ML030840233

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February 50-325/2003-301 Exam Draft SRO Written Exam
ML030840233
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 09/09/2002
From: Ernstes M
Operator Licensing and Human Performance Branch
To: Keenan J
Carolina Power & Light Co
References
50-324/03-301, 50-325/03-301
Download: ML030840233 (103)


See also: IR 05000325/2003301

Text

Draft Submittal

BRUNSWICK EXAM

50-2003-301

50-325 & 50-324

FEBRUARY 10 - 14 & 19, 2003

Senior Reactor Operator Written Exam

ES-401 Written Examination Forto ES*-401-7

Qualitv Checklist

Facility: *-- -lCTC Date of Exam: I1

1a13 Exmevl l

Initial

Item Description a I c.

1. Questions and answers technically accurate and applicable to facilit /

2. a. NRC WAS referenced for all questions

b. Facility learning objectives referenced as available

3. -per RO/SRO ovedap is no more than 75 percent, and SRO questions are appropriate

Section D.2.d of ES-401

4. Question selection and duplication from the last two NRC licensing exams

appears consistent with a systematic sampling process

as

5. Question duplication from the license screening/audit exam was controlled

indicated below (check the item that applies) and appears appropriate:

the audit exam was systematically and randomly developed; or

___Jhe audit exam was completed before the license exam was started; or

the examinations were developed independently; or

the licensee certifies that there is no duplication; or

other (explain)

Bank use meets limits (no more than 75 BankI Modified.. New

6.

percent from the bank at least 10 percent new,

and the rest modified); enter the actual question 341

distribution at right mo ts"o *' I SW

Between 50 and 60 percent of the questions on Memory C/A

7.

the exam (including 10 new questions) are

written at the comprehension/analysis level; ,

enter the actual question distribution at right Z 57 VN

8. References/handouts provided do not give away answers

9. Question content conforms with specific KJA statements in the previously

approved examination outline and is appropriate for the Tier to which they are

.assigned: deviations .ere justified

10. Question Psychometric quality and format meet ES, Appendix B, Quidelines

11. The exam contains 100, one-point, multiple choice items; the total Is correct and

agrees with value on cover sheet

ebjlDate

Print ame

I-- n wQIase C o" 20

a. Author

b. Facility Reviewer (*N /14

c. NRC Chief Examiner (#)3 ..*,ia, 7 -oc

d. NRC Regional Supervisor ite e-s -z//dol

Note: * The facility reviewer's initials/signature are not applicable for NRC-developed examinations.

  1. Independent NRC reviewer initial items in Column "c;" chief examiner concurrence required.

NUREG-1021, Revision 8, Supplement 1 42 of 46

U.S. Nuclear Regulatory Commission

Site-Specific

Written Examination

Applicant Information

Name: Region: II

Date: 02/19/03 Facility/Unit: Brunswick

License Level: SRO Reactor Type: 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. The passing grade requires a final grade of at least 80.00

percent. Examination papers will be collected six hours after the examination starts.

Applicant Certification

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

Applicant's Signature

Results

Examination Value: Points

Applicant's Score: Points

Applicant's Grade: Percent

Brunswick 2003-301

SRO Inital Exam

1.

During a reactor startup, Control Rod 34-39 is selected to be NOTCHED OUT from

Position 10 to Position 12. The RWM Withdraw Limit is Position 16.

After initiating ROD OUT NOTCH Sequence, the Operator observes:

Full Core Display white select light for Control Rod 34-39 is OFF.

4-Rod Display indicates Control Rod 34-39 STOPPING at Position 14.

Control Rod Select Matrix Backlighting is UNCHANGED

Rod Drift alarm is sealed in

Which ONE of the following has occurred?

A. The RMCS Timer has failed.

B. The RPIS Reed Switch at Position 12 has failed.

C. UPS supply breaker to rod select power has tripped.

D. RWM is enforcing a Withdraw Block.

Brunswick 2003-301

SRO Inital Exam

2.

Which ONE of the following describes the conditions under which the "Rod'Select

Permissive" light is illuminated?

A. REFUEL only and indicates all control rods are fully inserted; rod select power is Off

or rod select power is On with no rod selected.

B. REFUEL only and indicates all control rods are fully inserted except for the selected

rod; rod select power is On with only one rod selected.

C. SHUTDOWN or REFUEL and indicates all control rods are fully inserted; rod select

power is Off or rod select power is On with no rod selected.

D. SHUTDOWN or REFUEL and indicates all control rods are fully inserted except for

the selected rod; rod select power is On with only one rod selected.

Brunswick 2003-301

SRO Inital Exam

3.

Unit Two was 95% power when annunciator A-07 2-2, REACTOR WATER LEVEL

-HIGH/LOW, alarmed. Feed pump "B" Flow Controller is in manual following erratic

operation in automatic. Plant conditions are:

Reactor power 83% lowering

Reactor water level +180 inches rising

Feedwater Flow A 5.3 Mlbs/hr

Feedwater Flow B 0.9 Mlbs/hr

Recirc Pump A Speed 63% lowering

Recirc Pump B Speed 70% lowering

Core Flow 59 Mlbs/hr lowering

Which ONE of the following describe the actions that should be taken?

A. Lock the scoop tube for the 'A' Recirc pump; monitor for Thermal Hydraulic

Instabilities.

B. Lock the scoop tubes of both recirc pumps and then monitor for Thermal Hydraulic

Instabilities.

C. After level is restored, adjust recirc pump potentiometers to match demand and

speed, and reset runback;

D. Take manual control of recirc pump speeds and ensure that a mismatch of greater

than 10% does not occur.

Brunswick 2003-301

SRO Inital Exam

4.

Unit Two (2) is in Mode 1, in an active LCO for Recirculation Pump 2A out of service.

Preparations -are-in progress-to-restart RecirculationPumrp-2A-per OP'02, Reactor

Recirculation System OperatingProcedure. The following data is recorded within 30

minutes of the planned start of Recirculation Pump 2A:

Reactor pressure 985 psig

Bottom head drain temp 410°F

Recirc loop A temp 486 0 F

Recirc loop B temp 522 0 F

Recirc loop B flow 25,800 gpm

Which ONE of the following is correct concerning the restart of Recirculation Pump

2A?

A. It may continue, all requirements are met.

B. It may NOT continue, the Delta T between the operating and the idle loop is

excessive.

C. It may NOT continue, the Delta T between the coolant in the dome and bottom

head is excessive.

D. It may NOT continue, the operating Recirc loop flow rate is excessive.

Brunswick 2003-301

SRO Inital Exam

5.

Unit 2 was at 100% RTP when a small break LOCA concurrent with a loss of all high

pressure makeup capability to the reactor occured. The Reactor is being

depressurized using the SRVs due to level not being able to be maintained above TAF.

All RHR and Core Spray pumps have started as required with normal indications.

Reactor pressure is approximately 400 psig at this time.

Concerning the "A" RHR system only, which ONE of the following describes the

expected sytem parameters and configuration?

A. Both LPCI "A" injection valves OPEN, "A" system flow indicates 0 gpm, "A" and "C"

RHR Pump discharge pressures are approximately 200 psig.

B. Both LPCI injection valves CLOSED, "A" system flow indicates 0 gpm, "A"and "C"

RHR Pump discharge pressures are approximately 200 psig.

C. Both LPCI "A" injection valves OPEN, "A" system flow indicates 12,000 gpm, "A"

and "C" Pump discharge pressures are approximately 400 psig.

D. Both LPCI "A" injection valves CLOSED, "A" system flow indicates 2300 gpm, "A"

and "C" RHR Pump discharge pressures are approximately 200 psig.

Brunswick 2003-301

-SRO Inital Exam

6.

Following a reactor scram the Reactor operator attempts to place the RWCU in the

reject mode-of operation toaidin level-control' -Following the-valve manipulation you

note that: valve G31-F004 has-closed, and the inboard isolation valve G31-FOOl is

opened and you have lost condenser vacuum.

Which ONE of the following could have caused the above?

A. BOTH the Reject to Condenser Valve, F034 AND the Reject to Radwaste Valve,

G31-F035 were opened simultaneously and there was a non-regenerative heat

exchanger high temperature signal.

B. BOTH the Reject to Condenser Valve, F034 AND the Reject to Radwaste Valve,

G31-F035 were closed simultaneously and there was a non-regenerative heat

exchanger high temperature signal.

C. BOTH the Reject to Condenser Valve, F034 AND the Reject to Radwaste Valve,

G31-F035 were opened simultaneously and there was a Local SLC pump start

signal.

D. BOTH the Reject to Condenser Valve, F034 AND the Reject to Radwaste Valve,

G31-F035 were closed simultaneously and there was a Local SLC pump start

signal.

Brunswick 2003-301

SRO Inital Exam

7.

Unit 2 is at 10% power with RWCU filter demin in service and RWCU reject flow in

progress.

Which ONE of the following is correct concerning the PPC heat balance if Process

Computer Point B074, RWCU Inlet Flow, is NOT available?

The PPC heat balance will be:

A. up to 3 CMWT lower than actual reactor power because computer points only get

input from RWCU filter demin flow.

B. up to 6 CMWT lower than actual reactor power because computer points only get

input from RWCU temperature.

C. up to 3 CMWT higher than actual reactor power because computer points only get

input from RWCU filter demin flow.

D. up to 6 CMWT higher than actual reactor power because computer points only get

input from RWCU temperature.

Brunswick 2003-301

-SRO Inital Exam

8.

Which ONE of the following components prevents water from being forced up the HPCI

exhaust line as the-suppression-pobl pressurizestduring a-LOCA?

A. HPCI exhaust line vacuum breakers.

B. HPCI exhaust line T-quencher.

C. HPCI exhaust isolation valve.

D. HPCI exhaust drain pot.

Brunswick 2003-301

SRO Inital Exam

9.

With Unit 1 operating at rated conditions and Unit 2 at 75% power, Unit 2 annunciator

A3 2M6; CORE SPRAY SYS 2 LOGIC PWR FAILURE, is received. Investigation

reveals a tripped circuit breaker in Panel 4B which powers CORE SPRAY SYS 2

LOGIC.

Which ONE of the following describes the effect this has on a subsequent Unit 2 LOCA

initiation?

A. DIV I1Emergency diesel generators will not auto start.

B. DIV II Non Interruptible RNA isolation valve will not isolate and DIV II N2 BU

isolation valve will not open.

C. Drywell coolers B and C will not trip.

D. DIV II RHR pumps will not auto start.

Brunswick 2003-301

SRO Inital Exam

10.

Which ONE of the following contains a correct list of indications that are used to verify

the Standby Liquid Control System is operating properlyonce the system has been

-- initiated? (Not necessarfly-all-the indications) . ..

A. Squib valve loss of continuity alarm annunciated, storage tank level decreasing,

discharge pressure slightly lower than reactor pressure.

B. Red light indicating pump is running, reactor water level will increase, squib valve

status lights are illuminated.

C. Storage tank level decreasing, RWCU suction valve G31-F004 opens, squib valve

status lights are extinguished.

D. Indicated SLC pump discharge pressure will increase to greater than reactor

pressure, squib valve status lights are extinguished, RWCU suction valve G31-FO04

closes.

Brunswick 2003-301

SRO Inital Exam

11.

Unit two is operating at 100% power when there is a loss of 125 VDC distribution panel

4B on the Unit 2 Reactor Protection System.

Which ONE of the following describes the direct effect of this loss on the RPS?

A. All ARI valves fail open, venting the scram air header.

B. Outboard ARI valves fail open, venting the scram air header through the inboard

ARI bypass check valves.

C. Both backup scram valves remain as is, scram air header remains pressurized.

D. Upstream backup scram valve fails open, venting the scram air header through the

downstream backup scram valves bypass check valve.

Brunswick 2003-301

SRO Inital Exam

12.

Which ONE of the following explains why a "ROD DRIFT" alarm is received after

---novinga-control rod using the "EMERGENCY IN"switch?

A. "EMERGENCY IN" bypasses the Rod Position Indication System.

B. The sequence timer is bypassed causing an insert and withdraw signal at the same

time.

C. The rod is at an even reed switch and none of the selected relay busses are

energized (insert, withdraw or settle).

D. The rod is at an odd reed switch and none of the selected relay busses are

energized (insert, withdraw or settle).

Brunswick 2003-301

SRO Inital Exam

13.

Unit 1 is in the process of performing OGP-01, PrestartupChecklist step 6.2.9, Source

Range-MonitorChecks.

Which ONE of the following describes the minimum requirements for the SRM's?

A. Ensure at least 2 SRM channels are OPERABLE and indicate > 5 cps.

B. Ensure at least 2 SRM channels are OPERABLE and indicate > 10 cps.

C. Ensure at least 3 SRM channels are OPERABLE and indicate > 5 cps.

D. Ensure at least 3 SRM channels are OPERABLE and indicate > 10 cps.

Brunswick 2003-301

SRO Inital Exam

14.

Unit I is in Mode 2 with the Mode Switch in START/HOT STBY. Annunciator APP

A-05 2-2,-ROD OUTBLOCK, is in alarm- -APRM readings are as follows:

--.

APRMI 1 13%

APRM 2 Downscale

APRM 3 15%

APRM 4 14%

Which ONE of the following describes the effect on the plant for these conditions and

the reason for the response?

A. A scram should have occurred due to APRM 2 being Downscale and APRM 3 at

the Upscale Trip setpoint.

B. A 1/2 scram should have occurred on RPS Channel A due to APRM 3 at the

Upscale Trip setpoint.

C. A 1/2 scram should have occurred on RPS Channel B due to APRM 2 being

downscale.

D. The ROD OUT BLOCK alarm is the only expected actuation due to the position of

the Mode Switch.

Brunswick 2003-301

SRO Inital Exam

15.

Ifthe Topaz Inverter in Analog Trip Cabinet XU-68 (RPS B-2) had an open circuit and

failed, then-which ONE of the following should occur?

A. There will be no interruption of power to cabinet XU-68 as the power supply in

XU-67 (RIPS B-I) will provide power to both cabinets.

B. There will be no interruption of power to cabinet XU-68 as there is a second Topaz

Inverter in panel XU-68 that is in parallel with the Topaz Inverter that failed.

C. All associated instruments will lose power generating a trip signal. There will be a

1/2 scram and Group 1 PCIS as well as valve actuation for PCIS Groups 2, 6 and 8.

D. All associated instruments will lose power but will not generate any trip signals. The

plant will continue to operate, but Tech Specs should be addressed for each

instrument.

Brunswick 2003-301

SRO Inital Exam

16.

Which ONE of the following is correct concerning the RCIC Steam Supply Inboard

- Isolation-Valve (E51 F007)?..

A. AC powered due to less likely to spark during operation and more reliable in a

hostile environment.

B. DC powered due to less likely to spark during operation and more reliable in a

hostile environment.

C. Cannot be powered from an Alternate Safe Shutdown Feeder since the valve is

normally in the Open position.

D. May be throttled closed or open if isolation signal is not present to slowly warm the

RCIC steam line.

Brunswick 2003-301

SRO Inital Exam

17.

Unit 2 is operating at 80% RTP. The RCIC system is in standby with a suction from the

CST. The quarterly HPCI flow rate test is in progress and is taking longer than

expected. Torus level has reached -24" and preparations are being made to pump the

torus down to normal level within the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Tech Spec time limit.

Which ONE of the following describes the effect high Torus level had on RCIC?

A. No effect since the RCIC suction valves do not transfer on high torus level.

B. The Torus suction valves (F029 & F031) received an open signal and once both

valves were full open then the CST suction valve (FO10) received a closed signal.

C. The Torus suction valves (F029 & F031) received an open signal at the same time

the CST suction valve (FO10) received a closed signal.

D. The CST suction valve (F010) received a closed signal and when it was full closed

then the Torus suction valves (F029 & F031) received an open signal.

Brunswick 2003-301

SRO Inital Exam

18.

Unit Two just entered a shutdown LCO due to HPCI and RCIC being inop, when a

- Losof-Off-site Power occurs. EDGs 3 and 4 fail to start. Unit One buses El and E2

remain energized throughout the event. Pressure is being maintained 800 - 1000 psig

using SRVs. Level has been below 45 inches for 5 minutes and is currently +25 on the

N026's.

Assuming ADS was NOT inhibited, which ONE of the following describes how ADS

would respond to #4 EDG starting?

7 ADS valves would auto open _ seconds after the diesel tied to E4.

A. 10

B. 15

C. 83

D. 93

Brunswick 2003-301

SRO Inital Exam

19.

Unit Two is in RHR/LPCI suppression pool cooling mode with an elevated suppression

pool temperature-of 180 OF-.- The VITAL Servkice WaterHeader supply valve was

-inadvertantly closed.-The valve-was manually-opened 10 minutes later

Which ONE of the following occurred before the valve was reopened?

A. ONLY RHR Pump Seal temperatures increased.

B. ONLY RHR SW Pump Motor temperatures increased.

C. BOTH RHR Pump Seal temperatures and RHR SW Pump Motor temperatures

increased.

D. NEITHER RHR Pump Seal temperatures NOR RHR SW Pump Motor

temperatures all have increased.

Brunswick 2003-301

SRO Inital Exam

20.

Following a LOCA, Unit Two has been Emergency Depressurized during a high power

ATWS-andtaillcontrol rods are now fully inserted. Anjection-with the only available

-- injection systems (2A Core Spray, and B Loop RHR)-has been-maximized to raise RPV

level and adequate core cooling is assured.

Plant conditions are:

Torus Pressure 19 psig, slowly lowering

Torus Level -5.5 feet, slowly lowering

Torus Water Temp., 220 OF, steady

Drywell Avg. Temp. 287 OF, lowering

Reactor Level -35 ", rapidly rising

Reactor Pressure 50 psig

The operating crew should do which ONE of the following per Emergency Operating

Procedures?

A. Continue with maximum injection until above the top of active fuel.

B. Secure the B Loop of RHR and continue to raise level with the 2A Core

Spray Pump.

C. Reduce injection flow from Core Spray to maintain the minimum containment

cooling requirements.

D. Secure the 2A Core Spray Pump and continue to raise level with the B Loop of

RHR.

Brunswick 2003-301

SRO Inital Exam

21.

Unit 2 was in an extended shutdown. A startup has been conducted and reactor power

---is at 47%. A position indicator for one-ofthe-Suppression Chamber-to-Drywell Vacuum

-Breakers indicates-hat-the-vacuum-breaker-is-OP-EN. -Alternate vacuum breaker

position indication is not available.

Which ONE of the following statements is correct?

A. Continued operation is allowed as long as the other vacuum breakers indicate

closed and the containment differential pressure test is proven acceptable within 4

hours.

B. Begin a normal reactor shutdown within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Be in HOT SHUTDOWN within

the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Initiate repairs to the vacuum breaker to restore the breaker to

operation prior to restart.

C. Immediately begin a plant shutdown and cooldown. Be in HOT SHUTDOWN within

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Initiate repairs to

restore the vacuum breaker to operation.

D. Initiate a manual reactor scram. Conduct a drywell entry to initiate repairs to the

vacuum breaker as soon as possible. If repairs are not completed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />,

place the plant in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Brunswick 2003-301

SRO Inital Exam

22.

An Instrument Tech mistakenly throttles the bypass valves on an MSIV's hydraulic

-dash pot.

Which ONE of the following describes the effect of this manipulation?

It will result in a change in:

A. closing torque.

B. packing leakage.

C. closing time.

D. closing setpoint.

Brunswick 2003-301

SRO Inital Exam

23.

U-2 RCIC System is running with the following conditions present 10 minutes after the

event:

Reactor Water Level -38 inches

Drywell Pressure +1.5 psig

Suppression Chamber Ambient Temp. 170OF

RCIC Steam Line pressure 900 psig

RCIC Emergency Area Cooler Temp I 00OF and rising slowly

An operator has been sent to the RCIC room and reports that there is a small steam

leak on the line upstream of the Trip and Throttle valve. The Shift Supervisor orders

the Reactor Operator to manually isolate RCIC.

Which ONE of the following describes the effect on RCIC when the manual isolation

pushbutton is depressed?

A. Inboard and Outboard Steam Supply Isolation valves F007 and F008 close and the

RCIC turbine trips.

B. Inboard Steam Supply Isolation valve F007 closes and the RCIC turbine trips.

C. Outboard Steam Supply Isolation valve F008 closes and the RCIC turbine trips.

D. No effect on RCIC since the system should already be isolated.

Brunswick 2003-301

SRO Inital Exam

24. Unit I was

operating at 100%, when a loss of EHC caused a turbine trip without

typass valves. SRVs operated as required, and pressure crested at 1142 psig.

Disregarding the setpoint drift tolerance, which ONE of the following indicates how

many SRVs opened in response to the pressure transient?

A. 4

B. 7

C. 8

D. 11

Brunswick 2003-301

SRO Inital Exam

25.

During an overpressure transient, an operator has opened an SRV to control pressure.

RPV pressure is 1005 psig.

Which ONE of the following is the expected tail pipe temperature for the SRV that is

open, as indicated on ERFIS?

A. 212 OF

B. 300 OF

C. 350 OF

D. 545 OF

Brunswick 2003-301

-SRO Inital Exam

26.

Unit 2 is holding load at 75% Reactor Power when the operator receives the "Turbine

Vacuum Low" alarm. - - . ....

Which ONE of the following describes the expected sequence of actions as condenser

vacuum continues to decrease from 24.7" Hg Vac (alarm setpoint) to 0" Hg Vac?

A. 1st - Main Turbine trips.

2nd - Main Turbine Bypass Valves close.

3rd - MSIV's close.

B. 1st - MSIV's close.

2nd - Main Turbine trips.

3rd - Main Turbine Bypass Valves close.

C. 1st - Main Turbine trips.

2nd - MSIV's close.

3rd - Main Turbine Bypass Valves close.

D. 1st - Main Turbine Bypass Valves close.

2nd - MSIV's close.

3rd - Main Turbine trips.

Brunswick 2003-301

SRO Inital Exam

27.

Assume the Unit 2 Main Generator is operating with the following conditions:

- 800 MWe

- 400 MVARS out

- 60 psig Hydrogen Pressure

To facilitate an on-line adjustment to the Hydrogen Sealing system the Hydrogen

pressure is lowered to 48 psig.

Which ONE of the following describes the effect on the Main Generator?

A. Main Generator operation will be unaffected.

B. Main Generator armature will begin to overheat.

C. Main Generator armature core end will begin to overheat.

D. Main Generator field windings will begin to overheat.

Brunswick 2003-301

SRO Inital Exam

28.

Unit One and Unit Two are operating at 100% power. The following annunciators are

received on Unit One.

UA-13 3-9 SAT Fault Pressure

UA-13 1-9 SAT Lockout

Which ONE of the following describes which Condensate Transfer Pump(s) will have

power?

A. Unit One only.

B. Unit Two only.

C. Both Unit One and Unit Two.

D. Neither Unit One nor Unit Two.

Brunswick 2003-301

SRO Inital Exam

29.

Unit One is at 100% power with Feedwater level control (FWLC) in 3 ELEM and the

Reactor Water Level Select Switch in LEVEL A (NO04A).

Which ONE of the following describes how the DFWLC system will respond to the B

level instrument (N0O4B) failing high?

A. Transfer to 1 ELEMENT and utilize the C level instrument (NO04C) for

level control.

B. Remain in 3 ELEMENT control and continue utilizing the A level

instrument (NO04A) for level control.

C. Transfer to 1 ELEMENT control and continue utilizing the A level

instrument (NO04A) for level control.

D. Remain in 3 ELEMENT and utilize the C level instrument (NO04C) for

level control.

Brunswick 2003-301

SRO Inital Exam

30.

Which ONE of the following describes the effect that a loss of SBGT would have on the

RCIC and HPCI systems?

A. There would be no effect since the SBGT system is not connected to HPCI or

RCIC.

B. Both the RCIC Barometric Condenser and the HPCI Vacuum Pump Discharge line

would be effected.

C. Only the RCIC Barometric Condenser would be effected.

D. Only the HPCI Vacuum Pump Discharge line would be effected.

Brunswick 2003-301

SRO Inital Exam

31.

The following conditions exist on Unit 2:

Reactor Power 50%

Stator Water Coolant Pumps A/B De-energized 3 minutes ago

Rapid power reduction In-progress for 3 minutes

Generator output 400 MWe

Stator amps 9800 A

Turbine Bypass Valves CLOSED

Which ONE of the following describes how the plant would respond if all four of the

Unit 2 incoming 230 KV lines were suddenly lost?

A. A turbine trip due to failure to meet runback criteria, and a reactor scram.

B. A generator load reject will occur but the reactor will stay on line.

C. A generator load reject causes a TCV fast closure and a reactor scram.

D. A TCV fast closure causes an APRM setdown and an SRI initiation, but the reactor

will stay on line.

Brunswick 2003-301

-SRO Inital Exam

32.

Unit One is operating at 100% and the following annunciators are received:

GEN LOSS OF EXC (UA-13 3-1)

VOLT BALANCE RELAY A OPERATION (UA-23 6-6)

GENERATOR AUTO TRIP TO MANUAL (UA-13 1-4)

Which ONE of the following describes the plant response to these conditions?

A. The generator remains on line and the voltage regulator will maintain generator field

voltage constant.

B. A generator lockout is received with a turbine trip. Four EDGs AUTO start and a

reactor scram occurs.

C. The generator remains on line. The voltage regulator will maintain generator

terminal voltage constant.

D. A generator lockout is received with a turbine trip. No EDGs AUTO start and a

reactor scram occurs.

Brunswick 2003-301

SRO Inital Exam

33.

Which ONE of the following is the power supply to the Outboard MSIV's DC solenoids

on Unit One (1)?

A. Div 1 Switchboard 21A.

B. Div 2 Switchboard 22B.

C. Div I Switchboard IA.

D. Div 2 Switchboard I B.

Brunswick 2003-301

SRO Inital Exam

34

During an ATWS on Unit T"wo(2), RPV level is being controlled at Top of Active Fuel

(TAF).

Actions to terminate and prevent RHR injection have been completed. A fault on Bus

2C results in LOSS of Bus E4.

Which ONE of the following describe the RHR pump response as DG4 re-energizes

bus E4?

A. RHR pumps 2B and 2D both remain overridden off.

B. RHR pumps 2B and 2D both restart 10 seconds later.

C. RHR pump 2D restarts10 seconds later, RHR pump 2B remains off.

D. RHR pump 2B restarts 10 seconds later, RHR pump 2D remains off.

Brunswick 2003-301

SRO Inital Exam

35.

Unit 2 experiences a Loss of Off-Site Power (LOOP) with EDG #4 under clearance.

Which ONE of the following describes how the Nuclear Service Water (NSW) and

Conventional Service Water (CSW) pumps will respond as EDG #3 output breaker

closes and energizes bus E3?

A. NSW pump 2A and CSW pump 2A start immediately.

B. NSW pump 2A starts immediately and CSW pump 2A does not start.

C. NSW pump 2A and CSW pump 2A start after a 5 second time delay.

D. NSW pump 2A starts after a 5 second time delay and CSW pump 2A does not

start.

Brunswick 2003-301

SRO Inital Exam

36.

During a radwaste discharge to the Unit One weir, a Radwaste Effluent RAD Hi Hi

alarm annunciates. Which one of the following describe the actions, if any, that must

be taken if you desire to close both Unit's Radwaste Discharge valves (D12-V27A and

D12-V27B) and the Radwaste Flow Control valve (G16-FCV-189)?

A. Valves D12-V27A, D12-V27B, and G16-FCV-189 must be closed manually, no

auto signal.

B. Valves D12-V27A and D12-V27B receive a close signal. Valve FCV-189 must be

manually closed, no auto signal.

C. Valve FCV-189 receives a close signal. D12-V27A and D12-V27B must be

manually closed, no auto signal.

D. No actions required, all three valves receive a close signal.

Brunswick 2003-301

SRO Inital Exam

37.

During Unit One operation at 100% power, the control operator is performing

0PT-04.1.7, Main Condenser Air Ejector Radiation Monitor Functional Test. The

-backpanel-operator places-the "A" Steam-Jet Air Ejector (SJAE)-rad monitor NUMAC

drawer (D12-RM-K601A) "INOP/OPER" keylock switch to the "INOP" position.

Which one of the following is the expected plant response?

A. AOG bypass valve, HCV-1 02, immediately closes ONLY.

B. AOG bypass valve, HCV-1 02, immediately closes AND main condenser vacuum

begins to degrade.

C. PROCESS OFFGAS RAD MONITOR DOWNSCALE/INOP alarm is received and

the process offgas timer initiates.

D. PROCESS OFFGAS RAD MONITOR DOWNSCALE/INOP alarm is received and

the process offgas timer does NOT initiate.

Brunswick 2003-301

SRO Inital Exam

38.

You are the Shift Supervisor on Unit 1. Following a LOCA, plant conditions are:

-- Reactor water-leve[-- -....- - +200-inches -....

Drywell pressure 28 psig

Rx Bldg Vent Radiation 12 mR/hr

Primary Containment H20 2 Cannot be determined

You direct a containment purge using the CAD system. The CAC DIV I and DIV II

Isolation (Soft) Override Switches and the CAC Purge Vent Isolation (Hard) Override

Switch, CAC-CS-5519, are placed in OVERRIDE.

The CAC isolation valves that you directed opened earlier are still under override to

OPEN, but have closed automatically.

Which ONE of the following caused this to occur?

A. Reactor water level has dropped an additional 50 inches.

B. Main stack radiation has risen to the Hi-Hi setpoint.

C. Reactor Building ventilation radiation has increased by an additional 8 mR/hr.

D. Reactor Building ventilation exhaust temperature has risen to 140 OF.

Brunswick 2003-301

SRO Inital Exam

39.

Unit 2 is in single loop operation at 45% RTP. Preparations are being made to restart

the idle Recirculation Pump. The Control Operator reduces the operating Recirc Pump

--speed-so that-core flow is less that 40%-rated core-flow prior to-starting-the idle Recirc

Pump.

Which ONE of the following describes the affect on the plant if this condition is

maintained for an extended period of time?

A. The operating recirc pump seals may be damaged due to operating at the lower

pump speed.

B. Thermal hydraulic instabilities may develop due to the increased natural circulation

at the lower core flow.

C. The bottom head temperature will increase due to increased natural circulation at

the lower core flow.

D. The idle loop temperature may decrease such that the 50 OF differential

temperature limit between the operating loop and idle loop is exceeded.

Brunswick 2003-301

SRO Inital Exam

40.

The reactor is at 30% power. Which ONE of the following describes the impact on

continued plant operation during a complete loss of the-Conventional Service Water

--system?--

A. The plant should commence a shutdown immediately due to loss of cooling water to

all of the ECCS Room coolers.

B. The plant should commence a shutdown immediately due to loss of cooling to the

RBCCW Heat Exchangers.

C. The plant should reduce power as necessary to maintain equipment operating that

is supplied by TBCCW.

D. The reactor must be scrammed due to imminent loss of condenser vacuum.

Brunswick 2003-301

SRO Inital Exam

41.

Which ONE of the following describes why the Main Turbine automatically trips on

lowering condenser vacuum?

A. Lowering condenser vacuum decreases the NPSH to the condensate pumps and

the turbine is tripped to prevent a loss of feedwater to the reactor due to the

Condensate pumps tripping on low suction pressure.

B. Lowering condenser vacuum reduces the amount of energy that can be removed

from steam entering the turbine which causes increased dynamic loading on the

last stage blades and increases turbine vibration.

C. The turbine is tripped on lowering condenser vacuum to prevent a steam leak into

Secondary Containment due to a positive pressure occurring within the condenser

and rupturing the turbine casing overpressure discs.

D. The turbine is tripped on lowering condenser vacuum to prevent damage to the

turbine shaft due to increased torque from trying to push the steam through the

turbine.

Brunswick 2003-301

SRO Inital Exam

42.

A LOCA has occurred on Unit 1 which requires the El Emergency Bus to be supplied

by-Diesel Generator #1... ..

Which ONE of the following describes the sequence of events that prevents the Diesel

Generator from being overloaded?

A. Bus El load shed occurs and then the following pumps start in the given order at 5

second intervals: RHR pump IC, Core Spray pump 1A, NSW pump IA.

B. Bus El load shed occurs and then the following pumps start in the given order at 5

second intervals: NSW pump 1A, RHR pump 1C, Core Spray pump 1A.

C. Bus El sheds all loads except RHR pump 1C and then the following pumps start in

the given order at 5 second intervals: Core Spray pump 1A and NSW pump 1A.

D. Bus El sheds all loads except Core Spray pump 1A and then the following pumps

start in the given order at 5 second intervals: RHR pump 1C and NSW pump IA.

Brunswick 2003-301

SRO Inital Exam

43.

During a Station Blackout, RPV cooldown is in progress on the Blacked Out Unit with

the following RPV pressures recorded at the indicated times:

0100 540 psig

0115 420 psig

0130 300 psig

0145 210 psig

0200 150 psig

Per AOP-36.2, the cooldown rate is:

A. satisfactory but the cooldown must be stopped.

B. satisfactory and the cooldown should be continued.

C. too low and the coodown rate should be increased.

D. excessively high and the cooldown rate should be lowered.

Brunswick 2003-301

SRO Inital Exam

44.

The following conditions exist on Unit 1:

- HPCI system will not auto initiate, HPCI flow controller indication is lost.

- B logic is lost for the ADS system.

- RCIC will not trip on Hi water level and the inboard isolation logic is lost.

- Core Spray Loop A will not auto initiate.

- Inboard MSIV DC solenoids de-energize.

Which ONE of the following 125 VDC Distribution Panels was lost?

A. 3A.

B. 11A.

C. 1XDA.

D. 1XDB.

Brunswick 2003-301

SRO Inital Exam

45.

Unit 2 was operating at 100% RTP when the reactor scrammed due to a turbine trip.

In addition to the Turbine Stop Valves closing, which ONE of the following correctly

describes the remaining turbine valve response?

A. Turbine Control Valves Closed

Intercept Valves Closed

Intermediate Stop Valves Open

Bypass Valves - One or more may be open depending on throttle

pressure

B. Turbine Control Valves - Open

Intercept Valves - Closed

Intermediate Stop Valves - Closed

Bypass Valves All open initially; throttle closed to control Rx pressure.

C. Turbine Control Valves - Closed

Intercept Valves - Open

Intermediate Stop Valves - Closed

Bypass Valves - One or more may be open depending on throttle

pressure

D. Turbine Control Valves - Closed

Intercept Valves - Closed

Intermediate Stop Valves - Closed

Bypass Valves - All open initially; throttle closed to control Rx pressure.

Brunswick 2003-301

SRO Inital Exam

46.

The following conditions exist on Unit 2:

-

.Reactor-power----- 23%---

Reactor water level 160 inches

Reactor pressure 980 psig

Drywell pressure 1.3 psig

Drywell temperature 145 OF

Reactor Bldg Vent Exhaust Rad Monitor 2.5 mR/hr

Main Steam Line Rad Monitor 1.3 times normal full power reading

Which ONE of the following indicates which EOP's should be entered at this time?

A. EOP-01-LPC, Level/Power Control;

EOP-03-SCCP, Secondary Containment Control Procedure.

B. EOP-01-LPC, Level/Power Control ONLY.

C. EOP-01-RVCP, Reactor Vessel Control Procedure ONLY.

D. EOP-01-RVCP, Reactor Vessel Control Procedure;

EOP-04-RRCP, Radioactivity Release Control Procedure.

Brunswick 2003-301

SRO Inital Exam

47.

Unit Two has inserted a manual Reactor scram due to lowering condenser vacuum.

Control rods failed to insert on the scram. Plant conditions:

Reactor power 31%

Steam flow 3.2 Mlbm/hr.

Reactor pressure 960 psig, controlled by EHC

Drywell pressure 0.6 psig

Mode Switch RUN

Main Turbine Tripped on low vacuum

The operator is performing LEP-02, Section 3 to reset and scram the Reactor.

Jumpers to bypass RPS trip signals have been requested but NOT yet installed.

Which ONE of the following would prevent the operator from resetting RPS prior to

jumper installation?

A. Scram discharge volume Hi Hi level RPS trip sealed in.

B. Turbine stop valves closed with reactor power above 30%.

C. Reactor water level is controlling at the setdown setpoint.

D. IRMs upscale Hi Hi due to being inserted but not ranged up.

Brunswick 2003-301

SRO Inital Exam

48.

Unit 2 is operating at 80% power when INBOARD MSIV B21-F022A fails closed.

Which ONE of the following describes the effect on Reactor Pressure and Pressure

Averaging Manifold (PAM) Pressure after conditions stabilized, relative to the 80%

power?

A. Reactor pressure would have increased, and PAM Pressure would have increased.

B. Reactor pressure would have remained the same, and PAM Pressure would have

increased.

C. Reactor pressure would have increased, and PAM Pressure would have remained

the same.

D. Reactor pressure would have remained the same, and PAM Pressure would have

remained the same.

Brunswick 2003-301

SRO Inital Exam

49.

Which ONE of the following is the reason the Reactor Feed Pumps are required by

Technical Specifications to automatically trip on high reactor water level?

A. Tripping the feedwater pumps prevents vessel level from exceeding the high level

trip setpoints for HPCI and RCIC only, so that they remain available if necessary.

B. Tripping the feedwater pumps prevent damage to the feedwater pump turbines by

limiting water addition to the vessel.

C. Tripping the feedwater pump turbines limits further vessel level increase thereby

terminating the overfeed event.

D. Tripping the feedwater pump turbines limits further vessel level increase and is the

only means of preventing water from entering the main turbine.

Brunswick 2003-301

SRO Inital Exam

50.

Which ONE of the following is the basis for lowering RPV water level during an ATWS

condition?

A. Reduces reactor power by reducing the natural circulation driving head.

B. Reduces steam generation rate which reduces the moderator temperature.

C. Prevents thermal stratification which prevents localized power peaks.

D. Reduces reactor pressure which allows more injection from low pressure systems.

Brunswick 2003-301

SRO Inital Exam

51.

Reactor water level has just dropped suddenly to 158 inches. Control rod position

indications are unavailable. APRMs are down scale and periods indicate -80 seconds.

Which one of the following describes correct EOP pathway(s) that must be executed?

A. Enter RSP then go to RVCP.

B. Enter RSP then go to L/PC.

C. Enter L/PC then go to RVCP and execute RC/L and RC/P concurrently.

D. Enter RVCP then execute L/PC, RC/L and RC/P concurrently.

Brunswick 2003-301

SRO Inital Exam

52.

The following conditions exist on Unit 1:

Drywell pressure 2.0 psig

Drywell temperature 180 OF

Reactor water level +55 inches

Reactor pressure 400 psig

Drywell Cooler Overide Switch position NORMAL

Which ONE of the following describes the condition of the Drywell Cooler fans?

A. All cooling fans are tripped.

B. Div I cooling fans tripped, Div IIcooling fans running.

C. Div I cooling fans running, Div IIcooling fans tripped.

D. All cooling fans running.

Brunswick 2003-301

SRO Inital Exam

53.

A DBA LOCA has occurred on Unit 2 and the following conditions exist:

Drywell Pressure 62 psig and increasing at 2 psig/min

Reactor Water Level -20 inches and increasing at 10 "min with RHR pumps

Average Drywell Temp 280 OF

PC Water Level 20 ft and increasing slowly

Which ONE of the following should be ordered by the Shift Supervisor?

A. Vent the Torus. Do not exceed ODCM limits for radiological release rates.

B. Vent the Drywell IRRESPECTIVE of offsite radiological release rates.

C. Spray the Drywell after verifying within Drywell Spray Initiation Limit.

D. Enter the Severe Accident Guidelines (SAG's).

Brunswick 2003-301

SRO Inital Exam

54.

Following a reactor scram, drywell temperature is 225 OF. Which ONE of the following

describes the position of the MIN/MAX control switch on Panel XU-3 for the Drywell

Lower Vent dampers, the reason it is in that position, and the actual damper position?

Assume NO operator actions:

A. MIN position so that the Reactor Building Closed Cooling Water system is not

overloaded. Dampers will actually be in the MIN position.

B. MAX position to minimize DP between the torus and the drywell. Dampers will

actually be in the MIN position.

C. MIN position to prevent extreme temperature excursions in the upper drywell

regions during normal operation. Dampers will actually be in the MAX position.

D. MAX position to maximize drywell cooling AND to distribute the air flow in all

portions of the drywell evenly. Dampers will actually be in the MAX position.

Brunswick 2003-301

SRO Inital Exam

55.

During Unit 1 operation at rated power, annunciator A-03 1-1, SAFETY OR DEPRESS

VLV LEAKING was received. SRV sonics indicate the valve is OPEN. A check of the

Suppression Pool parameters -indicate-an average- temperature of 93 OF with a steady,

rising trend.

Which one of the following describe the actions that should be immediately taken?

A. Cycle the control switch of the affected SRV to OPEN and CLOSE/AUTO several

times while maintaining Suppression Pool temperature below 110 OF.

B. Commence a reactor shutdown per OGP-05 and perform an inspection of the

drywell and suppression pool in the area of the failed SRV prior to startup.

C. Manually scram the reactor and enter EOP-01 and OAOP-14.0 due to the

increasing Suppression Pool temperature from the stuck open SRV.

D. Commence a reactor shutdown per OGP-05 and place RHR Suppression Pool

Cooling in service as required.

Brunswick 2003-301

SRO Inital Exam

56.

Unit 1 has been operating at 75% RTP with a leaking Safety/Relief valve (the valve is

still OPERABLE). This has caused the local Suppression Pool temperature in the area

Saround-the -T-quencher-to-reach - 1-1RF.-T-he-average-Suppression Pool -temperature is

steady at 93 0 F.

Which ONE of the following describes the effect, if any, on continued plant operation?

A. The Tech Spec limit for Suppression Pool average temperature has been '

exceeded. Average temperature must be lowered to < 90 OF within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B. No TS limit has been exceeded. However, Supression Pool Cooling MUST be

placed in service to restore the T-quencher to < 110 OF.

C. The Suppression Pool temperature Tech Spec limit of 110 OF has been exceeded.

The reactor must be scrammed immediately.

D. No TS limit has been exceeded.

Brunswick 2003-301

SRO Inital Exam

57.

During a Unit 2 main turbine trip, reactor pressure peaked at 1145 psig and reactor

water level lowered to 125 inches. While responding to the transient, the reactor

operator reports both Reactor Recirculation pumps are running. He is directed to trip

both pumps. Which one of the following is the basis for these actions?

A. Add negative reactivity counteracting the positive reactivity addition resulting from

the pressure rise during the turbine trip ONLY.

B. Promote level swell in the reactor vessel counteracting the level shrink effects

caused by the turbine trip ONLY.

C. Add negative reactivity counteracting the positive reactivity addition resulting from

the pressure rise AND promote level swell in the reactor vessel counteracting the

level shrink effects caused by the turbine trip.

D. Protect the recirculation pumps from inadequate NPSH due to the level shrink

caused by the turbine trip.

Brunswick 2003-301

SRO Inital Exam

58.

Which ONE of the following describes the Abnormal Operating Occurances (Plant

Transients) which increase fuel temperature?

A. Recirc Flow Control Failure-Increasing Flow, Loss of Feedwater Heating,

Inadvertent start of HPCI.

B. Loss of Shutdown Cooling, Loss of Condenser Vacuum, Recirc Flow Control

Failure-Decreasing Flow.

C. Loss of Feedwater Heating, Trip of one Recirc Pump, Startup of idle Recirc Pump.

D. Recirc Flow Control Failure-Increasing Flow, Loss of Condenser Vacuum, Turbine

Trip with Bypass Valves available.

Brunswick 2003-301

SRO Inital Exam

59.

Which ONE of the following describes the reason a cooldown is NOT initiated prior to

the Cold Shutdown Boron Weight (CSBW) being injected during an ATWS condition?

A. The cooldown will cause an increase in reactor power which will require more boron

to be injected to maintain the reactor in an analyzed condition.

B. Initiating a cooldown while injecting boron is an uncontrolled reactivity manipulation

and it will prevent the boron from being uniformly mixed.

C. Core reactivity response is unpredictable in a partially borated core and subsequent

EOP steps may not provide the correct actions for such conditions.

D. Cooldown is not allowed at this time to ensure that low pressure injection systems

cannot inject into the vessel and add positive reactivity.

Brunswick 2003-301

SRO Inital Exam

60.

A chlorine tank car rupture has made the Control Room inaccessable. If possible, prior

to-leaving the-Control Room-the Control Operator inserts a manual Scram per

OAOP-32.0, PLANT SHUTDOWN FROM OUTSIDE CONTROL ROOM.

Which ONE of the following describes why the procedure also has steps to Scram the

reactor by de-energizing the RPS EPA's?

A. The Technical Requirements Manual requires the capability to Scram the reactor

from outside the Control Room.

B. The Technical Specifications require that Reactor Scram capability from outside the

Control Room be maintained.

C. The FSAR requires the ability for prompt hot shutdown of the reactor from locations

outside the Control Room.

D. The capability for prompt hot shutdown of the reactor from outside the Control

Room is not required but is a safe operating practice.

Brunswick 2003-301

SRO Inital Exam

61.

Fuel bundles are being moved in the Unit 1 Fuel Pool when alarm UA-03 3-5,

PROCESS-RX-BL-DG. VENT-IPAD HPtHl isreceived-ollowed by a-report that an

irradiated fuel assembly has been dropped and damaged. The Control Operator notes

that the Reactor Building ventilation failed to isolate on Unit 1 and manual actions to

close the isolation valves have been unsuccessful. Radiation levels at the site

boundary have started to increase.

Which ONE of the following is an immediate operator action for these conditions per

OAOP-05.0, Radioactive Spills, High Radiation, High Airborne Activity?

A. Ensure the Control Room Emergency Ventilation System (CREVS) is in operation.

B. Notify E&RC to perform surveys, post the area and control access to the affected

area.

C. Evacuate unnecessary personnel from the affected area.

D. Stop all fuel movements.

Brunswick 2003-301

SRO Inital Exam

62.

The Unit 2 Reactor Instrument Air Non-Interruptible/Pneumatic Nitrogen Supply

(RNA/PNS) header pressure-has-dropped to7O psig--.

Which ONE of the following describes the effect this will have on the Inboard MSIV's?

A. The Inboard MSIV's will not be affected due to the Backup Nitrogen valves SV-5481

and SV-5482 opening.

B. The Inboard MSIV's should not be affected due to the accumulators associated with

the valve operators.

C. The Inboard MSIV's may start drifting closed due to a sustained low header

pressure.

D. The Inboard MSIV's will close immediately after RNA/PNS header pressure drops

below 80 psig.

Brunswick 2003-301

SRO Inital Exam

63.

A partial Group 2 isolation has just occurred on Unit 2.

Which ONE of the following conditions initiated the isolation?

A. Drywell pressure at 1.5 psig.

B. Reference leg leaks that lower reference leg pressure for Reactor Vessel Water

Level LL#1 transmitters, LT-NO17C-1 and LT-NO17D-1.

C. A variable leg leak that lowers variable leg pressure for Reactor Vessel Water Level

LL#1 transmitters, LT-NO17A-1 and LT-NOI 7B-1.

D. Drywell temperature at 155 OF.

Brunswick 2003-301

SRO Inital Exam

64.

Which ONE of the following indications is used to monitor plant heatup/cooldown rate

while in Alternate Shutdown Cooling with the SRVs?

A. Recirculation loop suction line temperature.

B. Safety relief valve tailpipe temperature.

C. Steam dome pressure using steam table conversion.

D. The running ECCS pump local suction temperature.

Brunswick 2003-301

SRO Inital Exam

65.

Unit I is in Mode 4 with Shutdown Cooling established with the A Loop of RHR. Both

Recirc Pumps are out of service at this time. A spurious signal has caused a Group 8


isolation which-cannot be reset--Reactor vessel water level has been raised to +210".

Which ONE of the following describes the the most accurate method for determing if a

Mode Change has occurred under these conditions?

A. Verifying that the bottom head temperature is less than 212 OF ensures the Unit has

Mode 3.

not entered

B. Verifying that the recirc loop suction temperatures are less than 212 OF ensures the

Unit has not entered Mode 3.

C. Verifying an increasing trend in reactor pressure has not been established ensures

the Unit has not entered Mode 3.

D. Verifying reactor vessel level has been raised to > 200" ensures natural circulation

has been established and the Unit has not entered Mode 3.

Brunswick 2003-301

SRO Inital Exam

66.

The Unit I Control Operator is walking down his panels when he notices that the CRD

Flow Control Valve controller,CI -FC-R600 has failed such that the demand is 0 gpm.

Flow Control Valve C1 1-FO02A was in automatic at 60 gpm prior to the failure.

Which ONE of the following describes how Flow Control Valve C1 1-FO02A can be

controlled under these conditions?

A. The Flow Control Valve will continue to operate at 60 gpm due to the local controller

taking over control automatically.

B. The Flow Control Valve will close until local controller C11 -FK-DO09A is taken to

manual and adjusted as necessary.

C. The Flow Control Valve will fully open until local controller C11 -FK-DO09A is taken

to manual and adjusted as necessary.

D. The Flow Control Valve will close and cannot be operated until controller

C1 1-FC-R600 is repaired.

Brunswick 2003-301

SRO Inital Exam

67.

Unit 2 is in Mode 5 with the fuel pool gates removed. Fuel Handlers are verifying the

Refueling-Interlocks after maintenance on the-refuel bridge. 2A Core Spray pump is

-..running-for-a-flow rate-surveillance-whenthe-operator-inadvertently opens the Core

Spray Injection Valve F005B. (Assume F004B is open)

Which ONE of the following describes the effect on the plant under these conditions?

A. Fuel Pool water level will fill the skimmer surge tanks and cause the Fuel Pool

Cooling Pumps to trip on high level.

B. Reactor cavity water will drain to Radwaste through adjustable weirs located around

the cavity walls.

C. Fuel Pool water level will overflow into the Reactor Building Ventilation system.

D. Fuel Pool water level will rise to the high level alarm setpoint at which time the Fuel

Pool Cooling Pumps will trip.

Brunswick 2003-301

SRO Inital Exam

68.

Which ONE of the following describes why Drywell Sprays are not initiated until

- Suppression Chamber pressure reaches 11.5 psig?..

A. This ensures that Suppression Chamber sprays are attempted before operation of

Drywell sprays.

B. This ensures that 100% of the non-condensibles are in the Suppression Chamber.

C. This prevents opening of the Suppression Chamber to Drywell vacuum breakers

when sprays are initiated.

D. This prevents opening of the Reactor Building to Suppression Chamber vacuum

breakers when Drywell sprays are initiated in a 100% steam atmosphere.

Brunswick 2003-301

SRO Inital Exam

69.

Unit I was operating at 80% RTP when a loss of feedwater heating occurred.

Which ONE of the following describes the effect on the main turbine controls provided

no operator action is taken?

PAM (Throttle) Pressure will and send a signal to the Control Valves to

A. increase, close

B. increase, open

C. decrease, close

D. decrease, open

Brunswick 2003-301

SRO Inital Exam

70.

Which ONE of the following conditions would require entry in the Emergency Operating

-Procedures? .

A. Unit 1 Reactor Water Level at +168 inches following a Reactor Feed Pump trip.

B. Unit 2 HPCI flow rate test in progress and Suppression Pool temperature at 102 OF.

C. Unit 1 Reactor Pressure at 1065 psig following a spurious Group I isolation.

D. Units 1 and 2 in Mode 4 with new fuel being moved into Unit 2 fuel pool and

Reactor Building pressure cannot be maintained negative.

Brunswick 2003-301

SRO Inital Exam

71.

Unit 2 is operating at 100% RTP. The HPCI system is currently running for an

OPERABLILTY flow test after maintenance has been performed. The Control

Operator notes-that Suppression-Pool-temperature is-96-°F.

Which ONE of the following indicates the event status and the color code displayed by

the Safety System Parameter Display System (SPDS) with regards to the Suppression

Pool temperature?

Event Status = __; Color Code=

A. Safe; Green.

B. Caution; Yellow.

C. Alarm; Red.

D. Inactive; Cyan.

Brunswick 2003-301

SRO Inital Exam

72.

Unit 2 was operating at 100% RTP when a LOCA occurred. Water level is being

maintained above TAF with the HPCI system. The following conditions exist in the

Drywell:

Drywell pressure 8.0 psig

Suppression Chamber pressure 7.5 psig

Drywell temperature 275 OF

Reactor pressure 700 psig

Suppression Chamber sprays in progress

Which ONE of the following describes the effect on the indicated water level?

Assume the fuel zone level instrument reference leg piping height is longer than the

variable leg piping height in the Drywell.

A. Level indication will be reading lower than actual water level due to the reference

leg having more water in it.

B. Level indication will be reading lower than actual water level due to Drywell

temperature being above 212 OF.

C. Level indication will be reading higher than actual water level due to Drywell

temperature being above 212 OF.

D. Level indication will still read accurate level since the high Drywell temperature

affects both the reference and variable legs equally.

Brunswick 2003-301

SRO Inital Exam

73.

Unit 2 has developed an unisolable leak on the ECCS Suction header. Suppression

Pool level continues to lower. .

Which ONE of the following corresponds to the minimum level at which the HPCI

System must be isolated irrespective of adequate core cooling?

A. -2 feet and 7 inches

B. -5 feet and 6 inches

C. -6 feet and 5 inches

D. -9.0 feet

Brunswick 2003-301

SRO Inital Exam

74.

Unit 2 experienced a scram due to the loss of the Reactor Feedwater Pumps. Reactor

water-level initially dropped to +90 inches and has been restored to +150 inches and

increasing slowly. The following conditions are present at this time:

HPCI system currently injecting

RCIC system in Standy alignment

Secondary Containment isolated

SBGT system operating normally

Group 2 isolated

Group 3 RWCU system in operation

Group 6 isolated

Group 8 isolated

Which ONE of the following describes the actions that should be taken at this time?

A. Continue to monitor HPCI operation and restore reactor water level to the normal

band. RCIC operation is not required.

B. Start RCIC manually and then secure HPCI. Increase reactor water level to the

normal operating band. All required PCIS Group isolations have occurred.

C. Reset the Group 2 isolation immediately to prevent high drywell pressure and

continue to monitor HPCI while restoring reactor water level to the normal band.

D. Isolate the RWCU System, start RCIC manually, if possible, and continue to

monitor reactor water level to ensure the normal operating band is obtained.

Brunswick 2003-301

SRO Inital Exam

75.

Secondary Containment Control Procedure, EOP-03-SCCP, requires Emergency

Depressurization if 2 or more areas exceed the Maximum Safe Operating Temperature

and a primary system is discharging reactor coolant into secondary containment.

Which ONE of the following statements explain the reason for this action?

A. The rise in secondary containment parameters indicate a wide-spread problem

which may pose a potential threat to secondary containment integrity or preclude

personnel access required for the safe operation of the plant.

B. The rise in secondary containment parameters indicate substantial degredation of

the primary system and may lead to fuel failure if the leaks are not isolated.

C. The rise in secondary containment parameters indicate a wide-spread problem

which may pose a direct and immediate threat to secondary containment integrity or

equipment located in secondary containment.

D. The rise in secondary containment parameters indicate substantial degredation of

the primary system and emergency depressurization effectively isolates the leak.

Brunswick 2003-301

SRO Inital Exam

76.

Unit 2 is operating at 50% RTP when alarm AREA RAD RX BLDG HIGH annunciates.

Upon investigation the operator notes that the alarm is received from the Spent Fuel

Cooling System (Channel 30) which is reading 95 mR/HR. Reactor Building Exhaust

Radiation levels are 2 mR/HR with the system unisolated. The Equipment Operator

reports that the Fuel Pool Heat Exchanger is leaking approximately 50 gpm from the

end bell.

Which ONE of the following describes the actions required for this situation?

A. Isolate all systems discharging into the area except those required to shutdown the

reactor, assure adequate core cooling, or suppress a fire.

B. Emergency Depressurize the reactor per the RC/P section of EOP-01.

C. Shutdown the reactor by manual scram or GP-05 as directed by the SRO.

D. Perform actions required by the Annunciator Response procedure since an entry

condition to the EOP's does not exist.

Brunswick 2003-301

SRO Inital Exam

77.

Unit I is operating at 100% RTP when a high radiation condition occurs in the Reactor

Building. The following conditions exist in the Reactor Building:

Reactor Buidling Supply and Exhaust Fans tripped

Both SBGT trains running

Reactor Building vent isolation dampers (BFIVs) open

Reactor Building Dp zero

Which ONE of the following describes the impact on the plant due to the above

conditions?

A. An elevated release of radioactivity from the main stack could occur.

B. A release of radioactivity outside containment will NOT occur due to both SBGT

trains running.

C. A release of radioactivity outside containment will NOT occur since the Reactor

Building Supply and Exhaust fans have tripped.

D. A ground level release of radioactivity could occur.

Brunswick 2003-301

SRO Inital Exam

78.

Unit 2 has scrammed due to low reactor water level. Multiple control rods did not insert

and the ATWS-procedure is being directed by the-Shift Supervisor. Current power

-level following-the ATWS is 12%RTP. The Shift Supervisor-has ordered the RO to

insert control rods by increasing CRD cooling water differential pressure (dp).

Which ONE of the following describes how this action causes control rods to insert?

Increased cooling water dp:

A. puts additional pressure on the underside of the CRDM drive pistons.

B. puts additional pressure on the top of the CRDM drive pistons.

C. causes driving flow to increase.

D. causes driving flow to decrease.

Brunswick 2003-301

SRO Inital Exam

79.

Unit 2 is executing EOP-04, Radiation Release Control Procedure. During the release,

the radiation-level has exceeded the ALERT Emergency level. The crew is directed to

restart the Turbine Building Air Filtration Unit. Which one of the following is the reason

for this action?

To ensure:

A. any release to the Turbine Building can be routed through Standby Gas Treatment.

B. any release to the Turbine Building is exhausted via an elevated release path.

C. that the integrity of the Turbine Building is maintained.

D. that accessibility to the Turbine Building is preserved.

Brunswick 2003-301

SRO Inital Exam

80.

A loss of the Interruptible Instrument Air System has just occurred.

Which ONE-of-the-following-describe-how-the-Reactor-Feed Pump (RFP) recirculation

valves and Startup Level Control Valve (SULCV) will be affected?

The RFP recirculation valves:

A. and the SULCV fail open.

B. and the SULCV fail closed.

C. fail open and the SULCV fails closed.

D. fail closed and the SULCV fails open.

Brunswick 2003-301

SRO Inital Exam

81.

Unit One is in shutdown. You are reviewing a proposed special test of a Circulating

Water Ocean Discharge (CWOD) Pump. The test has the Caswell Beach Local

Control Panel control switch placed in the STOP position. The next step requires that

an operator place the LOCAL/REMOTE control switch for the operating CWOD Pump

in the LOCAL position.

Which ONE of the following describes the consequences of this action?

This will initiate:

A. pump discharge valve closure with a pump trip when the discharge valve is less

than 50% open.

B. pump discharge valve closure with a pump trip when the discharge valve is less

than 90% open.

C. an immediate pump trip due to undervoltage but will NOT close pump the discharge

valve.

D. an immediate pump trip due to undervoltage and will close the pump discharge

valve.

Brunswick 2003-301

SRO Inital Exam

82.

Unit 1 experienced a LOCA with the following conditions present:

__Drywellpressure - - -85-psig - - .

Drywell temperature 255 OF

Reactor water level +100 inches

Hydrogen concentration Unknown

No operator action has been taken up to this point.

Which ONE of the following describes the method for monitoring containment

Hydrogen concentration in accordance with EOP-02-PCCP?

A. Notify E&RC to coordinate with Chemistry to obtain containment atmosphere

samples manually. Hydrogen monitors are isolated and cannot be overridden.

B. Place CAC Div 1/11 AC ISOL OVRD switches, CS-4178 and CS-4179, to the

Override position and re-open the CAM sample valves. Depress the "Sample Start"

pushbutton.

C. Place CAM Div 1/11 ISOL OVRD switches, CS-2986 and CS-3452, to the "ON"

position. Place associated valve control switches to "close" and then to "open".

Depress the "Sample Start" pushbutton.

D. The containment is not required to be sampled for Hydrogen concentration unless

reactor water level drops below Top of Active Fuel (TAF).

Brunswick 2003-301

SRO Inital Exam

83.

Which ONE of the following conditions will cause the Control Room ventilation system

to enterinto-Fire Protection mode? ....

A. Smoke detected in Unit 2 Electronic Equipment room.

B. Smoke detected in the Unit 1 Electronic Equipment room AND the manual pull

station tripped in the Unit 2 Electronic Equipment Room.

C. Manual pull station tripped in Unit 1 Electronic Equipment room.

D. Manual pull station tripped in Unit 2 Cable Spread room.

Brunswick 2003-301

SRO Inital Exam

84.

Ifoperating in the Scram Avoidance Region of the Flow Control Operational Map,

which one of the following will reduce the likelihood of an instability event?

A. Control rod withdrawal.

B. Reducing recirculation flow.

C. Increasing recirculation flow.

D. Removing a feedwater heater string from service.

Brunswick 2003-301

SRO Inital Exam

85.

Which ONE of the following changes in plant operating conditions will result in a higher

MCPR operating limit as specified in the COLR?

A. Operation at the end of cycle vs. the beginning of cycle.

B. Operation at 90% power vs. 100% power for a given core flow.

C. Operation at 100% core flow vs. 90% core flow for a given power.

D. Setting the mechanical stop of the Reactor Recirculation Pumps to a lower setpoint.

Brunswick 2003-301

SRO Inital Exam

86.

Unit 2 is operating at 14% power with the Drywell de-inerted for mechanical

Smaintenance-to repacka valve.-When exiting the Primary Containment Air Lock the

outer door was damaged such that the door cannot be closed at this time.

Which ONE of the following describes the actions that are required?

A. The Inner Air Lock door must be verified closed and locked. Be in MODE 3 within

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

B. The Inner Air Lock door must be verified closed and locked. Operation may

continue until the next overall airlock leakage test provided the operable door is

verified locked every 31 days.

C. Either door must be verified closed. Action must be initiated to verify overall

containment leakage immediately. The Primary Containment Air Lock door must be

restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D. The Inner Air Lock door must be verified closed and locked. The outer door must

have a security guard posted or must be blocked to prevent entry. Repair the

inoperable door within 31 days or be in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Brunswick 2003-301

SRO Inital Exam

87.

Which ONE of the following describes why the plant must be placed in HOT

SHUTDOWN with an inoperable jet pump?

A. There is an increased possibility of thermal hydraulic instabilities outside the

defined region.

B. An inoperable jet pump is sufficient reason to declare the recirculation loop

inoperable.

C. Blowdown area is increased or reflood capability eliminated in the event of a DBA.

D. To prevent undue stress on the reactor vessel nozzles and in the bottom head

region.

Brunswick 2003-301

SRO Inital Exam

88.

You are the SCO and have just given interim approval of a temporary procedure

change.-

Which ONE of the following describes the expiration date?

The date shall not to exceed:

A. 14 days from the interim approval date.

B. 14 days from the procedure's periodic review date.

C. 4 months from the interim approval date.

D. 4 months from the procedure's periodic review date.

Brunswick 2003-301

SRO Inital Exam

89.

You are the Unit 2 SS. During movement of material through the HPCI Room,

insulation has been damaged. A repair crew has been assembled.

The wet-bulb temperature is 103.1 OF

The work requires single cotton Blend PCs.

The work will take 2 man hours.

You have 3 mechanics plus an HP available.

Assume that HP will not participate in the repairs and that the actual exposure time to

the hot environment is the actual stay time.

Using the recommended action times of OAI-1 07, which ONE of the following is the

shortest duration for this task?

A. 20 minutes

B. 35 minutes

C. 80 minutes

D. 100 minutes

Brunswick 2003-301

SRO Inital Exam

90.

You are the refueling floor SRO. Unit I is in refueling with all but four assemblies off

loaded.

Supplemental Spent Fuel Pool Cooling System is operating as follows:

Primary Pump P-74A and both heat exchangers are in service

Secondary pump P-82A and both cooling towers are in service

P-82A tripped due to a flexible coupling failure. Following the trip P-74A also tripped.

Which ONE of the following conditions must be satisfied prior to restarting P-74A?

A. Secondary loop pressure must be restored.

B. Primary pump seal water must be restored.

C. One heat exchanger must be taken out of service.

D. One fire pump must be started and aligned to the supplemental cooling header.

Brunswick 2003-301

SRO Inital Exam

91.

Which one of the following is a feature of Unit 1 only?

A. Select Rod Insert may be manually initiated by the operator at P603 by use of a

single pushbutton.

B. The fixed Scram point is setdown from 116% to 90%.

C. The EOC-RPT is manually bypassed via administratively controlled key switches on

P609 and P611.

D. When not in "Run" an IRM upscale will provide an RPS trip. There is no APRM

downscale RPS trip.

Brunswick 2003-301

SRO Inital Exam

Brunswick 2003-301

SRO Inital Exam

93.

You are the Site Emergency Coordinator. Following a LARGE Break LOCA you are

considering attempting to save a 4 Million Dollar test rig that is just inside the

containment access hatch. The task can be accomplished with a projected dose of

approximately 7.5 REM TEDE.

Which ONE of the following statements regarding this task is correct?

A. This exceeds the exposure limit listed in EPA 400 Emergency Work Limits to

protect valuable equipment.

B. While this exceeds the exposure limit listed in EPA 400 Emergency Work Limits to

protect valuable equipment you can authorize a single exposure for this purpose.

C. This does not exceed the exposure limit listed in EPA 400 Emergency Work Limits

to protect valuable equipment and you have the authority to grant permission for

this task.

D. This does not exceed the exposure limit listed in EPA 400 Emergency Work Limits

to protect valuable equipment. However, you do not have the authority to grant

permission for this task, it must be granted by the site VP or his designee.

Brunswick 2003-301

SRO Inital Exam

94.

Following an incomplete Reactor scram, the operating crew is executing EOP-01 -LPC,

Level/Power Control. A decision step is reached asking "Is The Reactor Shutdown?".

Which one of the following conditions would satisfy the definition of "SHUTDOWN" as

it applies to the Reactor?

A. All operable APRMs are downscale.

B. The Reactor is subcritical on range 6 of IRMs.

C. The entire SLC tank has been injected to the Reactor.

D. Hot Shutdown Boron Weight has been injected to the Reactor.

Brunswick 2003-301

SRO Inital Exam

95.

Unit heatup and pressurization is in progress per GP-02. Current plant conditions:

S...-Reactor power Range 9onIRM's .-...

RPV pressure 750 psig

RPV water level 187 inches

The operating CRD Pump trips on overcurrent. The operator attempts to start the

standby CRD Pump, which fails to start.

Which ONE of the following describes why AOP-02.0 requires a manual scram if CRD

pressure cannot be restored?

A. Control rods may fail to fully insert on a reactor scram if the HCU accumulator

pressure is lost.

B. Control rods cannot be inserted by normal means in the event of a positive

reactivity addition.

C. Control rod drive temperatures will rise and may result in a measurable delay in

scram response time.

D. Recirculation pump seal temperatures will rise to the point requiring both

Recirculation pumps to be tripped.

Brunswick 2003-301

,SRO Inital Exam

96.

Emergency Operating Procedure guidance is provided to trip the reactor recirculation

pumps during an ATWS condition.

Which ONE of the following is the basis for taking this action?

A. To rapidly reduce reactor power and potentially reduce the amount of heat that

would be added to the containment.

B. To avoid the area of thermal hydraulic instability.

C. To promote the dispersion of the boron from Standby Liquid Control System.

D. To decrease reactor pressure which increases CRD drive differential pressure.

Brunswick 2003-301

SRO Inital Exam

97.

During a Station Blackout on Unit One HPCI, RCIC and LPCI have all become

unavailable for injection to the RPV. Plant conditions:

RPV water level -55 inches (N036)

RPV pressure 300 psig

Drywell ref leg temp 315 OF

Injection sources None available

Which one of the following describes the current RPV water level?

A. Above the Minimum Steam Cooling Reactor Water Level, adequate core cooling is

assured.

B. Above the Minimum Zero-injection Reactor Water Level, adequate core cooling is

assured.

C. Below the Minimum Steam Cooling Reactor Water Level, adequate core cooling is

NOT assured.

D. Below the Minimum Zero-Injection Reactor Water Level, adequate core cooling is

NOT assured.

Brunswick 2003-301

SRO Inital Exam

98.

A fire in the Control Building requires Control Room evacuation and entry into

ASSD-02.

ASSD-02 directs the Diesel Generator Operator to trip the Unit Two RPS MG Set

output breakers and open the DC supply breakers to Distribution Panels 4A and 4B.

Failure to perform this action could result in which ONE of the following?

A. misoperation of RCIC.

B. loss of drywell cooling.

C. inability to operate SRVs.

D. spurious operation of MSIVs.

Brunswick 2003-301

SRO Inital Exam

99.

Following a steam leak in the Unit Two Secondary Containment, a manual Reactor Scram has been inserted. Plant conditions:

RPV pressure 1000 psig

Drywell ref leg area temp 197 OF

Rx Bldg 50' temp 145 OF

Recirculation Pump Running

RPV water level +150" (N036/N037)

RPV water level +170" (N026A/B)

RPV water level +155" (N0O4A/B/C)

RPV water level +160" (N027A/B)

RPV water level may be determined using which ONE of the following?

A. N004A/B/C only.

B. N004A/B/C and N026A/B only.

C. N004A/B/C and N027A/B only.

D. N004A/B/C and N036/N037 only.

Brunswick 2003-301

SRO -Inital Exam

100.

Unit 1 is operating at 100% power. The unit receives a Group 6 isolation and did NOT

receive a Secondary Containment Isolation.

Which ONE of the following may have occurred?

A. High Drywell Pressure.

B. Rx Bldg Exhaust Radiation High.

C. Rx Vessel Water Level Low LL2.

D. Rx Vessel Water Level Low LL1.