Text

2012-10 Final Written Exam
	ML12353A329
Person / Time
Site:	Cooper
Issue date:	10/30/2012
From:	Vincent Gaddy; Operations Branch IV
To:	;
	laura hurley
References
	Download: ML12353A329 (218)
	v • d • e

ES-401 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: 11-05-2012 Facility/Unit: Cooper Nuclear Station Region: I II III IV Reactor Type: W CE BW GE Start Time: Finish Time:

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

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

Applicants Signature Results Examination Value ____75____ Points Applicants Score __________ Points Applicants Grade __________ Percent

QUESTION: 1 A LOCA is in progress with RHR Pump B as the only source injecting into the RPV. The following conditions exist:

RPV level is -130 inches on the fuel zone instruments and rising at 5 inches/minute.

RHR Loop B injection is 3000 gpm.

RPV pressure is 80 psig and steady.

One minute later RHR-MO-13B, PUMP B TORUS SUCTION closes for unknown reasons.

Assuming all systems operate as designed and no operator actions are taken after RHR-MO-13B closes, what is the plant response?

a. RHR Pump B continues to run.

RPV level begins lowering due to no injection.

b. RHR Pump B trips due to valve closure.

RPV level continues rising at a slower rate due to pressure maintenance injection.

c. RHR Pump B continues to run.

RPV level continues rising at a slower rate due to pressure maintenance injection.

d. RHR Pump B trips due to valve closure.

RPV level begins lowering due to no injection.

QUESTION: 2 24818 RHR Loop B is operating in the Shutdown Cooling (SDC) Mode, when RPV pressure rises to 85 psig.

Which one of the following describes the expected system response?

(Assume all systems being operated from the control room.)

RHR Pump B trips and

a. RHR pump suction valve RHR-MO-15B auto closes, and Inboard Injection valve RHR-MO-25B auto closes.

b. Shutdown Cooling suction valves RHR-MO-17 and RHR-MO-18 auto close, and Inboard Injection valve RHR-MO-25B auto closes.

c. Shutdown Cooling suction valves RHR-MO-17 and RHR-MO-18 auto close, RHR pump suction valve RHR-MO-15B auto closes.

d. Min flow control valve RHR-MO-16B auto opens, and Inboard Injection valve RHR-MO-25B auto closes.

QUESTION: 3 The following conditions exist:

The plant is in MODE 5.

RHRSW Booster Pump A is operating in support of RHR SDC mode.

RPV coolant temperature is 140°F and rising 1°F every 15 minutes.

RHRSW Loop A flow on SW-FI-132A, SW FLOW, is indicating 2500 gpm.

The CRS directs the BOP operator to lower the RPV coolant temperature to 110°F.

The BOP operator places control switch HX-A SW DISCH VLV 89A to the OPEN position.

Simultaneously MCC-K de-energizes.

What is required to lower the RPV coolant temperature to 110°F?

a. Start RHRSW Booster Pump B.

b. Start RHRSW Booster Pump C.

c. Coordinate with an NLO to manually open SW-MO-89A locally.

d. Continue holding the control switch for HX-A SW DISCH VLV 89A until SW-FI-132A is indicating the desired flow.

QUESTION 4 The plant is operating at power and Barton Narrow Range instrument NBI-LIS-101B fails downscale. Subsequently a reactor scram occurs due to a PCIS Group 1 and HPCI starts and initiates in response to RPV level lowering. No operator actions are taken with the HPCI controls.

How does HPCI respond to these conditions?

a. HPCI continues to inject as RPV level goes above 59 inches.

b. HPCI speed lowers to minimum regardless of RPV level.

c. HPCI turbine trips and HPCI-MO-14, STM TO TURB VLV closes.

d. HPCI-MO-16, STM SUPP OUTBD ISOL VLV closes and HPCI speed ramps down to zero.

QUESTION: 5 5630 Core Spray pump A is delivering 2400 gpm as indicated on CS-FI-50A, PUMP FLOW, while operating in the test lineup for surveillance testing. The control room operator raises system flow to 4000 gpm.

How does Core Spray pump operation affect Wide Range Torus level indication (PC-LRPR-1A),

CNTMNT/TORUS PRESS & LVL RCDR, and why?

Wide Range Torus water level indicates . . .

a. higher than actual water level due to higher pressure in the discharge piping of the operating pump.

b. higher than actual water level due to reduced pressure in the suction piping of the operating pump.

c. lower than actual water level due to higher pressure in the discharge piping of the operating pump.

d. lower than actual water level due to reduced pressure in the suction piping of the operating pump.

QUESTION: 6 The plant is operating at rated conditions and the Standby Liquid Control above core plate inner pipe has separated from the bottom core plate. The pipe is now measuring below core plate pressure.

What effect does this condition have on Core Spray line break detection system?

a. CS-DPIS-43A & B indicate approximately -10 psid for BOTH systems.

b. CS-DPIS-43A & B indicate approximately zero for BOTH systems.

c. Core Spray break detection alarms annunciate for BOTH systems.

d. Core Spray break detection alarm annunciates in ONLY ONE Core Spray system.

QUESTION: 7 2194 During a failure to scram condition, the CRS orders both SLC Pumps started. Both SLC Pump control switches are taken to START and the following conditions result:

SLC Pump A trips after running 10 seconds.

Squib Valve 14B fails to fire.

What is the condition of the SLC system?

a. SLC is NOT being injected into the RPV into the RPV due to Squib Valve 14B failing to fire.

b. SLC can be injected into the RPV by SLC Pump B only by manual valve manipulations.

c. SLC is NOT being injected into the RPV because Squib Valves 14A and 14B are in series.

d. SLC is being injected into the RPV because SLC Pump B is discharging to the RPV via Squib Valve 14A.

QUESTION: 8 The plant is operating at 70% power making preparations for surveillance testing. BOTH Main Turbine Stop Valve 1 limit switches fail open causing the Stop Valve to indicate closed but actual Stop Valve position remains unchanged.

The limit switches are now repaired and the contacts are closed.

How does the Reactor Protection System (RPS) respond to both the limit switches opening?

How does the operator restore the Reactor Protection System according to Procedure 2.1.5, Reactor Scram?

The RPS system

a. Channel A de-energizes.

The operator places the REACTOR SCRAM RESET switch to Group 1 and 4, then back to NORM.

b. Channel A de-energizes.

The operator places the REACTOR SCRAM RESET switch to Group 1 and 4, Group 2 and 3, then back to NORM.

c. Channel B de-energizes.

The operator places the REACTOR SCRAM RESET switch to Group 2 and 3, then back to NORM.

d. Channel B de-energizes.

The operator places the REACTOR SCRAM RESET switch to Group 1 and 4, Group 2 and 3, then back to NORM.

QUESTION: 9 24791 A reactor startup is in progress, when a fire completely de-energizes 24/48 VDC Div I Bus.

Which IRMs will still be available for monitoring Reactor power?

a. A, C, E, G

b. B, D, F, H

c. A, B, C, D

d. E, F, G, H

QUESTION: 10 21774 During a Reactor Startup, the following indications were observed;

IRM F indication rose from 50/125 to 122/125 on range 6.

All other IRMs remained at approximately 50/125 on range 6.

All automatic actions took place at their Tech Spec Values.

Following the observations above, the following events occurred;

IRM F indication returned back to 50/125 from 122/125 on range 6.

All other IRMs remained at approximately 50/125 on range 6.

On panel 9-5 the control room operator performed the following actions:

bypassed IRM F.

reset all automatic actions that resulted from the actions of IRM F.

depressed the Panel 9-5 annunciator acknowledge and reset pushbuttons as appropriate.

For this event, what is the status of the Alarms and Alarm Indicating Lights, both on Panel 9-5 and on Panel 9-12? (Exclude the IRM bypass lights)

The alarms on Panel 9-5 are

a. clear; the alarm indicating lights on Panels 9-5 are reset and are NOT illuminated but the ones on Panel 9-12 are NOT reset and still illuminated.

b. clear; the alarm indicating lights on BOTH Panels 9-5 and 9-12 are reset and are NOT illuminated.

c. NOT clear; the alarm indicating lights on Panels 9-5 are reset and are NOT illuminated, but the ones on Panel 9-12 are NOT reset and are still illuminated.

d. NOT clear; the alarm indicating lights on NEITHER Panel 9-5 or 9-12 are reset and are still illuminated.

QUESTION: 11 What is the purpose of the Source Range Monitor (SRM) system?

The SRM system

a. monitors local thermal neutron flux and provides input to the Rod Block Monitor (RBM) system.

b. provides a continuous indication and permanent record of the core bulk thermal power until the Reactor Mode switch is in RUN.

c. monitors the core neutron flux levels and their rate of change during shutdown, refueling, and startup.

d. automatically detects and blocks control rod withdrawal that could violate MCPR limits.

QUESTION: 12 What positions must the associated meter function switches be placed in to allow the control room operator to read the LPRM output for the above illuminated indicating light?

What does the output on the meter face indicate?

One switch pointing to the

a. 1D position and one switch pointing to the COUNT position.

The meter indicates upscale.

b. 1D position and one switch pointing to the COUNT position.

The meter indicates downscale.

c. 1 position and one switch pointing to the D position.

The meter indicates upscale.

d. 1 position and one switch pointing to the D position.

The meter indicates downscale.

QUESTION: 13 Where does RCIC receive its steam supply and into what feedwater (FW) line does it inject?

MS Line FW Line

a. A B

b. C A

c. C B

d. A A

QUESTION: 14 An Automatic Depressurization System (ADS) initiation has occurred, and RPV blowdown is in progress. The following conditions exist:

The initiation signals are still present.

RPV Pressure is 950 psig and lowering.

The control room operator presses and releases the ADS LOGIC A TMR and ADS LOGIC B TMR RESET pushbuttons.

What is the RPV pressure response over the next five minutes?

a. RPV pressure stops lowering while the RESET pushbuttons are depressed and immediately resumes lowering when the RESET pushbuttons are released.

b. RPV pressure stops lowering and continues rising until the safety valves open.

c. RPV pressure stops lowering for 109 seconds, and then resumes lowering.

d. RPV pressure continues lowering without pause.

QUESTION: 15 626 What effect does the tripping of RPS MG Set A EPAs have on the Primary Containment Isolation System?

a. Half Group 1, 2, 3, 6 and 7 isolations.

b. Full Group 1, 2, 3, 6 and 7 isolations.

c. Half Group 1 and 2 isolations.

Full Group 3, 6 and 7 isolations.

d. Half Group 1, 2 and 7 isolations.

Full Group 3 and 6 isolations.

QUESTION: 16 Due to ongoing events, the following are displayed in the control room:

Alarm 9-3-1/C-2, DRYWELL PNEUMATIC HDR LOW PRESSURE VID Display (1029) DRYWELL PNEUMATIC HDR PRESSURE LOW

Alarm 9-3-1/D-2, RELIEF VALVE ACCUMULATOR LOW PRESSURE VID Display (1030) RELIEF VALVE A ACCUMULATOR PRESSURE LOW VID Display (1031) RELIEF VALVE B ACCUMULATOR PRESSURE LOW VID Display (1032) RELIEF VALVE C ACCUMULATOR PRESSURE LOW VID Display (1033) RELIEF VALVE D ACCUMULATOR PRESSURE LOW VID Display (1034) RELIEF VALVE E ACCUMULATOR PRESSURE LOW VID Display (1035) RELIEF VALVE F ACCUMULATOR PRESSURE LOW VID Display (1036) RELIEF VALVE G ACCUMULATOR PRESSURE LOW

The MSIVs are closed.

The reactor is shutdown with pressure at rated conditions. How can the control room operator lower RPV pressure so the Condensate Booster Pumps can inject into the RPV?

a. Close IA-SOV-SPV21, DRYWELL IA SUPPLY VLV from Panel 9-3, and SRV valves are opened with their control switches as needed.

b. Open SRV VALVES 71E, 71F, 71G by placing their Isolation switches to ISOL in the ASD room.

c. Open the main turbine bypass valves in MANUAL mode from an HMI.

d. Open SRV VALVE 71H with its control switch.

QUESTION: 17 The plant is starting up and in MODE 1. SRV testing has been completed satisfactorily and two hours have lapsed. MS-TR-166, MAIN STEAM RELIEF AND SAFETY VALVE LEAK TEMP RECORDER, Channel 5 for Relief/Safety Valve B is indicating 195°F and steady. PMIS Point T143, MS RELIEF VALVE B is indicating 195°F and steady. No control room alarms associated with safety relief valves are present.

What is the condition of SRV B?

a. The valve is leaking.

b. The valve is full open.

c. The tailpipe thermocouple is failed open.

d. The valve is closed and indicating normally.

QUESTION: 18 The plant is starting up and the second Reactor Feed Pump has been placed in service one minute ago. RFPT A and RFPT B are being operated in MDEM mode. Three speed probes for RFPT A turn INVALID and two speed probes for RFPT B turn INVALID.

How are both RFPTs controlled in these conditions? (Assume the control room operator only utilizes the HMI UP/DOWN arrows).

a. RFPT A speed is changed utilizing the HMI UP/DOWN arrows in MDVP.

RFPT B speed is changed utilizing the HMI UP/DOWN arrows in MDVP.

b. RFPT A speed is changed utilizing the HMI UP/DOWN arrows in MDEM.

RFPT B speed is changed utilizing the HMI UP/DOWN arrows in MDVP.

c. RFPT A speed is changed utilizing the HMI UP/DOWN arrows in MDEM.

RFPT B speed is changed utilizing the HMI UP/DOWN arrows in MDEM.

d. RFPT A speed is changed utilizing the HMI UP/DOWN arrows in MDVP.

RFPT B speed is changed utilizing the HMI UP/DOWN arrows in MDEM.

QUESTION: 19 With the plant at power, the following timeline of events/actions occur:

0800 Drywell pressure starts rising.

0805 The control room operator is aligning for venting.

0807 The reactor automatically scrams on high primary containment pressure.

0830 Reactor building pressure is indicating -0.30 inches wg.

How is the SGT system affected by the conditions above?

What does procedure require to be performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of the high primary containment trip signal?

a. SGT continues to vent from primary containment.

Both SGT fan control switches must be placed in OFF and then to STANDBY.

b. SGT vents from the Reactor Building plenum only.

Both SGT fan control switches must be placed in RUN.

c. SGT vents from the Reactor Building plenum only.

The preferred SGT fan control switch must be placed in RUN and the other SGT fan control switch must be placed in OFF and then to STANDBY.

d. SGT continues to vent from primary containment.

The preferred SGT fan control switch must be placed in OFF and then to STANDBY and the other SGT fan control switch must be placed in RUN.

QUESTION: 20 23132 The plant is operating at rated conditions. The Electrical Maintenance department is troubleshooting a relay on 4160VAC critical bus 1F. Troubleshooting activities cause the bus to lockout. The control room operators respond according to alarm procedure guidance.

What condition and action statements of Technical Specifications require entry?

a. TS 3.8.1 AC Sources - Operating only.

b. TS 3.8.2 AC Sources - Shutdown only.

c. TS 3.8.1 AC Sources - Operating and TS 3.8.7 Distribution Systems - Operating.

d. TS 3.8.2 AC Sources - Shutdown and TS 3.8.8 Distribution Systems - Shutdown.

QUESTION: 21 25667 The plant is in a normal full power electrical lineup. The following alarm is received:

C-4/E-7 NO BREAK SYSTEM INVERTER 1A VOLTAGE FAILURE.

The electrical system responds as designed. What is the source of power to the NBPP?

a. MCC-L via a step down transformer and bypassing the inverter cabinet static switch.

b. MCC-L via a step down transformer and the inverter cabinet static switch.

c. MCC-R via a step down transformer and bypassing the inverter cabinet static switch.

d. MCC-R via a step down transformer and the inverter cabinet static switch.

QUESTION: 22 What is the normal power supply to the Main Turbine Emergency Bearing Oil Pump?

a. 125VDC Distribution Panel 1A via 125VDC SWGR 1A.

b. 125VDC Distribution Panel 1B via 125VDC SWGR 1B.

c. 250VDC Turbine Building Starter Rack via 250VDC SWGR 1A.

d. 250VDC Turbine Building Starter Rack via 250VDC SWGR 1B.

QUESTION: 23 The 125VDC Div 1 batteries are being charged after the charger had been removed from service for maintenance. How could plant operations be affected while charging the batteries?

a. Potassium hydroxide could accumulate and corrode battery terminals causing loads on the circuit to become overheated due to resistance to electrical current.

b. Nickel oxide-hydroxide could accumulate and corrode battery terminals causing loads on the circuit to become overheated due to resistance to electrical current.

c. Hydrogen could be generated and an explosive atmosphere could cause detonation and battery damage rendering the batteries inoperable.

d. Arsine could be generated and an explosive atmosphere could cause detonation and battery damage rendering the batteries inoperable.

QUESTION: 24 Diesel Generator 1 automatically starts on a valid signal and is powering 4160V Bus 1F. The following exist:

All DG automatic initiation signals are clear.

4160V Bus 1A is energized.

DG 1 EMERGENCY TO NORMAL RESET is pushed and released.

DG 1 DROOP PARALLEL switch is in PARALLEL.

SYNCH SWITCH is in 1FA.

What indications are procedurally required to be present for the control room operator to transfer 4160V Bus 1F to 4160V Bus 1A?

The synchroscope has to be rotating slowly in the

a. counter-clockwise (SLOW) direction and DG voltage is slightly LOWER than Bus 1A voltage.

b. counter-clockwise (SLOW) direction and DG voltage is slightly HIGHER than Bus 1A voltage.

c. clockwise (FAST) direction and DG voltage is slightly LOWER than Bus 1A voltage.

d. clockwise (FAST) direction and DG voltage is slightly HIGHER than Bus 1A voltage.

QUESTION: 25 7057 What automatic interlock functions on a service air leak to prevent losing all air to the critical components in the Instrument Air (IA) System?

a. IA-SOV-SPV21, DRYWELL IA SUPPLY, receives an open signal to supply the reliable air header.

b. IA-SOV-SPV21, DRYWELL IA SUPPLY, receives a close signal to supply the reliable air header.

c. SA-PCV-609, SERVICE AIR SYSTEM ISOLATION, receives a close signal to isolate the SA System from the IA System.

d. SA-PCV-609, SERVICE AIR SYSTEM ISOLATION, receives a open signal to supply additional air to the IA System.

QUESTION: 26 What is the power supply for each REC pump?

a. 1A and 1B Pumps are powered from MCC-S.

1C and 1D Pumps are powered form MCC-K.

b. 1A and 1B Pumps are powered from MCC-K.

1C and 1D Pumps are powered form MCC-S.

c. 1A and 1B Pumps are powered from MCC-K.

1C and 1D Pumps are powered form MCC-Y.

d. 1A and 1B Pumps are powered from MCC-Q.

1C and 1D Pumps are powered form MCC-S.

QUESTION: 27 Control rod 26-27 is continuously inserted from notch 16 to 12.

What is the minimum drive water flow, indicated on CRD-FI-305 on Panel 9-5, as the control rod moves past notch 14?

a. 2 gpm

b. 4 gpm

c. 6 gpm

d. 8 gpm

QUESTION: 28 How is the Reactor Recirculation seal flow rate controlled?

a. Setting a manual flow regulator between 0.25 and 0.5 gpm.

b. Setting a manual flow regulator between 1.6 and 1.8 gpm.

c. Seal internal orifices regulate flow between 0.25 and 0.5 gpm.

d. Seal internal orifices regulate flow between 1.6 and 1.8 gpm.

QUESTION: 29 5060 What is the reason for ensuring the Reactor Recirculation Pump Discharge Valve Jog Circuit is used when starting a RR Pump above 30% power?

The Discharge Valve Jog Circuit ensures . . .

a. the resultant shrink in Reactor level is within the capability of the Reactor Level Control System.

b. the resultant swell in Reactor level is within the capability of the Reactor Level Control System.

c. the subsequent rise in Reactor power does not exceed the flow biased High Flux scram setpoint.

d. Jet Pump NPSH conditions are maintained as the valve strokes open.

QUESTION: 30 The plant is operating at rated conditions. The flow in the RWCU system piping downstream of RWCU-MO-18, OUTBD ISOL VLV, has reached 195% of rated conditions. No RWCU valve actuations have automatically occurred. All control room attempts to close RWCU valves have failed. Secondary Containment temperatures are rising.

Using the provided Wall Chart, what is the HIGHEST Emergency Action Level (EAL) reached for this condition?

a. An ALERT due to the loss of the Primary Containment Fission Product Barrier.

b. An ALERT due to the loss of the Secondary Containment Fission Product Barrier.

c. A Site Area Emergency due to the loss of the Reactor Coolant System Barrier and Primary Containment Barrier.

d. A Site Area Emergency due to the loss of the Fuel Clad Barrier and Reactor Coolant System Barrier.

QUESTION: 31 1223 A full reactor scram from rated conditions has been initiated. What will be the indication of a control rod that has moved past the full-in position 10 seconds after the scram (assume no operator action is taken)?

Full In Light Four Rod Display

a. ON Blank

b. ON 00

c. OFF Blank

d. OFF 00

QUESTION: 32 Reactor power is 54% and control rod 34-27 is selected for withdrawal. The following occur:

Control rod 34-27 is notched from position 18 to position 22.

Control rod 26-37 is selected.

After control rod withdrawal and the subsequent selection of control rod 26-37, what is the response of Rod Block Monitor A as observed on RBM A meter at Panel 9-14?

AFTER 34-27 AFTER 26-37 MOVEMENT SELECTED

a. 56-58% 54%

b. 102-103% 54%

c. 100% 100%

d. 102-103% 100%

QUESTION: 33 1728 The plant is operating at 75% power with RHR Loop A operating in Suppression Pool Cooling (SPC). A reactor coolant leak develops in the Drywell resulting in the following conditions:

Drywell pressure 3.4 psig and rising slowly

Reactor pressure 700 psig and steady

Reactor water level +36 " (wide range) and steady What is the status of RHR-MO-39A, OUTBOARD SPC VALVE and RHR-MO-66A, HX BYPASS VALVE five (5) minutes later? (Assume NO operator actions taken with RHR Loop A controls).

RHR-MO-39A position RHR-MO-66A position

a. CLOSED OPEN

b. OPEN OPEN

c. CLOSED CLOSED

d. OPEN CLOSED

QUESTION: 34 RHR Pump D is operating and controlling drywell pressure between 2 psig and 10 psig. All systems operate per design. What is the power supply to RHR Pump D at the present time?

a. 4160V Bus 1F via 4160V Bus 1A.

b. 4160V Bus 1G via 4160V Bus 1B.

c. 4160V Bus 1F via the Emergency Station Transformer.

d. 4160V Bus 1G via the Emergency Station Transformer.

QUESTION: 35 93 A plant startup is in progress with the Reactor Mode Switch in RUN. MCC-L de-energizes.

What effect(s) does this have on the Main Steam system?

a. MO-74 (MSL Drain Inboard Isolation) closes.

b. MO-77 (MSL Drain Outboard Isolation) closes.

c. Inboard MSIVs and MO-74 (MSL Drain Inboard Isolation) closes.

d. Outboard MSIVs and MO-77 (MSL Drain Outboard Isolation) closes.

QUESTION: 36 23729 What effect does de-energizing 125 VDC power panel BB-2 have on the main turbine trip logic?

The main turbine . . .

a. CAN be manually tripped from the Control Room AND can be tripped locally. The main turbine automatic electric trips WILL function.

b. CAN be manually tripped from the Control Room AND can be tripped locally. The main turbine automatic electric trips will NOT function.

c. CANNOT be manually tripped from the Control Room, but CAN be tripped locally. The main turbine automatic electric trips WILL function.

d. CANNOT be manually tripped from the Control Room, but CAN be tripped locally. The main turbine automatic electric trips will NOT function.

QUESTION: 37 The plant was operating at rated conditions when the main generator tripped on an NSST fault.

Ten minutes later the following alarm is received:

B-2/C-1, TG EXHAUST HOOD A TEMP HIGH A check of TGI-R-RECCST, CONTROLLED START TEMP, CH 9 - 1ST LP TURBINE EXHAUST, reveals the temperature is 195°F and rising slowly.

How does this condition impact the main turbine?

What operator action is required per alarm B-2/C-1?

a. The high pressure turbine could experience differential expansion and rubbing of the turbine blades on the casing.

If turbine is on turning gear, on HOOD SPRAY screen, TG EXHAUST HOOD A control, verify hood spray operation by verifying DEMAND is > 0%.

b. The high pressure turbine could experience differential expansion and rubbing of the turbine blades on the casing.

Lower condenser backpressure by opening AR-MO-150, VACUUM BREAKER.

c. The low pressure turbine could experience differential expansion and rubbing of the turbine blades on the casing.

If turbine is on turning gear, on HOOD SPRAY screen, TG EXHAUST HOOD A control, verify hood spray operation by verifying DEMAND is > 0%.

d. The low pressure turbine could experience differential expansion and rubbing of the turbine blades on the casing.

Lower condenser backpressure by opening AR-MO-150, VACUUM BREAKER.

QUESTION: 38 21750 How does a loss of Plant Air affect the operation of Secondary containment Isolation valves HV-259AV and HV-261AV, Reactor Building Vent Exhaust Inboard Isolation valves?

A loss of plant air

a. requires both valves to be closed manually if an auto close signal is received.

b. prevents the closing of HV-259AV with its control switch.

c. prevents the closing of HV-261AV from an automatic isolation signal.

d. requires accumulator air as a motive force for closing both valves.

QUESTION: 39 1063 Given the following conditions:

Recirculation Pump B has tripped.

RR-MO-53B, Recirculation Pump B discharge valve was closed and is now open.

LOOP B JET PUMP FLOW (FI-92B) indicates 2 Mlbm/hr.

LOOP A JET PUMP FLOW (FI-92A) indicates 35 Mlbm/hr.

Annunciator 9-4-3/E-7, RECIRC LOOP B OUT OF SERVICE is NOT alarming.

What is the expected value for indicated Total Core Flow as indicated on Panel 9-5 Recorder DPR/FR-95 AND what is Actual Core Flow?

Indicated total Core Flow Actual core flow

a. 33 Mlbm/hr 33 Mlbm/hr

b. 33 Mlbm/hr 37 Mlbm/hr

c. 37 Mlbm/hr 33 Mlbm/hr

d. 37 Mlbm/hr 37 Mlbm/hr

QUESTION: 40 The plant was operating at full power with the Startup Station Transformer (SSST) de-energized for switchyard work. The plant experiences a reactor scram and the electrical systems operate per design. The crew enters Procedure 5.3EMPWR, EMERGENCY POWER DURING MODES 1, 2, OR 3. The crew misses performing step addressing the Main Condensate Pumps and they are in the configuration shown below.

The SSST is repowered. With no manipulation of the above switches, what is the status of the Main Condensate Pumps after the non-critical 4160V buses are re-energized?

a. There is no change to the pumps status as they remained operating throughout the transient.

b. The pump breakers all trip once their respective buses are repowered.

c. The pumps all start with the potential of water hammer damage in the system.

d. The pumps all start with the pumps running deadheaded.

QUESTION: 41 The plant is operating in Mode 1 in a normal system alignment when the control room operator reports that several RCIC MOVs have lost their indicating lights. What could be the cause of this condition?

a. 125VDC SWGR 1A Bus has a blown fuse which supplies the RCIC Starter Rack.

b. 125VDC SWGR 1B Bus has a blown fuse which supplies the RCIC Starter Rack.

c. 125V Charger 1A sustained a DC output over voltage.

d. 125V Charger 1B sustained a DC output over voltage.

QUESTION: 42 The plant is operating at 100% power when the main turbine trips.

What is the immediate reactor water level response to this condition?

a. RPV level rapidly lowers greater than 20 inches.

b. RPV level rapidly rises greater than 10 inches.

c. RPV level slowly lowers to 15 inches.

d. RPV level slowly rises to 54.5 inches.

QUESTION: 43 A reactor scram has just occurred. Procedure 2.1.5, Reactor Scram directs operating the instruments represented by the picture below. What sequence of operator actions are required per Procedures 4.1.1, SRMs and 4.1.2, IRMS?

a. Press POWER ON switch.

Press SRM A through D SELECT switches.

Press IRM A through H SELECT switches.

Press and hold DRIVE IN switch until IN lights all illuminated, then release.

b. Press SRM A through D SELECT switches.

Press IRM A through H SELECT switches.

Press and hold DRIVE IN switch until IN lights all illuminated, then release.

c. Press POWER ON switch.

Press SRM A through D SELECT switches.

Press IRM A through H SELECT switches.

Momentarily press DRIVE IN switch.

d. Press SRM A through D SELECT switches.

Press IRM A through H SELECT switches.

Press POWER ON switch.

Momentarily press DRIVE IN switch.

QUESTION: 44 What is the reason for manually tripping the main turbine during a control room abandonment event?

a. To cause the main turbine bypass valves to open and control RPV pressure throughout the event.

b. To take positive action to trip the turbine without relying on automatic trips.

c. To initiate a reactor scram and place the reactor in a low energy state.

d. To preclude RPV inventory overfill resulting in RFPT trips.

QUESTION: 45 10641 Following a LOCA, HPCI is maintaining RPV level and RHR loop B is in suppression pool cooling. The following annunciators now alarm:

M-1/A-1, REC SYSTEM LOW PRESSURE

M-1/A-3, REC SURGE TANK LOW LEVEL The crew performed the following per Procedure 5.2REC, Loss of REC:

Stopped all the operating REC pumps.

Closed REC-MO-709, DRYWELL RETURN ISOLATION.

Inspected the critical loops and found them intact.

Restarted REC Pump 1A.

The following plant and REC system conditions are now present:

REC critical loop supply pressures are 60 psig and oscillating.

Surge tank level is low out of sight and the level control valve is open.

What REC action is required per 5.2REC?

a. Stop REC pump 1A.

b. Split the critical loops.

c. Start two additional REC pumps.

d. Supply SW backup to REC critical loops.

QUESTION: 46 The plant is operating at power when a partial loss of instrument air occurs. The crew enters Emergency Procedure 5.2AIR, Loss of Instrument Air. The procedure directs the crew to enter Procedure 2.1.5, SCRAM, and close the MSIVs and drains. The procedure also directs the crew to ensure the preferred Standby Gas Treatment system is operating.

Why is the crew directed to ensure the preferred Standby Gas Treatment system is operating?

a. To provide dilution flow to the Elevated Release Point due to the Off-Gas dilution fan running deadheaded.

b. To ensure proper Reactor Building Quad room cooling due to room coolers temperature control valves failing closed.

c. To support Reactor Building Kaman operation due to the loss of building ventilation.

d. It is critical for HPCI operation when adequate core cooling is required.

QUESTION: 47 24838 The Plant is in Mode 4 with RCS temperature at 175°F

RHR Pump B is in service in SDC.

RHR Loop A is out of service for maintenance.

Reactor Recirculation Pumps A and B are out of service for maintenance.

RWCU is in service with 1 pump and 2 filters.

RHR Pump B trips due to a motor failure.

What effect does this have on the RWCU system?

a. RWCU can now provide more core forced circulation inside the shroud.

b. The additional cooling in the downcomer precludes flashing in the RWCU suction.

c. The reactor heat removal rate in the regenerative heat exchanger becomes greater.

d. The reactor heat removal rate in the non-regenerative heat exchanger becomes greater.

QUESTION: 48 A refueling accident has occurred. What is the Standby Gas Treatment system relationship with this event?

a. The trains start when reactor building exhaust radiation levels reach predetermined levels and any subsequent radiation release is through the elevated release point.

b. The trains start when reactor building exhaust radiation levels reach predetermined levels and any subsequent radiation release is through the reactor building exhaust.

c. The trains remain idle and any radiation release is through the elevated release point.

d. The trains remain idle and any radiation release is through the reactor building exhaust.

QUESTION: 49 The plant is operating at rated conditions. A steam leak develops in the drywell. What effect does this have on containment? (Assume no operator actions are taken)

a. Drywell temperature rises and then steadies out when the torus to drywell vacuum breakers open.

b. Suppression pool water temperature continually rises as drywell temperature rises.

c. Torus pressure rises at a faster rate than the drywell because of its relatively smaller size.

d. Torus air space temperature equalizes with drywell temperature.

QUESTION: 50 The Plant is operating at 100% power when a DEH malfunction occurs, causing RPV Pressure to rise to 1122 psig. Assume Drywell Temperature is 100F and Torus pressure is 1.2 psig.

What is the expected SRV tailpipe temperature response of RV71C?

RV71Cs tailpipe temperature starts at approximately

a. 150F and rapidly rises to approximately 300F.

b. 150F and slowly rises to approximately 360F.

c. 220F and rapidly rises to approximately 300F.

d. 220F and rapidly rises to approximately 360F.

QUESTION: 51 5334 An Anticipated Transient Without Scram (ATWS) has occurred. Average Reactor Thermal Power is 15% AND Suppression Pool temperature is 96°F and rising 1°F every 5 minutes.

What is the MAXIMUM temperature the Suppression Pool temperature may reach before Boron injection is required?

a. 110°F.

b. 123°F.

c. 139°F

d. 140°F

QUESTION: 52 23331 A Loss of Coolant Accident has occurred with the following conditions:

Reactor pressure 200 psig (lowering slowly)

Torus pressure 5 psig (rising slowly)

Drywell temperature 400° F (all points) (steady)

RPV water level can no longer be determined.

What action is performed next and why?

a. Spray the Drywell to lower primary containment pressure.

b. Spray the torus to lower primary containment temperature.

c. Flood the RPV because fuel submergence cannot be assured.

d. Flood the RPV because minimum steam cooling pressure is not met.

QUESTION: 53 23333 A LOCA has occurred with the following conditions:

RHR Pump C is the only low pressure ECCS pump available.

Maximum injection is required

Current RHR flow rate 7000 gpm

Torus pressure 9.57 psig (stable)

Torus average water temp 185°F (rising slowly)

Primary containment water level 5 feet (stable)

The CRS directs that NPSH and Vortex requirements be complied with.

What action is required for RHR Pump C and why?

a. Lower flow to 6000 gpm because of NPSH limits.

b. Lower flow to 6000 gpm because of Vortex limits.

c. Raise flow to 7700 gpm as allowed by Vortex limits.

d. Raise flow to 8600 gpm as allowed by NPSH limits.

QUESTION: 54 Given the following conditions:

The plant has experienced a LOCA.

CRD is the only system injecting into the RPV.

All control rods have fully inserted.

RPV pressure is stable at 900 psig utilizing SRVs.

RPV water level has stabilized at -156 inches (Corrected Fuel Zone).

What is the status of core cooling?

a. Adequate core cooling does NOT exist because the core is uncovered.

b. The core is covered so adequate core cooling exists.

c. The core is adequately cooled because Minimum Steam Cooling Pressure conditions exist.

d. Steam cooling is providing adequate core cooling at this RPV level.

QUESTION: 55 The plant is operating at 100% power when the following occur:

Main Generator fault with a Main Turbine trip.

Very little rod motion on the scram.

The crew initiates ARI.

Both RR pumps are tripped.

The Main Turbine Bypass Valves control pressure.

The feedwater system remains in operation.

Current plant conditions are:

Reactor power 15% (stable)

Reactor Pressure 935 psig (stable)

Reactor water level +13"(NR) (stable)

The CRS orders RPV injection stopped and prevented.

Why is stop and prevent injection ordered at this time?

a. To lower reactor water level which mitigates the consequences of thermal-hydraulic instabilities.

b. To prevent uncontrolled injection of large amounts of cold unborated water and fuel damage due to overpower conditions.

c. To prevent injection from sources inside the shroud which cause large power excursions and fuel damage.

d. To raise the subcooling of the cold unborated feedwater injection which lowers reactor power and heat addition to containment.

QUESTION: 56 19785 During the execution of EOP 5A, RADIOACTIVITY RELEASE CONTROL, the CRS directs Emergency Depressurization (ED) to be performed.

What is the basis for Emergency Depressurizing while performing EOP 5A, Radioactive Release Control actions?

a. ED ensures the availability of equipment in the turbine building, which is necessary to mitigate the event, is not challenged.

b. ED ensures the energy level of the radiation and the atmospheric dispersion factors fall within the bounds of the accident analysis.

c. ED ensures the isotopic mixture of radioactive materials deposited off-site will be within the bounds of the EPA Protective Action Guides.

d. ED ensures the lowest possible driving head and flow of primary systems that are discharging outside of containment.

QUESTION: 57 An active electrical fire has been automatically extinguished in the Service Water Pump room.

What class of fire existed and what are the potential hazard(s) associated with entering the Service Water Pump room?

a. Class D fire and the hazard is electrocution due to water deluge discharge.

b. Class C fire and the hazard is electrocution due to water deluge discharge.

c. Class C fire and the hazards are physical symptoms such as dizziness, headache, and confusion due to Halon discharge.

d. Class D fire and the hazards are physical symptoms such as dizziness, headache, and confusion due to Halon discharge.

QUESTION: 58 The plant is operating at 96% power and grid disturbances cause both 4160V 1F and 1G bus voltages to oscillate as follows:

TIME RESPONSE OF Bus 1F & 1G 0800 Dips to 3950V for 7 seconds.

0804 Dips to 3950V for 12 seconds.

0810 Dips to 3850V for 7 seconds.

0813 Dips to 3850V for 12 seconds.

What EOP(s) require entry and what time is the entry required?

a. EOP 1A only at 0800.

b. EOPs 1A and 3A at 0804.

c. EOPs 1A and 3A at 0810.

d. EOP 1A only at 0813.

QUESTION: 59 16653 A plant shutdown is in progress. With the Reactor operating at 19% power (main turbine still on the line), the BOP operator notices that steam pressure to the Steam Jet Air Ejectors is lowering rapidly and subsequently determines that opening the SJAE steam supply bypass valves does not correct the problem.

The crew enters Abnormal Procedure 2.4VAC, LOSS OF CONDENSER VACUUM and vacuum is now 22Hg.

What immediate action(s) is/are required?

a. Perform Rapid Power Reduction per Procedure 2.1.10.

b. Place Mechanical Vacuum Pumps in service per Procedure 2.2.55.

c. Scram the Reactor, then trip the Main Turbine per Procedure 2.1.5.

d. Trip the Main Turbine and enter Procedure 2.2.77.

QUESTION: 60 5425 The plant has been operating at 100% power for the past 90 days following a refueling outage, when the following events occur:

An MSIV isolation occurs for unknown reasons.

The Reactor is shutdown.

RPV Pressure rises to 1090 psig, then lowers to 875 psig.

20 minutes later, pressure is cycling between 990 AND 825 psig.

Which of the following statements describes the status of Low Low Set (LLS)?

a. Neither LLS valve is controlling pressure within its designed range.

b. LLS is correctly controlling pressure with SRV F. SRV D is NOT responding as designed.

c. LLS is correctly controlling pressure with SRV D. SRV F is NOT responding as designed.

d. LLS is correctly controlling pressure with BOTH LLS valves.

QUESTION: 61 The plant is operating at power when RPV level begins to rise. As water level rises, what are the potential consequences to the plant if automatic actions do NOT take place?

a. An elevated water level results in cooler water entering the downcomer causing a significant effect on available NPSH for the RR Pumps.

b. An elevated water level results in a higher water level in the downcomer causing a significant effect on available NPSH for the RR Pumps.

c. RPV level being high enough that moisture carryover causes steam quality to lower and damage to steam driven turbines.

d. RPV level being high enough that moisture carryover causes steam quality to rise and damage to steam driven turbines.

QUESTION: 62 A leak has developed in the drywell. What MINIMUM drywell pressure will cause an automatic reactor scram?

a. 0.6 psig

b. 1.5 psig

c. 1.84 psig

d. 2.0 psig

QUESTION: 63 Power has been raised to 90% after a control rod swap evolution. The control room operator notices SJAE Radiation monitor indication slowly rising. Annunciator 9-4-1/C-4, OFFGAS TIMER INITIATED, alarms 15 minutes later. The CRS enters Procedures 5.2FUEL, FUEL FAILURE and 2.4OG,OFF-GAS ABNORMAL.

What is the appropriate operator action per procedure(s) and why?

a. Scram the reactor and place OFFGAS TIMER switch to CLOSE to contain the radiation release.

b. Lower reactor power to lower the radiation release.

c. Scram the reactor to lower the fission product gap release and lower the radiation release.

d. Lower reactor power and close the MSIVs to contain the radiation release.

QUESTION: 64 24586 Following a LOCA and SCRAM the following conditions are noted:

HPCI high suppression pool water level suction transfer logic is defeated per 5.8.20.

HPCI is injecting at 4000 gpm with suction from the ECST.

Reactor pressure is 650 psig.

Reactor water level is -155 inches (corrected FZ) and steady.

Drywell temperature is 185°F and rising slowly.

Drywell pressure is 4.0 psig and rising slowly.

Torus pressure is 2.6 psig and rising slowly.

Primary Containment water level is 15 ft and rising an inch per minute.

Suppression pool temperature is 120°F and steady.

What action is required?

a. Initiate drywell sprays.

b. Emergency depressurize.

c. Align HPCI suction to the Suppression Pool.

d. Vent primary containment with drywell vent line.

QUESTION: 65 The Reactor Building HVAC is in a normal lineup. Outside temperature is 70°F and winds are steady at 5 miles per hour. The running Reactor Building exhaust fan vortex damper closes.

Per Panel R Annunciator R-2 alarm procedure, when does the Reactor Building exhaust and supply fans trip for the present conditions?

a. Immediately with Reactor Building pressure at -0.45 wg or more negative.

b. After a 45 second time delay with Reactor Building pressure at -0.45 wg or more negative.

c. Immediately with Reactor Building pressure at -0.15 wg or less negative.

d. After a 45 second time delay with Reactor Building pressure at -0.15 wg or less negative.

QUESTION: 66 16476 An RO left shift work on 6/3. The RO worked all scheduled workdays this year as BOP until leaving shift. Since leaving shift, the RO performed the following shifts as the BOP:

7/19 worked 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

8/18 worked 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

8/30 worked 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

9/10 worked 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months What is this operator's license status on 9/11?

a. License is active and only stays active with another 12-hour shift before 10/1.

b. License is active and only stays active with another 12-hour shift before 11/1.

c. License became inactive on 6/30.

d. License became inactive on 7/31.

QUESTION: 67 The plant is operating at power when an unexpected alarm is received.

What information is to be relayed to control room supervision concerning the alarm, according to Procedure 2.3.1, GENERAL ALARM PROCEDURE? (Assume the alarm is a valid alarm)

a. Read or paraphrase the annunciator descriptor only.

b. Report alarm card automatic actions and any referenced TS/TRM/ODAM.

c. Read or paraphrase the annunciator descriptor and any referenced TS/TRM/ODAM.

d. Report the alarm as an unexpected alarm only.

QUESTION: 68 Refueling operations are taking place per Procedure 10.25.1, REFUELING-CORE REFUELING SUPPORT OPERATIONS. A control rod is withdrawn and a bypass jumper for refueling interlocks is installed for the RPIS probe buffer card of the withdrawn control rod.

What indication is available to inform the At the Controls operator the control rods refueling interlocks are bypassed?

a. The Panel 9-5 Full Core Display FULL IN indicating light illuminates and the FULL OUT indicating light extinguishes.

b. The Panel 9-5 Full Core Display FULL IN indicating light extinguishes and the FULL OUT indicating light illuminates.

c. Both Panel 9-5 Full Core Display FULL IN and FULL OUT indicating lights extinguish.

d. Both Panel 9-5 Full Core Display FULL IN and FULL OUT indicating lights illuminate.

QUESTION: 69 16466 During a reactor startup and heatup after a refueling outage, reactor period was infinity after withdrawing a control rod. The following conditions are present with NO control rod movement for the last two (2) minutes:

The reactor is on range 5 of the IRMs (rising)

Reactor period is +120 seconds (getting shorter)

Reactor coolant temperature is 180°F (rising)

What action is required?

a. Insert a manual scram.

b. Range IRMs as necessary to keep them on scale until the Point of Adding Heat (POAH) is reached.

c. Fully insert control rods per the Emergency Power Reduction section of NPP 10.13 until the reactor is subcritical.

d. Wait and see if reactor period shortens to under 50 seconds, then insert the last withdrawn control rod until period is longer than 50 seconds.

QUESTION: 70 The SE Quad fan coil unit is having its belts replaced by maintenance personnel.

Does the Core Spray subsystem have to be declared inoperable? Why or why not?

a. No; support equipment does not need to be maintained in an operable status to maintain the TS Required Equipment Operable.

b. No; if maintenance can return the support system to a functional state, then the TS required equipment can remain Operable.

c. Yes; any work on a support system that is associated with a Technical Specification piece of equipment affects the operability of that system.

d. Yes; the Tech Spec for the SE Quad fan coil unit states that the associated Core Spray System must be declared inoperable.

QUESTION: 71 The plant is operating at power when a leak in the Reactor Building causes a building high radiation alarm. The Rx Bldg HVAC isolates on a valid high radiation signal and 10 minutes later the Reactor Building Vent radiation monitors are all reading 5 mR/hr and steady.

What does EOP 5A, Secondary Containment Control require for building ventilation control?

a. Verify the HVAC isolation valves all closed and then start Standby Gas Treatment system.

b. Install EOP PTMs to override the high radiation signal and then restart Rx Bldg HVAC.

c. Restart the Rx Bldg HVAC and leave Standby Gas Treatment system operating.

d. Verify the radiation levels and then restart Rx Bldg HVAC.

QUESTION: 72 One of the rooms in the Reactor Building contains an area in which a person could receive a deep dose equivalent (DDE) of 1250 mR/hr.

Why is the entrance required to be posted as a Locked High Radiation Area?

a. To preclude 10CFR100, REACTOR SITE CRITERIA, radiation limits from being exceeded.

b. To preclude 10CFR20, STANDARDS FOR PROTECTION AGAINST RADIATION, radiation limits from being exceeded.

c. To ensure CNS Planned Special Exposure (PSE) limits are not exceeded during an accident.

d. To ensure dose to the control room personnel does not exceed federal limits during a fuel handling accident.

QUESTION: 73 5923 What is the basis for requiring boron injection before the Boron Injection Initiation Temperature (BIIT) (Graph 8) is exceeded?

a. Ensures Hot Shutdown Boron weight is injected into the RPV before the Primary Containment Pressure Limit (Graph 11) is exceeded.

b. Ensures Cold Shutdown Boron weight is injected into the RPV before the Heat Capacity Temperature Limit (Graph 7) is exceeded.

c. Ensures Cold Shutdown Boron weight is injected into the RPV before the Primary Containment Pressure Limit (Graph 11) is exceeded.

d. Ensures Hot Shutdown Boron weight is injected into the RPV before the Heat Capacity Temperature Limit (Graph 7) is exceeded.

QUESTION: 74 During EOP actions, the order is given to Stop and Prevent all injection into the RPV. What priority is given when performing the order and why?

Priority is given to the

a. systems that are injecting or about to inject because the objective is to lower RPV water level or prevent a power excursion.

b. systems that are injecting or about to inject because RPV level control would be more difficult in the given level band.

c. highest capacity systems because a rapid cooldown could exceed procedural cooldown rate limitations.

d. low pressure systems because they can rapidly be secured with an individual control switch.

QUESTION: 75 A fire has been confirmed in the Turbine Building. The CRS has entered Procedure 5.1INCIDENT, SITE EMERGENCY INCIDENT. As the control room operator you are directed to announce the fire to station personnel. What are your actions for these conditions?

Sound the Fire Alarm Pulse Tone for ten (10) seconds and direct the

a. Fire Brigade and Utility Fire Brigade to a specific fire locker designated by the control room operator and the Turbine Building NLO to the scene of the fire.

b. Fire Brigade to a specific fire locker designated by the control room operator and the Utility Fire Brigade and Fire Brigade Leader to the location of the fire.

c. Fire Brigade and Utility Fire Brigade to an exterior entrance closest to the fire and the Incident Commander to the scene of the fire.

d. Fire Brigade to a specific fire locker designated by the control room operator; the Utility Fire Brigade to an exterior entrance closest to the fire and the Turbine Building NLO to the scene of the fire.

HANDOUT TABLE OF CONTENTS

1. EAL Matrix Category F

2. EOP NOTE 3, Graph 3 and Graph 5 (NPSH Limits)

3. EOP Graph 4 (Vortex Limits)

4. EOP Graph 7 (Heat Capacity Temperature Limit)

5. EOP Graph 8 (Boron Injection Initiation Temperature)

ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: 11-05-2012 Facility/Unit: Cooper Nuclear Station Region: I II III IV Reactor Type: W CE BW GE Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to complete the combined examination, and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months if you are only taking the SRO portion.

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

Applicants Signature Results RO/SRO-Only/Total Examination Values 75 / 25 / 100 Points Applicants Scores / / Points Applicants Grade / / Percent

QUESTION: 1 A LOCA is in progress with RHR Pump B as the only source injecting into the RPV. The following conditions exist:

RPV level is -130 inches on the fuel zone instruments and rising at 5 inches/minute.

RHR Loop B injection is 3000 gpm.

RPV pressure is 80 psig and steady.

One minute later RHR-MO-13B, PUMP B TORUS SUCTION closes for unknown reasons.

Assuming all systems operate as designed and no operator actions are taken after RHR-MO-13B closes, what is the plant response?

a. RHR Pump B continues to run.

RPV level begins lowering due to no injection.

b. RHR Pump B trips due to valve closure.

RPV level continues rising at a slower rate due to pressure maintenance injection.

c. RHR Pump B continues to run.

RPV level continues rising at a slower rate due to pressure maintenance injection.

d. RHR Pump B trips due to valve closure.

RPV level begins lowering due to no injection.

QUESTION: 2 24818 RHR Loop B is operating in the Shutdown Cooling (SDC) Mode, when RPV pressure rises to 85 psig.

Which one of the following describes the expected system response?

(Assume all systems being operated from the control room.)

RHR Pump B trips and

a. RHR pump suction valve RHR-MO-15B auto closes, and Inboard Injection valve RHR-MO-25B auto closes.

b. Shutdown Cooling suction valves RHR-MO-17 and RHR-MO-18 auto close, and Inboard Injection valve RHR-MO-25B auto closes.

c. Shutdown Cooling suction valves RHR-MO-17 and RHR-MO-18 auto close, RHR pump suction valve RHR-MO-15B auto closes.

d. Min flow control valve RHR-MO-16B auto opens, and Inboard Injection valve RHR-MO-25B auto closes.

QUESTION: 3 The following conditions exist:

The plant is in MODE 5.

RHRSW Booster Pump A is operating in support of RHR SDC mode.

RPV coolant temperature is 140°F and rising 1°F every 15 minutes.

RHRSW Loop A flow on SW-FI-132A, SW FLOW, is indicating 2500 gpm.

The CRS directs the BOP operator to lower the RPV coolant temperature to 110°F.

The BOP operator places control switch HX-A SW DISCH VLV 89A to the OPEN position.

Simultaneously MCC-K de-energizes.