the Unit?

A. PORV 455 will open until it is manually closed.

B. PORV 456 will open until it is manually closed.

C. PORV 455 will open until RCS pressure lowers below the minimum COPs setpoint.

D PORV 456 will open until RCS pressure lowers below the minimum COPs setpoint.

Page 49 of 85

HL-16 NRC SRO Exam 2011-301

63. WEO9G2.4.9 001/1 /2/NAT CIRC/3.8/4.2 C/AJLOIT BANKJRO/SRO/NRC/GCW Given the following conditions:

- A small break LOCA has occurred.

- The RCPs have been secured.

- 19012, Post LOCA Cooldown and Depressurization, is in progress.

- RCS pressure is 1490 psig.

- Wide Range T-Cold indications are 505°F and slowly lowering.

- Wide Range T-Hot indications are 515°F and slowly lowering.

- Core Exit Thermocouples (CETCs) are 581°F and stable.

- S/G pressures are 715 psig and stable.

According to 19012-C, which ONE of the following correctly states the status of Natural Circulation and the correct operator actions?

A. Natural Circulation is occurring. Continue attempts to start a RCP.

B. Natural Circulation is occurring. Maintain Steam Dump operation.

C. Natural Circulation is NOT occurring due to stable CETCs. Raise rate of Steam Dump Operation.

D Natural Circulation is NOT occurring due to inadequate subcooling. Raise rate of Steam Dump Operation.

Page 50 of 85

HL-16 NRC SRO Exam 2011-301

64. WE1 IEK2.2 002/1/1/LOSS OF COOLANT RECJI3.9/4.3 C/AILOIT BANK/RO/SRO/NRC/GCW The following Unit 1 conditions exist:

- A primary LOCA outside containment is in progress.

- Reactor Trip and SI have occurred.

- 19111 -C, Loss of Emergency Coolant Recirculation is in effect.

Which ONE of the following choices describes the correct actions to take in 19111-C under these conditions?

A. Start makeup to the RWST from the Boric Acid System.

Terminate ECCS flow with proper RVLIS indication ONLY.

B Start makeup to the RWST from the Spent Fuel Pool.

Establish one train of ECCS flow. The minimum required subcooling to terminate ECCS flow is 74°F.

C. Start makeup to the RWST from the Reactor Coolant Drain Tank.

Terminate ECCS flow with proper RVLIS indication and subcooling > 74°F.

D. Start makeup to the RWST from the Spent Fuel Pool.

Establish one train of ECCS flow. The minimum required subcooling to terminate ECCS flow is 24°F.

Page 51 of 85

HL-16 NRC SRO Exam 2011-301

65. WE12EK2.1 002/1/IIMSL RUPTUREI3.413.7 MEMJMOD BANK WOLF CRK/RO/SRO/NRC/GCW During the performance of 19121-C, Uncontrolled Depressurization Of All Steam Generators, the following conditions exist:

- RCS cooldown rate is determined to be 125 °F/HR.

- All SG NR levels are off-scale low.

Which ONE of the following describes how the crew is directed to control AFW flow and the basis for the action?

A Flow is reduced to 30 gpm to each SG.

WR Hot Leg temperatures are monitored to ensure secondary heat sink is maintained.

B. Total flow is reduced to 30 gpm to only one SG.

WR Cold Leg temperatures are monitored for conditions that may result in PTS.

C. Total flow is maintained > 570 gpm until ANY SG NR level is> 10%.

WR Hot Leg temperatures are monitored to ensure secondary heat sink is maintained.

D. Total flow is maintained > 570 gpm until ANY SG NR level is> 10%.

WR Cold Leg temperatures are monitored for conditions that may result in PTS.

Page 52 of 85

HL-16 NRC SRO Exam 2011-301

66. G2.1.1 002/3/N/AICOND OF OPS/3.8/4.2 MEMINEW/RO/SRO/NRC/GCW The On-Duty Shift Manager is required to notify the Operations Manager On-Call (OMOC) promptly of significant plant events.

Per NMP-OS-007-001, Conduct of Operations Standards and Expectations, which ONE of the following would (1) require the notification to the OMOC and (2) the minimum requirements of the individuals fulfilling the OMOC function?

A. (1) Apprentice Mechanic has sustained a First Aid injury.

(2) Must be knowledgeable at the SRO level.

B.

(1) Chemistry reports Secondary Chemistry Action Level 2.

(2) Must have a current or formerly held an SRO license.

C (1) A missed Tech Spec surveillance or test.

(2) Must be knowledgeable at the SRO level.

D. (1) A reportable event per 10CFR.

(2) Must have a current or formerly held an SRO license.

67. G2.1.23 00213/N/AJCOND OF OPS/SYSTEMS/4.3/4.4 MEMJLOIT BANKIRO/SRO/NRC/GCW UOP 12004-C, POWER OPERATION is in effect.

The transfer from Auxiliary Feed Water to Main Feed Water step is in progress.

The Bypass Feed Isolation Valve (BFIV) is opened while the Main Feed Isolation Valve (MFIV) is verified closed. The flowpath of main feedwater to the selected steam generator as the Bypass Feed Reg Valve (BFRV) is opened is:

A. established, because the MFIV leak-by is great enough to supply SG flow needs at low power through the BFRV.

B established, because the BFRV and BFIV are in series and not isolated by the MFIV.

C. NOT established, because the MFIV isolates flow to both the BFRV and the MFRV.

D. NOT established, because both the MFIV and BFIV must be opened before flow can be established.

Page 53 of 85

HL-16 NRC SRO Exam 2011-301

68. G2.2. 13 002/3/N/NC & T14. 1/4.3 MEM/BANK-HL-1 5RJRO/SRO/NRC/GCW

69. G22. 14002/3/N/A/EQUIP CONFIQ/3.9/4.3 MEM/NEW/RO/SRO/NRC/GCW A fail open air operated valve (AOV) with a handwheel must be Danger Tagged as a boundary point for a clearance.

To meet the minimum requirements of NMP-AD-003-002, Tagout Standards:

1) The handwheel is

2) The air supply valve is 1

A. Danger tagged B Danger tagged C. NOT required to be Danger tagged D. NOT required to be Danger tagged 2

Danger tagged NOT required to be Danger tagged Danger tagged NOT required to be Danger tagged Procedure 10000-C, Operations Administrative Controls has requirements for Tracking Configuration of Repositioned Components.

A component that is procedurally manipulated from the Control Room to an Off Normal configuration is expected to remain in that position past shift turnover time.

Which ONE of the following is CORRECT concerning how this component is tracked in order to return it to its normal alignment?

A. The only requirement is the component is Caution Tagged stating the reason for its repositioning.

B. The only requirement is the controlling procedure is placed into the Procedures in Progress book in the Control Room.

C. The component is flagged with a Pink Off Normal Component flag and logged in the Unit Control Log.

D The component is flagged with a Pink Off Normal Component flag and controlling procedure placed into the Procedures in Progress book in Control Room.

Page 54 of 85

HL-16 NRC SRO Exam 2011-301

70. G2.3. 15001 /3/N/A/RMS-KNOWLEDGE OF/2.9/3. 1/NEW/RO/SRO/NRC/GCW Per 00930-C, Radiation and Contamination Control, when exiting Contaminated Areas, hand carried tools and materials (e.g., clipboards, notebooks, pencils, etc.) shall be frisked for 1

contamination.

Personnel decontamination should be performed when the results of personnel monitoring exceed a minimum of 2

above background.

A.

(1) Beta-Gamma (2) 200 cpm B. (1)Alpha (2) 200 cpm C (1) Beta-Gamma (2) 100 cpm D. (1) Alpha (2) 100 cpm Page 55 of 85

HL-16 NRC SRO Exam 2011-301

71. G2.3.5 002/31N/AJRMS-USE 0F12.9/2.9 MEM!NEWIRO/SRO/NRC/GCW An operator has exited Containment during a Refueling Outage.

Which ONE of the following is CORRECT concerning the Personnel Monitoring requirements for the operator prior to leaving the RCA?

A Hands and Feet should be frisked at the nearest frisker location.

Proceed to the nearest personnel contamination monitor for a Whole Body survey.

B. Hands and Feet should be frisked at the nearest frisker location.

Proceed to the HP Control Point personnel contamination monitor for a Whole Body survey.

C. Hands and Feet are NOT required to be frisked at the nearest frisker location.

Proceed to the nearest personnel contamination monitor for a Whole Body survey.

D. Hands and Feet are NOT required to be frisked at the nearest frisker location.

Proceed to the HP Control Point personnel contamination monitor for a Whole Body survey.

Page 56 of 85

HL-16 NRC SRO Exam 2011-301

72. G2.3.7 002/3/N/AjRWP/3.5/3.6 MEM/LOIT BANK/RO/SROINRC/GCW An individual is reviewing the RWP before beginning work.

If the dose rate in the area is 900 mrem/hr, he would expect to find a

_____( )

colored RWP requiring an ALARA briefing prior to (b) entry.

A. (a)RED (b) each B. (a) YELLOW (b) each C. (a)RED (b) only the first D (a) YELLOW (b) only the first Page 57 of 85

HL-16 NRC SRO Exam 2011-301

73. G2.4. 14 002/3/N/A/GENERAL EOP USAGE/3.8/4.5 C/A/LOIT BANK/RO/SRO/NRC/GCW Following a Reactor Trip, the IQAs of 1 9000-C, E-0 Reactor Trip or Safety Injection have been completed.

The following conditions exist:

- SG # 1 has a Main Steam Safety Valve stuck open.

- SG # 2 has been identified as having a tube leak by Chemistry sample.

- Both SG levels are currently 12% in the Narrow Range.

- Containment pressure is 4.4 psig.

- The UO desires to isolate AFW flow to both SGs prior to reaching procedural direction to do so.

The UO would be allowed to isolate AFW flow to (a)_, SS permission b) required prior to taking the action.

A (a) SG # 1 only (b) is B. (a) SG # 1 only (b) is not C. (a) both SGs # 1 and # 2 (b) is D. (a) both SGs # 1 and # 2 (b) is not Page 58 of 85

HL-16 NRC SRO Exam 2011-301

74. G2.4.2 002/31N/AJEOPS STPTS-ENTRY/4.5/4.6 C/AIBANKJRO/SROJNRC/GCW The following conditions exist:

- Unit is at 5% reactor power following a start up.

- A Pressurizer Spray valve fails open.

Which ONE of the following would be the first to trip the reactor? (Assume no operator action).

A. OT Delta T Reactor Trip B. Pressurizer High Level Reactor Trip C. Low Pressurizer Pressure Reactor Trip D Pressurizer Pressure Safety Injection Reactor Trip Page 59 of 85

HL-16 NRC SRO Exam 2011-301

75. G2.4.34 00213/N/AJEOP TASK OUT CRJ4.2/4.1 MEM/MOD BANK-FARLEYIRO/SRO/NRC/GCW Given the following:

- A fire required evacuation of the Control Room.

- Charging was aligned to the VCT before exiting the Control Room.

- Procedure 18038-1,Operation From Remote Shutdown Panels is in progress.

- All equipment control has been transferred to the Shutdown Panels.

Upon receipt of a VCT Lo-Lo Level, the RWST to CCP suction valves and VCT outlet isolation valves (1) automatically re-position and 1FV-121 will be controlled locally (2)

A. (1) will (2) from the B Train Shutdown Panel.

B. (1) will (2) from the control box located on C level of the Aux Building.

C. (1)will not (2) from the B Train Shutdown Panel.

Dv (1)will not (2) from the control box located on C level of the Aux Building.

Page 60 of 85

HL-16 NRC SRO Exam 2011-301

76. 003G2.2.22 002! 1/2/DROPPED ROD-LCO/4.7INEW/SRO/NRC/GCW Unit one is at 90% power.

- Control Bank Rod D12 drops to the bottom of the core.

Which ONE of the following describes (1) the status of Control Rod D12 and (2) how is core power distribution limits affected?

A (1) Operable (2) FQ(Z) remains within limits.

8.

(1) Inoperable (2) FQ(Z) limits will be exceeded.

C. (1) Operable (2) FQ(Z) limits will be exceeded.

D. (1) Inoperable (2) FQ(Z) remains within limits.

Page 61 of 85

HL-16 NRC SRO Exam 2011-301

77. 003G2.2.25 OO3I2IIIRCP -TS BASES/4.1 MEMJBANK SEABROOK 2004/SRO/NRCIEMT/GCW Given the following conditions:

- The unit is stable at 557 °F and 2235 psig.

- Both Reactor Trip Breakers are closed, Rod Control is capable of withdrawal.

- Two RCPs are in service.

Which ONE of the following is CORRECT regarding Reactor Coolant Pumps which are required to be in OPERATION and the bases?

A. ONE required to be operating.

Ensures Safety Limit criteria met in the event of an inadvertent rod withdrawal.

B BOTH required to be operating.

Ensures Safety Limit criteria met in the event of an inadvertent rod withdrawal.

C. ONE required to be operating.

Ensures decay heat removal and a homogenous boron concentration in the RCS.

D. BOTH required to be operating.

Ensures decay heat removal and a homogenous boron concentration in the RCS.

Page 62 of 85

HL-16 NRC SRO Exam 2011-301

78. 007A2.02 OO1/2/1/PRT-ABNORM PRESSI3.4 MEM/BANK TURKEY PT 09/SRO/NRC/EMT/GCW Unit 1 is at 100% power.

- PRT pressure and PRZR PORV 456 tailpipe temperature is slowly rising due to excessive seat leakage.

Which ONE of the following correctly identifies the required Tech Spec action and the subsequent operability status of 1 PV-0456?

A. Close PRZR PORV 456A.

1 PV-0456 is OPERABLE.

B. Close PRZR PORV 456A.

1 PV-0456 is INOPERABLE.

C. Close PRZR PORV 456A Block Valve 1 HV-8000B.

1 PV-0456 is INOPERABLE.

D Close PRZR PORV 456A Block Valve 1 HV-8000B.

1PV-0456 is OPERABLE.

Page 63 of 85

HL-16 NRC SRO Exam 2011-301

79. 007EA2.02 003/1/1/RX TRIP-RECOVERY/4.6 CIA]BANK FARLEY 2010/SRO/NRC/GCW Unit 1 is in Mode 3, and the following conditions exist:

- The shutdown banks are withdrawn.

- Technical Specifications requires Mode 5 entry within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

- Tcold is 530°F.

- A complete Loss of Off-Site Power occurs.

- PCC reports that off-site power will be restored in 18 hrs.

Which ONE of the following correctly completes the following statements?

Manual action 1 )

required to open the Rx Trip Breakers.

After the plant is stabilized the crew will utilize (2) to perform the RCS cooldown.

1 )_

A.

IS 19003-C, ES-0.3, Natural Circulation Cooldown With Void In Vessel (With RVLIS).

B IS 19002-C, ES-0.2, Natural Circulation Cooldown.

C.

IS NOT 19003-C, ES-0.3, Natural Circulation Cooldown With Void In Vessel (With RVLIS).

D.

IS NOT 19002-C, ES-0.2, Natural Circulation Cooldown.

Page 64 of 85

HL-16 NRC SRO Exam 2011-301

80. 01 1EA2.08 003/1/1/LB LOCA-RECOVERY/3.9 C/AILORQ BANK/SRO/NRC/GCW A large break loss of coolant accident (LOCA) has occurred 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ago and the crew is performing 1901 0-C, E-1 Loss of Reactor or Secondary Coolant.

Recovery actions are in effect and the control room staff is evaluating conditions for entry into 19014-C, ES-1.4 Transfer to Hot Leg Recirculation.

19014-C, ES-1.4, Transfer to Hot Leg Recirculation will be entered (1)to A. (1) in 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months (2) terminate boiling in the core and to prevent boron precipitation in the core.

B (1) in 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months (2) terminate boiling in the core and to prevent boron precipitation in the core.

C. (1) in 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months (2) refill the reactor vessel and establish reflux cooling.

D. (1) in 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months (2) refill the reactor vessel and establish reflux cooling.

Page 65 of 85

HL-16 NRC SRO Exam 2011-301

81. 022G2.2.42 003/2/1/CNMT COOLERS-TSI4.6 C/AIBANKJSROINRC/GCW Given the following:

- Plant is at 100% power.

- Containment Cooler # 2 High Speed fan trips.

- Electrical maintenance has determined the trip was due to a breaker problem.

- Containment Cooler # 2 Low Speed fans ability to auto function is affected.

Which ONE of the following is CORRECT regarding the Containment Cooling System in accordance with Tech Specs 3.6.6 and the bases for the Containment Spray and Cooling System?

A. Affected train is OPERABLE, Tech Spec bases requires three Low Speed fans to operate in the more dense atmosphere during DBA events.

B Affected train is INOPERABLE, Tech Spec bases requires all Low Speed fans to operate in the more dense atmosphere during DBA events.

C. Affected train is OPERABLE, Tech Spec bases requires three High Speed fans to operate and maintain containment temperature limits following an LOSP event.

D. Affected train is INOPERABLE, Tech Spec bases requires all High Speed fans to operate and maintain containment temperature limits following an LOSP event.

Page 66 of 85

HL-16 NRC SRO Exam 2011-301

82. 025AA2.05 001/1/1/LOSS OF RHRJ3.6 C/A/MOD BANK SURRY 2009/SRO/NRC/GCW Unit 2 Initial conditions:

- Time 0800 hrs.

- Plant is in Fueled Mid-Loop Operation for nozzle dam installation.

- Containment Equipment and Personnel Hatches are secured.

- Steam Generators are not available.

- RCS Temperature = 195 °F and stable.

- RCS level at 187 feet 6 inches and lowering.

- 18019-C, Loss of Residual Heat Removal, has been initiated.

Current plant conditions:

- Time 0825 hrs.

- The running RHR pump was secured due to vortexing.

- RCS temperature = 225 °F and increasing.

- RVLIS Full Range = 70%

- Source Range Indications Unstable.

Based on the above conditions: (1) Classify the event using the Emergency Plan and (2) once RCS level is restored and and if RHR cannot be adequately vented, state the minimum indicated RHR flow that must be established?

(Reference Provided)

A. (1) Alert Emergency (2) 3000 gpm B.

(1) Site Area Emergency (2) 3000 gpm C (1) Alert Emergency (2) 3200 gpm D. (1) Site Area Emergency (2) 3200 gpm Page 67 of 85

HL-16 NRC SRO Exam 2011-301

83. 026G2.2.44 003/1/1/LOSS OF CCW-CR INDIC/4.4 C/AJNEW/SROJNRCJEMT/GCW Unit 1 Large Break LOCA.

- Cold Leg Recirculation is in progress.

- Crew is performing 19010-C, Loss of Reactor or Secondary Coolant.

- The following alarms illuminate:

- ALBO2-C05 CCW Train A Surge TK Make Up LVL

- ALBO2-B05 CCW Train A Surge TK HI/LO LVL

- ALBO2-A05 CCW Train A Surge TK LO-LO LVL Based on the existing conditions, which ONE of the following describes the response of the CCW System makeup valves and the actions that must be taken per 18020-C, Loss of Component Cooling Water?

A. LV-1850 from Demineralized Water auto opens.

Leave the affected RHR pump running.

B.

LV-1 848 from Reactor Makeup Water auto opens.

Stop the affected RHR pump.

C.

LV-1 848 from Reactor Makeup Water auto opens.

Leave the affected RHR pump running.

D LV-1 850 from Demineralized Water auto opens.

Stop the affected RHR pump.

Page 68 of 85

HL-16 NRC SRO Exam 2011-301

84. 034K 1.04 0051212/PH EQUIP-NIS/3.5 C/AINEW/SRO/NRC/EMT/GCW Unit 1 is in Mode 6:

- Preparations for core offload are completed.

- 1 BD1 is removed from service for planned maintenance.

- Source Range Nl-32 is powered with temporary power from 1 NLP39.

- Audible indication is in service in the Control Room and Containment from N 1-32.

Which ONE of the following CORRECTLY completes the following statement?

CORE ALTERATIONS _(1 )_ proceed based on A (1) Can (2) both Source Ranges are OPERABLE.

B. (1)Can (2) only one Source Range is required to be OPERABLE.

C. (1)Can NOT (2) NI-31 must be selected for audible indication to be OPERABLE.

D. (1) Can NOT (2) Nl-32 must be returned to its normal power supply to be OPERABLE.

Page 69 of 85

HL-16 NRC SRO Exam 2011-301

85. 036AA2.02 001/1/2/FUEL HAND ACCIDENT/4. 1 C/A/NEW/SRO/NRC/GCW Core offload is in progress during a refueling outage when the following annunciator window illuminates on the QMCB.

SPENT FUEL PIT LOW LEVEL

- Personnel in the FHB report SEP level at 216 feet 2 inches and lowering.

- Attempts to raise SEP level via normal makeup methods are unsuccessful.

- RE-008 Area Monitors are NOT in alarm but radiation levels are slowly rising.

Which one of the following is correct regarding:

1) if an Emergency Classification is required per NMP-EP-1 10 Emergency Classification Determination and Initial Notification, and

2) what qualifies as an Alternate Source of Makeup during Emergency Conditions per Attachment C of AOP-18030-C, Loss of Spent Euel Pool Cooling or Level?

Reference Provided Do NOT consider Emergency Director Discretion A.

1) No event classification is required at this time.

2) Fire Water via hose cabinets.

B.

1) No event classification is required at this time.

2) Recycle Holdup Tank to the transfer canal.

C 1) Notification of Unusual Event (NOUE) is required.

2) Fire Water via hose cabinets.

D.

1) Notification of Unusual Event (NOUE) is required.

2) Recycle Holdup Tank to the transfer canal.

Page 70 of 85

HL-16 NRC SRO Exam 2011-301

86. 037G2.4.4 002/1/2/SGTL ENTRY/4.7 C/A/MOD SUMMER 06/SRO/NRC/GCW Given the following plant conditions:

- A Steam Generator Tube leak has been identified on SG # 2.

- The crew has entered AOP-1 8009-C, Steam Generator Tube Leak.

- Based on RE-0724 and RE-0810 reading, the following trend is developed:

-2115 62gpd

-2215 68gpd

-2315 lO9gpd

-0015 362gpd

- 0045 580 gpd with Pressurizer level currently stable.

- VCT level is 8.2% and trending down with maximum makeup in progress.

Which ONE of the following actions is correct in accordance with AOP-1 8009-C?

A. Isolate CVCS letdown.

Initate 12004-C, Power Operation (Mode 1) and be in Mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

B. Swap charging suction to the RWST.

Trip the reactor, when reactor trip verified, actuate SI, then go to 19000-C, E-0.

C. Isolate CVCS letdown.

Initiate 12004-C, Power Operation (Mode 1) and be in Mode 3 within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

D Swap charging suction to the RWST.

Trip the reactor, intiate 19000-C, E-0 concurrently with actions of AOP-1 8009-C.

Page 71 of 85

HL-16 NRC SRO Exam 2011-301

87. 056G2.2.42 004/1 / 1/LOSP-TS/4.6 C/AJBANK/SROINRC/GCW Given the following conditions:

- An RCS heatup is in progress on Unit 1 in preparation for a Mode change following refueling.

- Tavg is 195 °F.

- Outside air temperature is 12°F.

- An LOSP has occurred and resulted in the loss of the RWST Heater.

- RWST water temperature is 42 °F.

- RWST Boron Concentration is 2470 ppm.

Which ONE of the following identifies the status of the RWST and the actions relative to the upcoming Mode change?

Status of RWST Actions Relative to Mode ChanQe A Below minimum temperature.

Heatup can continue. Mode change can be made only if a risk assessment is performed.

B. Below minimum temperature.

Heatup must be stopped. Mode change is prohibited until the RWST heater is restored.

A risk assessment is NOT required.

C. Below minimum Heatup must be stopped. Mode change is Boron Concentration, prohibited until the RWST Boron Concentration is restored. A risk assessment is NOT required.

D. Below minimum Heatup can continue. Mode change can be Boron Concentration.

made only if a risk assessment is performed.

Page 72 of 85

HL-16 NRC SRO Exam 2011-301

88. 062G2. 1.20002/1 / 1/LOSS OF NSCW/4.6 C/A/NEW/SROIHL-16 NRC/GCW Given the following conditions at full power.

- NSCW pump # 4 is danger tagged.

An LOSP occurs with both 4160 1 E buses load shedding, then being re-energized from their respective DGs.

- Catastrophic leakage occurs and pumps 1, 3, & 5 are now in PTL

- NSCW pump 2 is running and pump 6 wont start In accordance with 18021-C, Loss of Nuclear Service Cooling Water System:

1) which is the required action to take, and

2) the required Tech Spec actions?

A.

1) Remain in 18021-C, place NSCW train B in single pump operations.

2) Perform the actions of LCO 3.7.8, NSCW and 3.8.1, AC Sources

- Operating.

B.

1) Remain in 18021-C, place NSCW train B in single pump operations.

2) Perform actions of LCO 3.0.3.

C. 1) Trip the reactor and initiate 19000-C, E-0 Reactor Trip or Safety Injection.

2) Perform the actions of LCO 3.7.8, NSCW and 3.8.1, AC Sources

- Operating.

D 1) Trip the reactor and initiate 19000-C, E-0 Reactor Trip or Safety Injection.

2) Perform actions of LCO 3.0.3.

Page 73 of 85

HL-16 NRC SRO Exam 2011-301

89. 064A2. 14 002/2/IIEDG-STOP UNDER LOAD/2.9 CIAJNEWISROINRCIGCW Unit 2 is at 100% power with all systems in normal alignment.

- Reserve Auxiliary Transformer 2A trips.

- DG2A starts and ties to 2AA02 and load sequencing is complete.

- Only NSCW pump 1 is running

- Attempts to start pumps 3 and 5 are NOT successful.

- The UO depresses both EMERGENCY STOP pushbuttons for DG2A.

- The crew has performed AOP-1 8031 -2, Loss of Class 1 E Electrical Systems, taken appropriate actions, and have reached the steps for addressing Technical Specifications.

When DG2A trips, during the load shed, the transformers to the 480V 1 E switchgear breakers trip open.

The FIRST LCO stated below that requires the plant to be placed in Mode 3 is REFERENCE PROVIDED A.

(1) high side (2) 3.8.1, AC Sources

- Operating B. (1)lowside (2) 3.8.1, AC Sources

- Operating C. (1) high side (2) 3.8.9, Distribution Systems

- Operating D (1) low side (2) 3.8.9, Distribution Systems

- Operating Page 74 of 85

HL-16 NRC SRO Exam 2011-301

90. 068AA2.04 004/1/2/CR EVACUATION/4.0 MEM/NEW/SROINRC/GCW The Main Control Board indicators for various Steam Generator (SG) pressure channels display a RED Bezel on the bottom of the indicator. SG pressures are also displayed on the Remote Shutdown Panels.

Which ONE of the following is correct concerning both (1) the Control Room indicators and (2) the Remote Shutdown Panel indicators for SG Pressure?

A. (1) The Control Room indicators are Post Accident Monitoring qualified only.

(2) The B Remote Shutdown Panel indicators are Fire Event qualified only.

B. (1) The Control Room indicators are Post Accident Monitoring and Fire Event qualified.

(2) The B Remote Shutdown Panel indicators are Fire Event qualified only.

C (1) The Control Room indicators are Post Accident Monitoring qualified only.

(2) The B Remote Shutdown Panel indicators are NOT Fire Event qualified.

D. (1) The Control Room indicators are Fire Event qualified only.

(2) The B Remote Shutdown Panel indicators are NOT Fire Event qualified.

Page 75 of 85

HL-16 NRC SRO Exam 2011-301

91. 072G2.4.46 00212/2/ARM-ALARMS/4. 1 C/A/MOD BANK/SRO/NRC/GCW A dropped fuel assembly in the Unit 2 Spent Fuel Pool has resulted in the following indications on the FHB Effluent Radiation Monitors:

- ARE-2533A is in HIGH alarm.

- ARE-2532A, 2532B, and 2533B are all in INTERMEDIATE alarm.

In addition:

- 2RE-0008, Fuel Handling Building Area Monitor is in HIGH alarm.

The crew enters AOP-18006-C, Fuel Handling Event and is at the step to check proper FHB HVAC alignment.

Which ONE of the following is CORRECT regarding:

1) how many FHB Post Accident Filtration Units would auto start, and

2) operator actions to take, if any, per the AOP and the bases?

Av 1)two auto start

2) stop one unit, to limit the offsite dose release.

B. 1)oneautostarts

2) start an additional unit, to ensure negative pressure in FHB.

C. 1)two auto start

2) take no action, both running limits airborne concentrations in FHB atmosphere.

D.

1) one auto starts

2) start an additional unit, to limit airborne concentrations in the FHB atmosphere.

Page 76 of 85

HL-16 NRC SRO Exam 2011-301

92. 073A2.02 002/2/1 /PRM-DETECTOR FAIL/3.4 C/A/NEW/SRO/NRC/GCW A Containment Pressure relief is in progress on Unit 1.

A lightning strike on Unit 1 containment causes a detector failure for each of the following radiation monitors:

- 1 RE-2562A, Containment Atmosphere Gaseous

- 1 RE-2562C, Containment Particulate Radiation

- 1 RE-i 2444C, Plant Vent Noble Gas Activity Monitor Which ONE of the following is the CORRECT actions to take for these failures?

A. Immediately terminate pressure relief.

Enter Tech Spec LCO 3.0.3.

B. Pressure relief may continue.

Obtain grab samples at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and analyze for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

C. Immediately terminate pressure relief.

Release may be re-started provided samples are continously collected with auxiliary sampling equipment.

Dv Pressure relief may continue.

Perform an RCS Leak Rate once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND restore the monitors to operable status in 30 days.

Page 77 of 85

HL-16 NRC SRO Exam 2011-301

93. 086A2.02 005/2/2IFP-LOW HEADER PRESS/3.3 C/A/NEW/SRO/NRC/GCW Given the following conditions:

- Diesel Fire Pump #1 is tagged out for maintenance.

- Electric Fire Pump starts and trips.

- Fire Header pressure is 98 psig and lowering.

Diesel Fire Pump #2 low pressure auto start setpoint is (1).

If the remaining Fire Pump fails to start, the Fire Protection LCO action is to establish a backup fire suppression supply sytem using the (2)

A. (1)95psig (2) Category 1 Standpipe.

B.

(1) 85 psig (2) Category 1 Standpipe.

C. (1) 95 psig (2) Burke County EMA pumper Truck.

D (1)85 psig (2) Burke County EMA pumper Truck.

Page 78 of 85

HL-16 NRC SRO Exam 2011-301

94. G2.1.23 OO3I3INIAICOND OF OPSI4.4 C/AJNEW/SRO/NRC/GCW The following conditions exist on Unit 2:

- Charging flow at 93 gpm.

- Letdown flow at 75 gpm.

- Seal leakoff flow at 12 gpm.

- 2RE-0724 Rate of Change (ROC) indicates 75 gpd/hr and has maintained that value for the last 21 minutes.

- Chemistry has identified SG #2 as having the leak.

- The operators have entered 18009-C, Steam Generator Tube Leakage.

Which ONE of the following would be the CORRECT (1) procedure response to take and (2) the required Tech Spec actions and completion times for LCO 3.4.13 RCS Operational LEAKAGE?

A.

(1) Initiate to 18013-C, Rapid Power Reduction.

(2) Identified leakage has been exceeded. Be in Mode 3 in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

B (1) Initiate to 18013-C, Rapid Power Reduction.

(2) Primary to secondary leakage has been exceeded. Be in Mode 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

C. (1) Initiate 12004-C, Power Operation (Model).

(2) Identified leakage has been exceeded. Be in Mode 3 in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

D. (1) Initiate 12004-C, Power Operation (Model).

(2) Primary to secondary leakage has been exceeded. Be in Mode 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Page 79 of 85

HL-16 NRC SRO Exam 2011-301

95. G2.!.44 002/31N/AICOND OF OPS-RO DUTIEI3.8 CIA/BANK HARRIS2009ISRO[NRC/GCW The unit is in Mode 6 with core reload in progress with the following conditions.

- Rx Cavity level flooded to 220 foot elevation.

- RHR pump B in service.

- RHR pump A tagged out for outage maintenance work.

In accordance with Technical Specifications for the above conditions, which ONE of the following completes the statement below.

The operating RHR loop may be secured for a maximum of up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per _(1)_

to perform core alterations in the vicinity of the Reactor Vessel _(2).

A. (1)4hourperiod (2) Hot Legs BY (1) 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period (2) Hot Legs C. (1)4hourperiod (2) Cold Legs D. (1) 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period (2) Cold Legs Page 80 of 85

HL-16 NRC SRO Exam 2011-301

96. G2.2. 12 002/31N/A/SURV PROCEDURES/4. 1 C/A/LOIT BANK/SRO/NRC/GCW Initial conditions:

- The unit is at 100% power.

- A surveillance has a specified periodicity of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

- The surveillance was last performed 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months ago.

It normally takes approximately 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to complete the surveillance.

Which one of the following demonstrates the correct use of Surveillance Requirement (SR) Applicability (SR 3.0.2) of the VEGP Technical Specifications for this situation?

A Ensure the surveillance is performed in the next 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

B. Ensure the surveillance is performed in the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

C. Declare the LCO not met if the surveillance is not completed in the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

D. Apply the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months delay provided by SR 3.0.3 to allow time to complete the surveillance.

Page 81 of 85

HL-16 NRC SRO Exam 2011-301 9T G2.2.44 003/3/N/A/CR INDICATIONS/4.4 MEMJNEW/SRO/NRC/GCW A seismic event has occurred.

Unit 2 CST levels are as follows:

- CST # 1 is 70% and stable.

- CST # 2 is 11% and lowering.

The Unit 2 CSTs are

1) and the basis for the Tech Spec minimum level requirements are tor(2)..

followed by a 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months cooldown to RHR entry conditions.

A. (1) OPERABLE (2) holding the unit in MODE 3 for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B.

(1) OPERABLE (2) holding the unit in MODE 3 for 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months C. (1) INOPERABLE (2) holding the unit in MODE 3 for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months D (1) INOPERABLE (2) holding the unit in MODE 3 for 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Page 82 of 85

HL-16 NRC SRO Exam 2011-301

98. G2.3.6 002/3/N/A/APPROVE RELEASE P/3.8 MEMJBK VOGTLE 2005 NRC/SRO/NRC/GCW The SS has received a completed release permit for the following tanks:

- Waste Monitor Tank 009 (Unit 1)

- Waste Monitor Tank 010 (Unit 2)

Due to the plant schedule, Operations Management would like both tanks to be released at the same time in accordance with 1321 6-1/2, Liquid Waste Release.

Which ONE of the following correctly states the procedure requirements given the above conditions?

A. Two tanks cannot administratively be released at the same time.

B. Two tanks may be released without additional authorization because they are on different Units.

C The two tanks may be released simultaneously as long as the SS receives authorization from the Chemistry Manager.

D. The two tanks may be released simultaneously as long as the SS receives authorization from the Health Physics Supervisor.

Page 83 of 85

HL-1 6 NRC SRO Exam 2011-301 99 G2.4. t8 003131N/AIEOP BASIS/4.O C/A/NEWIINRCIGCW 19231-C, FR-H.l, Response To Loss of Secondary Heat Sink is in effect.

- All SG WR levels are - 8%.

- PORV 455 and associated Block Valve are open.

- PORV 456 Block Valve is shut and cannot be opened.

- All Reactor Vessel Head Vent valves are open.

- All CCPs and SIPs are running.

- CETs are 562°F and stable.

- Restoration of feed capability is imminent.

Which ONE of the following is CORRECT regarding:

1) the current RCS bleed path, and

2) the proper procedural action to take when feed flow is restored?

RCS Bleed Path Feed Restoration A. adequate remain in 19231-C until at least one SG NR level >10%

B. adequate immediately exit to 19010-C, Loss of Reactor or Secondary Coolant C not adequate remain in 19231-C until at least one SG NR level> 10%

D. not adequate immediately exit to 19010-C, Loss of Reactor or Secondary Coolant Page 84 of 85

HL-16 NRC SRO Exam 2011-301 10G. G24.3 1 002/3/N/A/EMERG PROC-ARP/4. 1 C/AJBANK WOLF CREEK 07/SRO/NRC/GCW Initial conditions:

- A loss of RCS level during mid-loop operations occurred.

- AOP 18019-C, Loss of Residual Heat Removal was implemented.

- RHR pump 1 B has been stopped.

Current conditions:

- Core exit TCs have been verified at 129 F and increasing.

- RCS MIDLOOP LO LEVEL alarm is lit.

- RCS level is currently 185 10 and lowering.

- RCS cold and hot legs are intact (no openings).

The SS is at step Bi 1 which reads:

Bi 1.

Check RCS level:

_a. LESS THAN 188 FEET

b. LESS THAN 186 FEET The preferred method to restore RCS level is to make up from the RWST using A. a CCP through the normal charging path into an intact cold leg.

B. a CCP through the BIT into an intact cold leg.

C an SI pump through the RCS hot legs.

D. an SI pump through the RCS cold legs.

Page 85 of 85

- Answers ID 0.

1 001G2.4.92 B

2 001K2.052 D

3 002K5.112 A

4 003K5.03 2 A

5 003K6.02 1 B

6 004A3.06 2 B

7 005A1.02 I C

8 005A4.03 2 B

9 006A1.072 C

10 006G2.1.302 B

11 007A1.032 A

12 OO8AKI.01 1

A 13 009G2.4.8 2 A

14 010K6.042 B

15 O1IEA1.032 C

16 011K4.034 A

17 012A4.07 1

D 18 013K5.012 B

19 014A1.022 A

20 017K6.01 1

B 21 022A4.05 2 D

22 022AA2.03 4 C

23 022K3.02 2 A

24 025AK1.01 2 A

25 026K3.02 2 A

26 027AK2.03 2 A

27 028AK1.01 2 D

28 029EK3.02 2 A

29 029K1.022 D

30 033AK3.01 2 C

31 033G2.4.49 2 C

32 035A4.06 2 D

33 038EK3.01 2 A

34 039G2.2.39 2 C

35 054G2.4.49 I C

36 055EA1.01 3 A

37 055K3.01 2 A

38 056AK3.01 3 D

39 057AA2.02 1

C 40 058G2.4.49 2 D

41 059K4.182 C

42 0591(4.193 C

43 060AK2.01 2 A

44 061K2.01 2 D

45 061K6.022 D

46 0621(4.022 D

47 063A2.01 2 D

48 064G2.2.12 2 A

Page: 1 of 3 4/6/2011

Answers ID 0

--V 49

064K3.032

B 50 067AA1,072 A

51 068A3.022 B

52 068AK3.08 2 D

53 073K1.012 C

54 073K5.02 2 B

55 076A3.02 1 c

56 076AA2.032 B

57 076K1.052 B

58 077AA2.07 2 D

59 103K1.082 A

60 WEO4EK1.1 2 B

61 WEO5EA1.12 A

62 WEO8EAI.1 2 D

63 WEO9G2.4.9 I D

64 WE11EK2.22 B

65 WE12EK2.1 2 A

66 G2.1.12 C

67 G2.1.232 B

68 G2.2.132 B

69 G2.2.142 D

70 G2.3.15 1

C 71 G2.3.5 2 A

72 G2.3.72 D

73 G2.4.142 A

74 G2.4.2 2 D

75 G2.4.34 2 D

76 003G2.2.22 2 A

77 003G2.2.25 3 B

78 007A2.02 1 D

79 007EA2.02 3 B

80 O11EA2.083 B

81 022G2.2.42 3 B

82 025AA2.05 1 C

83 026G2.2.44 3 D

84 034K1.045 A

85 036AA102 I C

86 037G2.4.4 2 D

87 056G2.2.42 4 A

88 062G2.1.20 2 D

89 064A2.142 D

90 068AA2.044 C

91 072G2.4.46 2 A

92 073A2.02 2 D

93 086A2.02 5 D

94 G2.1.233 B

95 G2.1.442 B

96 G2.2.122 A

Page: 2 of 3 4/6/2011

c.)uu c

c-1 c.

()Lc C

tQOC

Southern Nuclear Operating Company Nuclear NMP-TR-21 5-F02 SOUTHERN A Management Exam Question Feedback Version 1.0 COMPANY Form Page 1 of 2 NOTE:

The Comment box should be checked if the question is not worded clearly or contains errors and/or misleading information. The Challenge box should be checked if the question to be reviewed for credit on your exam. Include your name.

Exam

Title:

Voqtle 2011 NRC SRO Examination 4/1/11 Date Exam Administered Submitted By: Andrew Dyer 4/5/11 Date El Comment Challenge Question Identifier (Complete number example:

Question #10 AFW-40201 D08004) LOCT Cycle 3, Question #2)

State the reason for comment or challenge on the question:

Question #10 states that the main control room has been evacuated and all switches at PSDB have been taken to local and all switches at PSDA have not been taken to local. An automatic SI then occurs. This will cause Train A SI to automatically actuate. Per 18038-C step 30 RNO ci. substep 2, we will start ECCS pumps as necessary to maintain PRZR pressure. Step 39 also has us start ECCS pumps on both trains to maintain PRZR level between 50%-70%. Appendix E, part B, number 7 of NUREG1 021 Supplement 1 states that you should assume actions would take place if they are a consequence of conditions stated in the question.

(State the question unambiguously, precisely, and as concisely as possible, but provide all necessary information. Often the individuals who develop a question assume that certain stipulations or conditions are inherent in the question when, in fact, they are not NUREG 1021

- Appendix B, page 4 of 29). One must assume all procedural actions between SI actuation and SI termination criteria being met are completed as required. Both trains of ECCS would be running with shutdown panel switches in the LOCAL position and would be required to be shut down at their respective shutdown panels once SI termination criteria were met in 18038-C. The stem of the question does not contain a specific time frame. This would make choice D also a correct answer for question #10.

Operation Management supports this challenge for the reasons stated above.

Challenge Review:

Credit given to the submitter El YES El NO Key changed El YES El NO N/A Submitted for exam bank update El YES El NO El N/A Exam Bank Review:

Comment/Challenge incorporated El YES El NO El N/A

Southern Nuclear Operating Company Nuclear I

I NMP-TR-215-F02 SOUTHERNA Management I

Exam Question Feedback Version 1.0 COMPANY Form I

Page 2 of 2 Reason for not incorporating:

challenge Approved:

Training Supervisor Date

N/A if challenge does not result in an exam key change

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN Page Number 8/27/2010 PANELS 21 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 27.

Trip the following breakers:

BREAKER NO.

LOCATION SIGNIFICATION EQUIPMENT ACTIONS 1AY2A-17 AB-118

Closes SG ARV 1-PV-3000 IAY2A-18 AB-118

Closes SG ARV 1-PV-3030

_28.

Inside Shutdown Panel B, place 1-HS-3010A and 1-HS-3020A to the FIRE EMERGENCY position.

29.

Align CCP suction to RWST:

At Shutdown Panel B Open 1-LV-0112E Close 1-LV-0112C

-OR At Shutdown Panel A Open 1-LV-0112D Close 1-LV-0112B Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN Page Number 8/27/2010 PANELS 22 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTIONS If there is a Control Room fire, Train B is preferred for Pressurizer pressure control.

PRZR Heaters will NOT turn off on low PRZR level after control has been transferred to the Shutdown Panels.

30.

Control PRZR pressure between

30.

IF PRZR pressure cannot be 2220 and 2260 psig:

controlled between 2220 and 2260 psig and pressure is less Operate Backup Heaters on than 2220 psig AND lowering, Shutdown Panel A or Shutdown THEN:

Panel B.

a.

Verify PRZR PORVs Operate PRZR Sprays on

1-PV-0455A (Shutdown Shutdown Panel A.

Panel A) and 1-PV-0456A (Shutdown Panel B) closed.

Step 30 continued on next page Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN Page Number 8/27/2010 PANELS 23 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED b.

11 PRZR PORV can NOT be

closed, THEN close its Block Valve:

1-HV-8000A (Shutdown Panel A)

1-HV-8000B (Shutdown Panel B)

-OR-Trip the following:

Breaker4onlADlM (CB-B52) for 1 -PV-0455A

-OR

Breaker 4 on 1 BD1 M (CB-B47) for 1 -PV-0456A

_c.

Verify PRZR Spray Valves on Shutdown Panel A closed.

d.

PRZR Spray Valve can NOT be closed, THEN stop RCP 4 (SDP A).

_e.

IF PRZR pressure continues lowering due to open Spray

Valve, THEN stop RCP 1 (SDP A).

Step 30 continued on next page Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN PageNumber 8/27/2010 PANELS 24 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

_f.

Verify PRZR level greater than 19%,

THEN energize PRZR Heaters (SDP A and SDP B).

g.

IF PRZR pressure is less than 1870 psig or continues to lower, THEN perform the following:

1)

Close letdown isolation valves:

1-LV-459(SDPA) 1-LV-460(SDPA) 2)

Start ECCS pumps as necessary:

CCP SIP RHR Pumps 3)

Align CCPs to RWST suction:

Open RWST TO CCPA&B SUCTION:

1-LV-0112D 1-LV-0112E Close VCT OUTLET ISOLATION:

1-LV-0112B 1-LV-0112C Step 30 continued on next page Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN PageNumbet 8/27/2010 PANELS 25 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4)

Close CHARGING TO RCS ISOLATION valves:

1-HV-81 05 1-HV-8106 5)

Open BIT DISCH ISOLATION valves:

1-HV-8801A 1-HV-8801B Step 30 continued on next page Prhited April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DteApproved OPERATION FROM REMOTE SHUTDOWN PageNumber 8/27/2010 PANELS 26 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED IF PRZR pressure is greater than 2260 psig, THEN:

a.

De-energize PRZR Heaters on Shutdown Panel A and Shutdown Panel B.

b.

Control pressure using Normal PRZR Sprays (SDPA).

c.

Normal PRZR Spray NOT available, AND letdown is in

service, THEN use Auxiliary Spray:

_1)

Open 1-HV-8145 (SDPA).

2)

Close Normal Charging Isolation valves:

1-HV-8146 (SDP A) 1-HV-8147 (SDP B) 3)

Verify Normal PRZR Spray Valves closed:

1-PV-455B (SDP A) 1-PV-455C (SDP A) d.

IF Auxiliary Spray NOT available, THEN use a PRZR PORV:

1-PV-455A(SDPA)

1-PV-456A (SDP B)

Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Staney Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN PageNumber 8/27/2010 PANELS 27 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 31.

Verify at least one PRZR PORV Block Valve

- OPEN:

_1 -HV-8000A PRZR PORV 455A BLOCK VALVE (Shutdown Panel A)

_1-HV-8000B PRZR PORV456A BLOCK VALVE (Shutdown Panel B)

V CAUTION The AFW pumps and throttle valves will NOT respond to automatic signals after control has been transferred.

If an SG fed by the MDAFW pump is also being fed from the TDAFW pump, one of the MDAFW pumps throttle valves or its miniflow valve must remain fully open to maintain minimum miniflow requirements.

32.

Control SO WR level(s) between

_*32.

IF MDAFW pumps NOT 65% and 70% on all SGs:

available, THEN initiate ATTACHMENT A.

a.

On Shutdown Panel A:

_1)

Start MDAFW Pump A.

_2)

Throttle 1-HV-5139 and 1 -HV-51 37.

_3)

Operate miniflow 1-FV-5155 as follows:

OPEN

- Total Pump flow less than 175 gpm.

CLOSE - Total Pump flow greater than 330 gpm.

Step 32 continued on next page PrintedApiil5 2011 at 12:45

Approved By Procedure Number Rev J. B. Staney Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN PageNumber 8/27/2010 PANELS 28 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED b.

On Shutdown Panel B:

_1)

Start MDAFW Pump B.

_2)

Throttle 1-HV-5134 and 1-HV-51 32.

_3)

Operate miniflow 1-FV-5154 as follows:

OPEN

- Total Pump flow less than 175 gpm.

CLOSE - Total Pump flow greater than 330 gpm.

Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN PageNumber 8/27/2010 PANELS 29 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Closing BSIVs by opening IAD12-03 and 1BD12-03 will isolate RMW to VCT blender.

33 CHECK RCS temperature

33 IF temperature is less than STABLE AT OR TRENDING TO 557°F and lowering, 557°F.

THEN:

a.

Verify SGARVs are closed.

IISGARVcanNOTbe

closed, THEN control RCS temperature by initiating ATTACHMENT E.

-OR-Close SGARV by opening its breaker:

Brkrl7on lAY2Afor 1-PV-3000 (AB-1 18)

Brkrl8on lAY2Afor 1-PV-3030 (AB-1 18)

Brkr lOon 1BYC1 for 1-PV-3010 (CB-B61)

Brkr 12 on 1BYCI for 1-PV-3020 (CB-B61)

_b.

IF cooldown continues, THEN throttle total AFW flow to a minimum of 570 gpm, OR less if at least one SG level is above 10% NR.

33 continued on next page Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN PageNumber 8/27/2010 PANELS 30 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED c.

IF cooldown continues, THEN close MSIVs, BSIVs and SGBD valves by opening the following breakers:

At 1ADI2 (CB-B52)

Breaker 8 Breaker 3 At IAD1 1 (CB-B52)

Breaker 8 At1BD12(CB-B47)

Breaker 8 Breaker 3 IF temperature greater than 557°F and rising, AND IF a control room fire, THEN control RCS temperature by performing the following:

Initiate ATTACHMENT G.

-OR Use SGARVs 1-PV-3010 and 1-PV-3020 by initiating ATTACHMENT E.

Step 33 continued on next page Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN PageNumber 8/27/2010 PANELS 31 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED IF temperature greater than 557°F and rising, AND IF NOT a control room

fire, THEN control RCS temperature by performing the following:

Use SGARVson Shutdown Panel A or Shutdown Panel B.

-OR-By initiating ATTACHMENT E.

NOTE If an SI actuation occurs, TSC consultation may be necessary after it is staffed.

34 Check if SI is actuated.

_*34*

Go to Step 39.

Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DteApproved OPERATION FROM REMOTE SHUTDOWN Page Number 8/27/2010 PANELS 32 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 35.

Check if ECCS flow should be 35.

Do not reduce ECCS flow.

reduced:

_Consult TSC when it is staffed.

RCS subcooling

- GREATER THAN 24°F (using Core Exit Go to Step 37.

Temperature and RCS WR pressure)

RCS pressure

- STABLE OR RISING PRZR level - GREATER THAN 9%

Secondary heat sink:

Total feed flow to SGs GREATER THAN 570 gpm.

-OR WR level in at least one SG

- GREATER THAN 65%.

NOTE Train B is the preferred charging train for a Control Room fire when operating from Remote Shutdown Panels.

36.

Reduce ECCS flow by stopping the following equipment:

All but 1 CCP SI Pumps RHR Pumps Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley VogUe Electric Generating Plant 18038-1 DateApproved OPERATION FROM REMOTE SHUTDOWN PageNumber 8/27/2010 PANELS 33 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 37.

IF preferred normal power is supplying Emergency 41 60V Busses, THEN stop emergency Diesel Generators using local emergency stop pushbuttons.

38.

Check NCP stopped

- BREAKER 38.

Perform the following:

I NAO5-08 TRIPPED (AB-A52).

_a.

Turn 1 NAO5-08 control power breaker off.

b.

Trip 1 NAO5-08.

Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 Date Approved OPERATION FROM REMOTE SHUTDOWN Page Number 8/27/2010 PANELS 34 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTIONS 1-LV-01 12B, 01 12C, 01 12D, 01 12E will NOT reposition on VCT low-low level after they have been transferred to the Shutdown Panels.

PRZR Heaters will NOT cut off on low PRZR level after controls have been transferred to the Shutdown Panels.

When operating from the Shutdown Panels, Train B is the preferable charging train.

Closing BSIVs by opening 1AD12-03 and 1BD12-03 will isolate RMW to VCT blender.

39 Control PRZR level 50% to 70%:

a.

Check charging pump suction a.

Align charging pump suction aligned to VCT:

to RWST:

Letdown in service At Shutdown Panel B:

(1-Fl-0132B on Shutdown Panel A).

Open 1-LV-0112E.

1-LV-0112B VCT OUTLET Close 1-LV-0112C.

ISOLATION on Shutdown Panel A - OPEN.

-OR-1-LV-01 12C VCT OUTLET At Shutdown Panel A:

ISOLATION on Shutdown Panel B

- OPEN.

Open 1-LV-0112D.

1-LV-01 12D RWST TO Close 1-LV-01 12B.

CCP-A&B SUCTION on Shutdown Panel A CLOSED.

1-LV-0112E RWSTTO CCP-A&B SUCTION on Shutdown Panel B CLOSED.

Step 39 continued on next page Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN Page Number 8/27/2010 PANELS 35 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED b.

Open CHARGING TO RCS ISOLATION valves:

1-HV-8105

(Shutdown Panel B) 1-HV-8106 (Shutdown Panel A) c.

IFSlactuated, THEN at discretion of Shift Supervisor, close BIT DISCH ISOLATION valves:

1-HV-8801A

(Shutdown Panel A) 1-HV-8801B

(Shutdown Panel B)

_d.

Start CCP B on Shutdown Panel B or CCP A on Shutdown Panel A.

_e.

Start additional CCP if desired while waiting for local charging valve 1-FHC-0121 (AB-C113)to be manned

_f.

Stop NCP by locally tripping breaker 1 NAO5-08 (AB-A52).

Step 39 continued on next page Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN PageNumber 8/27/2010 PANELS 36 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED g.

Maintain PRZR level between 50% and 70%:

Throttle charging using 1-FHC-0121 (outside NCP Room in AB-Ci 13).

Control seal injection flow 8 to 13 gpm per RCP by throttling 1-1208-U6-136 and closing 1-1208-U6-134 (both in NCP valve gallery AB-Ci 12).

-OR-IF instrument air is NOT available, THEN maintain PRZR level between 50% and 70% by using ATTACHMENT F.

Step 39 continued on next page g.

Maintain PRZR level between 50% and 70%

using either of the following:

With CCP B running:

1)

Verify mini-flow path:

1-HV-8110 CCP-A&B COMMON MINIFLOW open (Shutdown Panel A).

1-HV-8111B CCP-B MINIFLOW open (Shutdown Panel B).

NOTES At SS discretion, ATTACHMENT F may be used to establish Safety Grade Charging even if Instrument Air is available.

CCP motor starting limitations are two consecutive starts from ambient temperature, one start from operating temperature; subsequent start after 15 minutes running or 45 minutes standstill.

ATTACHMENT L should be used to locally operate 1-FHC-0121.

Printed Apd5, 2011 at 12:45

Approved Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 Date Approved OPERATION FROM REMOTE SHUTDOWN Page Number 8/27/2010 PANELS 37 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2)

Isolate letdown by closing LETDOWN ISOLATION VLV UPSTREAM 1-LV-460 AND LETDOWN ISOLATION VLV DOWNSTREAM 1-LV-459 (Shutdown Panel A).

_3)

Close CHARGING TO RCS ISOLATION 1-HV-8106 (Shutdown Panel A).

_4)

Open 1-HV-8801B BIT DISCH ISOLATION (Shutdown Panel B).

5)

Control PRZR level by:

Closing and opening 1-HV-8801 B (Shutdown Panel B).

-OR Stopping and starting CCP B.

Step 39 continued on next page Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 Date Approved OPERATION FROM REMOTE SHUTDOWN Page Number 8/27/2010 PANELS 38 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

_6)

At Shift Supervisors discretion, establish control of seal injection flow by closing 1-1208-U6-153 to isolate 1-FV-0121 (reach rod handwheel in NCP valve gallery AB-C112), and throttle seal injection using 1-1208-U6-151, (reach rod handwheel in CCP B valve gallery AB-Ci 19). Flows can be monitored locally on 1-Fl-0143B and 1-Fl-0142B (FHB-A10) or on Plant Computer.

-OR-With CCP A running:

1)

Verify mini-flow path:

1-HV-8110 CCP-A&B COMMON MINIFLOW open (Shutdown Panel A).

1-HV-81 1 1A CCP-A MINIFLOW open (Shutdown Panel B).

Step 39 continued on next page Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN Page Number 8/27/2010 PANELS 39 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

_2)

Isolate letdown by closing LETDOWN ISOLATION VLV UPSTREAM 1-LV-460 AND LETDOWN ISOLATION VLV DOW NSTREAM 1 -LV-459 (Shutdown Panel A).

_3)

Close 1-HV-8105 CHARGING TO RCS ISOLATION (Shutdown Panel B).

_4)

Open 1-HV-8801A BIT DISCH ISOLATION (Shutdown Panel A).

5)

Control PRZR level by:

Closing and opening 1-HV-8801A (Shutdown Panel A).

-OR

Stopping and starting CCPA.

Step 39 continued on next page Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN PageNumber 8/27/2010 PANELS 40 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

_6)

At Shift Supervisors discretion, establish control of seal injection flow by closing 1-1208-U6-153 to isolate 1-FV-0121 (reach rod handwheel in NCP valve gallery AB-C112) and throttle seal injection using 1-1208-U6-152 (reach rod handwheel in CCP A valve gallery AB-CI 14). Flows can be monitored locally on 1-Fl-0144B and 1-FI-0145B (AB-A09) or on Plant Computer.

Step 39 continued on next page Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN Page Number 8/27/2010 PANELS 41 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Power may need to be restored by closing breakers 1ADI2-03 (CB-B52) and IBDI2-03 (CB-B47) to establish safety grade letdown.

h.

H PRZR level can NOT be maintained less than 88%,

THEN open the following until PRZR level lowers to less than 70%:

Train B head vent:

1-HV-8095B RX HEAD

VENT TO LETDOWN ISOLATION VLV 1-HV-8096B RX HEAD VENT TO LETDOWN ISOLATION VLV 1-HV-0442B REACTOR

HEAD VENTTO PRT Train A head vent:

1-HV-8095A RX HEAD

VENT TO LETDOWN ISOLATION VLV 1-HV-8096A RX HEAD VENT TO LETDOWN ISOLATION VLV 1-HV-0442A REACTOR HEAD VENT TO PRT Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN PageNumber 8/27/2010 PANELS 42 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTES RCP 4 (preferentially) or RCP 1 should be run to provide normal PRZR spray.

Spray valves should be closed if the associated RCP 4 or RCP 1 is not running to prevent spray flow leak through non-isolated spray path.

40.

Check at least one RCP

- RUNNING.

40.

IF offsite power is available and at least one ACCW Pump is in

service, THEN:

_a.

Start the RCP Lift Oil Pump.

b.

Verify at Shutdown Panel A PRZR Spray Valves closed:

1-PV-0455B 1-PV-0455C Step 40 continued on next page Printed April 5, 2011 at 12:45

Southern Nuclear Operating Company Nuclear NMP-TR-21 5-F02 sOUTHERN.

Management Exam Question Feedback Version 1.0 COMPANY Form Page 1 of 2 NOTE:

The Comment box should be checked if the question is not worded clearly or contains errors and/or misleading information. The Challenge box should be checked if the question to be reviewed for credit on your exam. Include your name.

Exam

Title:

Vocitle 2011 NRC RO/SRO Examination 4/1/11 Date Exam Administered Submitted By: A. Curtis Jenkins 4/5/11 Date LI Comment Challenge Question Identifier (Complete number example:

52 (RO Exam)

AFW-40201 D08004) LOCT Cycle 3, Question #2)

State the reason for comment or challenge on the question:

The question has no correct answer because for the scenario presented there is no need to maintain condenser vacuum. Procedure 18038 requires the crew to maintain one condensate pump running. Procedure 18038 also requires opening the breakers for MSlVs andBSIVs (step 25); thus, isolating main steam. Therefore, unless auxiliary steam is aligned to the other unit (aux steam is normally out-of-service), there is no need to maintain condensate flow for vacuum maintenance. The scenario presented requires both units to implement procedure 18038; thus, no auxiliary steam for air eiectors on either unit.

Based on the procedure flow path, there is no acceptable answer, it is therefore submitted that this question be removed from the exam.

Operation Management supports this challenge for the reasons stated above.

Challenge Review:

Credit given to the submitter LI YES LI NO Key changed LI YES LI NO LI N/A Submitted for exam bank update LI YES LI NO LI N/A Exam Bank Review:

Comment/Challenge incorporated LI YES LI NO LI N/A Reason for not incorporating:

Southern Nuclear Operating Company I

SOUTHERN Management I

Exam Question Feedback Version 1.0 Nuclear I

NMP-TR-215-F02 I

COMPANY Form I

Page2of2 I

Challenge Approved:

Training Supervisor Date

N/A if challenge does not result in an exam key change

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN PageNumber 8/27/2010 PANELS 19 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTIONS Closing BSIVs by opening 1AD12-03 and 1BDI2-03 will isolate RMW to VCT blender.

The SG ARVs, MSIVs and BSIVs will fail closed when breakers are opened in the following step. This will require secondary pressure control with ARVs using ATTACHMENT E or ATTACHMENT G, or Main Steam Code Safeties.

25.

Trip the following breakers:

BREAKER NO.

LOCATION SIGNIFICATION EQUIPMENT ACTIONS 1BDI2-08 CB-B47

Closes MSIVs

Closes MFIVs

Closes BFIV5 IBD12-03 CB-B47

Closes BSIVs

Closes 1-HV-7760B (RMW to VCT blender)

Closes Head Vent to PRT 1-HV-0442B

Closes Accumulator Vent 1-HV-0943B

Closes Safety Grade Charging 1-HV-0190B IADI2-08 CB-B52

Closes MSIVs

Closes MFIVs

Closes BFIVs 1AD12-03 CB-B52

Closes BSIVs

Closes 1-HV-7760A (RMW to VCT blender)

Closes Head Vent to PRT 1-HV-0442A

Closes Accumulator Vent I -HV-0943A

Closes Safety Grade Charging 1-HV-0190A 1AD1 1-08 CB-B52

Closes SGBD

Isolates Fire Protection to CNMT Printed April 5, 2011 at 12:45

Approved By Procedure Number Rev J. B. Stanley Vogtle Electric Generating Plant 18038-1 32 DateApproved OPERATION FROM REMOTE SHUTDOWN PageNumber 8/27/2010 PANELS 20 of 123 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26.

Transfer switches at SWGR as follows:

_a.

IABO4 (CB B76) Place Transfer switch HS-1ABO4OIB to LOCAL.

_b.

Place HS-1ABO4O1A to CLOSE.

_c.

1A805 (CB 876) Place Transfer switch HS-1ABO5OB to LOCAL.

_d.

Place HS-1ABO5OIA to CLOSE

_e.

1BBO6 (CB B61) Place Transfer switch HS-1BBO6O1B to LOCAL.

_f.

Place HS-1BBO6O1At0 CLOSE g.

1 BBO7 (CB B61) Place Transfer switch HS-1BBO7O1B to LOCAL.

h.

Place HS-1BBO7O1Ato CLOSE i.

1AB15 (AB D105) Place Transfer switch HS-1AB1 501 B to LOCAL.

.j.

Place HS-1AB15O1Ato CLOSE k.

1 BBI 6 (AB207) Place Transfer switch HS-1BBI6O1B to LOCAL.

_l.

Place HS-IBB16O1Ato CLOSE Pdnted April 5, 2011 at 12:45

Southern Nuclear Operating Company Nuclear NMP-TR-21 5-F02 sOUTHERNS.

Management Exam Question Feedback Version 1.0 COMPANY Form Page 1 of 2 NOTE:

The Comment box should be checked if the question is not worded clearly or contains errors and/or misleading information. The Challenge box should be checked if the question to be reviewed for credit on your exam. Include your name.

Exam

Title:

Vogtle 2011 NRC RO/SRO Examination 4/1/11 Date Exam Administered Submitted By: Mackie Sinkler 4/5/11 Date Li Comment Challenge Question Identifier (Complete number example:

66 (RO Exam)

AFW-40201 D08004) LOCT Cycle 3, Question #2)

State the reason for comment or challenge on the question:

This question is at the wrong license level for the ROs and is not linked to iob requirements for both ROs and SROs. (NUREG 1021 Supplement 1, ES-403, D. 1.b.) Question is technically correct for reasons stated in the Answer/Distracter Analysis. However, knowledge of OMOC qualification criteria is not required by either ROs or SROs and ROs are not required to know what events require notification of the OMOC.

NMP-OS-007-001 Section 6.2, Operations Manager On-Call (attached) discusses the qualifications and the notification requirements. The SRO portion that is not a iob assignment or a function of an SRO is to be knowledgeable on the qualifications of the OMOC. The SROs on shift do not check the qualifications of the OMOC. The premise that the SRO knowledge of the OMOC qualification and knowledge is NOT important to protect the health and safety of the public is in error. The OMOC position is not listed in the station Technical Specifications Administration sections or the UFSAR Section 13, Conduct of Operations Qualification. ANSI 181-1971 (station committed to this ANSI Standard) does not list this position or qualification in this document. Therefore, based on the aforementioned, this question is recommended to be deleted from the RO and SRO exam. The qualifications is NOT a SM (SRO) responsibility for the OMOC notification per step 6.2.2.2. OMOC notification is NOT an OATC or UO responsibility per section 5.9 and 5.10 of NMP-06-007.

The_Utility supports this challenge for the reasons stated above.

Operation Management supports this challenge for the reasons stated above.

Challenge Review:

Credit given to the submitter Li YES Li NO Key changed Li YES Li NO Li N/A Submitted for exam bank update Li YES Li NO Li N/A Exam Bank Review:

Comment/Challenge incorporated Li YES Li NO Li N/A Reason for not incorporating:

Southern Nuclear Operating Company SOUTHERN Management I

Exam Question Feedback Version 1.0 1

Nuclear I

j NMP-TR-215-F02 COMPANY Form I

Page 2 of 2

challenge Approved:

Training Supervisor Date

N/A if challenge does not result in an exam key change

for the stored energy within the reactor core. Faced with unexpected or uncertain conditions, operators place the plant in a known, safe condition and do not hesitate to reduce power or shut down the reactor.

6.1.2 Expectations 6.1.2.1 Safety First Safe operation takes precedence over all other considerations. Operators do not hesitate to reduce power or shut down the reactor if nuclear safety is challenged.

Operators recognize degraded conditions that could challenge plant safety or reliability.

Licensed operators comply with Technical Specifications.

Because the need for a time-critical response is infrequent, operators avoid hasty decisions. When faced with time-critical decisions, operators:

Utilize alternate indications to validate information Assume the available indications are valid until proven otherwise Develop contingency actions, if time allows Use all available resources, including people offsite, if necessary Do not proceed in the face of uncertainty Do not allow production or cost to override safety Do not challenge the safe operating envelope 6.1.2.2 Conservative Approach Information is gathered and analyzed from relevant sources in order to clearly define and provide options for resolution of operational concerns. Short and long-term risks, consequences, and the aggregate impact associated with decision options are critically and objectively considered.

When addressing operational concerns, operators implement plans that include contingencies and compensatory measures to maintain or enhance safety. Decision-makers and their roles and responsibilities are clearly identified. Command and control responsibilities are carried out in accordance with approved procedures. The bases for decisions are communicated throughout the organization. The effectiveness of significant operational decision-making is periodically evaluated.

Human performance tools, including team involvement, are used whenever practicable to avoid inappropriate actions when reaching operating decisions.

6.2 Operations Manager On-Call 6.2.1 Standard The on-duty Shift Manager consults with the management team in order to improve the quality of operational decisions. To this end, the on-duty Shift Manager notifies the Operations Manager on Call (OMOC) promptly of significant plant events.

,/

I Southern Nuclear Operating Company SCUTHERN4WS Nuclear j

COMPA Management i

Conduct of Operations I

NMP-OS-007-001 j

SYrW,r1f Instruction Standards and Expectations Version 8.0 Page 6 of 49 6.22 Expectations 6.22.1 OMOC Responsibilities (may be coincident with EP on call functions)

An individual, assigned by the Operations Manager, is on-call to assist the duty Shift Manager in the resolution of problems.

The individual assigned as OMOC for the site is on-call and capable of arriving at the plant promptly if needed, Individuals fulfilling the OMOC function are knowledgeable at the SRO level.

6.2.2.2 OMOC Notification The OMOC serves as a resource for the Shift Manager to use to discuss operational decisions and insights from an Operations Department leadership point of view. The off shift operations leadership may have insights that are not known to the Shift Manager regarding overall plant conditions. The duty Shift Manager should contact the OMOC regarding conditions or events that are deemed to be of interest to management. If in doubt, the duty Shift Manager is encouraged to notify the OMOC.

In addition to notifications required specifically by procedure, the duty Shift Manager notifies OMOC without delay if any of the following occur:

Unplanned Reactor Protection System or Engineered Safeguard Function actuation Personnel injury involving Operations personnel Unplanned entry into a Technical Specification LCO Action Statement of less than 7 days Valid entry into an abnormal or emergency procedure Unplanned plant transient or load reduction Out-of-specification chemistry that could result in significant short term damage (action level 2 or greater)

Significant radiological event Unplanned condition that results in a heightened risk (orange or red)

Any reportable event (e.g., 10 CFR 50.72 or 50.73, environmental event)

Missed technical specification surveillance or test Valid entry into the site Emergency Plan Reactivity incident or event Consequential component mispositioning Significant human performance error involving Operations personnel 6.3 Performance Monitoring 6.3.1 Standard Operations personnel reinforce desired behaviors to optimize individual and team performance.

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