ML080910135

Browns Ferry Exam 05000259/2008301, 05000260/2008301, 05000296/2008301 - Final RO Written Exam

ML080910135
Person / Time
Site:	Browns Ferry
Issue date:	03/25/2008
From:	NRC/RGN-II
To:
References
50-259/08-301, 50-260/08-301, 50-296/08-301
Download: ML080910135 (79)

See also: IR 05000259/2008301

Text

Final Submittal (Blue Paper)FINAL RO WRITTEN EXAMINATION

ES-401, Rev.9 Name: Date: March 25, 2008 Site-Specific

RO Written Examination

Cover Sheet u.s.Nuclear Regulatory

Commission

Site-Specific

RO Written Examination

Applicant Information

Facility/Unit:

Browns Ferry Form ES-401*7 Region: Start Time:I/II/III/IV Reactor Type:W/CE/BW/GE 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 Applicant Certification

All work done on this examination

is my own.I have neither given nor received aid.Applicant's

Signature Results Examination

Value Applicant's

Score Applicant's

Grade Points Points____Percent

ANSWER KEY REPORT for 0610 RO Final Examination

Test Form: 0 1 RO 203000A1.01

1 1.00 MCS C 2 RO 205000K4.02

1 1.00 MCS C 3 RO 206000K6.09

1 1.00 MCS C 4 RO 209001K5.04

1 1.00 MCS B 5 RO 211000AK2.01

1 1.00 MCS A 6 RO 212000K6.03

1 1.00 MCS B 7 RO 215003A4.04

1 1.00 MCS D 8 RO 215004A3.03

1 1.00 MCS D 9 RO 215005A2.03

1 1.00 MCS D 10 RO 217000K2.03

1 1.00 MCS C 11 RO 218000K1.05

1 1.00 MCS B 12 RO 218000G2.1.24

2 1.00 MCS C 13 RO 223002A2.06

1 1.00 MCS A 14 RO 223002A3.01

2 1.00 MCS D 15 RO 239002A3.03

1 1.00 MCS B 16 RO 239002A4.08

1 1.00 MCS B 17 RO 259002A4.03

2 1.00 MCS A 18 RO 261000K3.03

1 1.00 MCS A 19 RO 262001K4.04

1 1.00 MCS B 20 RO 262002A1.02

1 1.00 MCS C 21 RO 263000K1.02

1 1.00 MCS D 22 RO 264000K5.06

2 1.00 MCS A 23 RO 300000K2.02

1 1.00 MCS D 24 RO 300000K3.01

1 1.00 MCS C 25 RO 400000G2.4.31

1 1.00 MCS A 26 RO 400000A2.02

1 1.00 MCS D 27 RO 201003K3.03

2 1.00 MCS A 28 RO 201006K4.09

1 1.00 MCS B 29 RO 202001K6.09

1 1.00 MCS A 30 RO 215001A1.01

1 1.00 MCS D 31 RO 216000K1.10

1 1.00 MCS D 32 RO 219000K2.02

1 1.00 MCS C 33 RO 226001A4.12

1 1.00 MCS B 34 RO 234000G2.4.50

1 1.00 MCS C 35 RO 245000K6.04

1 1.00 MCS B 36 RO 268000A2.01

2 1.00 MCS B 37 RO 272000K5.01

1 1.00 MCS A 38 RO 290003A3.01

2 1.00 MCS D 39 RO 295001G2.1.14

1 1.00 MCS A 40 RO 295001AK3.01

1 1.00 MCS A 41 RO 295003AA2.01

1 1.00 MCS B 42 RO 295004AK1.03

1 1.00 MCS A 43 RO 295005AA1.04

1 1.00 MCS C 44 RO 295006AK3.05

1 1.00 MCS B 45 RO 295016AA2.04

2 1.00 MCS D 46 RO 295018AK2.01

2 1.00 MCS C Thursday, March 20, 2008 11:29:33 AM 1

ANSWER KEY REPORT for 0610 RO Final Examination

Test Form: 0 47 RO 295019AA2.02

1 1.00 MCS A 48 RO 295021G2.4.50

1 1.00 MCS A 49 RO 295023AK1.02

1 1.00 MCS C 50 RO 295024G2.1.33

2 1.00 MCS D 51 RO 295025EK2.08

1 1.00 MCS B 52 RO 295026EA2.01

2 1.00 MCS A 53 RO 295028EK3.04

2 1.00 MCS A 54 RO 295030EAl.06

2 1.00 MCS D 55 RO 295031G2.4.6

1 1.00 MCS A 56 R0295037EK2.111

1.00 MCS A 57 RO 295038EKl.0l

1 1.00 MCS C 58 RO 600000AA1.08

1 1.00 MCS B 59 RO 295009AK2.01

1 1.00 MCS D 60 RO 295012G2.2.22

2 1.00 MCS A 61 RO 295015AKl.02

1 1.00 MCS C 62 RO 295020AK3.08

1 1.00 MCS B 63 RO 295032EAl.0l

1 1.00 MCS B 64 RO 295033EA2.01

1 1.00 MCS D 65 RO 295035EA2.02

1 1.00 MCS B 66 RO GENERIC 2.1.33 1 1.00 MCS C 67 RO GENERIC 2.1.16 1 1.00 MCS C 68 RO GENERIC 2.1.18 2 1.00 MCS D 69 RO GENERIC 2.2.13 1 1.00 MCS B 70 RO GENERIC 2.2.33 2 1.00 MCS B 71 RO GENERIC 2.3.10 1 1.00 MCS D 72 RO GENERIC 2.3.9 1 1.00 MCS B 73 RO GENERIC 2.4.47 1 1.00 MCS B 74 RO GENERIC 2.4.15 1 1.00 MCS C 75 RO GENERIC 2.4.8 1 1.00 MCS C SECTION1(75 items)75.00 Thursday, March 20, 2008 11:29:34 AM 2

Name:--------------

1.Given the following conditions:

0610 RO Final Examination

Form: 0 Version: 0*Unit2 has experienced

a Loss of Coolant Accident (LOCA).*Drywell sprays are required in accordance

with 2-EOI-2 flowchart.

Which ONE of the following plant conditions

must exist prior to opening BOTH the Residual Heat Removal (RHR)SYS I Inboard AND Outboard Drywell Spray Valves?A.RPV level MUST be greater than (-)155 inches (Emergency

Range)with ONLY the the CONT SPRAY VLV SEL SWITCH in SELECT.B.RPV level MUST be greater than (-)162 inches(PostAccident

Range)with ONLY the CONT SPRAY VLV SEL SWITCH in SELECT.C.RPV level is greater than (-)183 inches (Post Accident Range)with ONLY the CONT SPRAY VLV SEL SWITCH in SELECT.D.RPV level is less than (-)200 inches (Post Accident Range)with ONLY the 2/3 CORE HEIGHT KEYLOCK BYPASS SWITCH in BYPASS.Thursday, March 20, 2008 11:16:55 AM 1

0610 RO Final Examination

2.Given the following conditions

on Unit 2:*Reactor level*Reactor pressure*Drywell pressure (+)20 inches 45 psig 1.7 psig Which ONE of the following describes which modes of Residual Heat Removal (RHR)are capable AND available for use?A.Low Pressure Coolant Injection (LPCI), Drywell Sprays, and Shutdown Cooling.B.Suppression

Pool Cooling, Suppression

Pool Sprays, and Shutdown Cooling.C.Suppression

Pool Cooling, Low Pressure Coolant Injection, and Shutdown Cooling.D.Low Pressure Coolant Injection (LPCI), Drywell Sprays, and Supplemental

Fuel Pool Cooling.Thursday, March 20, 2008 11:16:55 AM 2

0610 RO Final Examination

3.Given the following plant conditions:*Unit2 reactor water level initially lowered to (-)69 inches.*Conditions

required entry into EOI-1,"RPV Control" and EOI-2,"Primary Containment

ControL"*After water level recovery, the High Pressure Coolant Injection (HPCI)Pump Injection Valve (FCV-73-44)

was manually closed and HPCI was placed in pressure control to remove decay heat.*Subsequently, Condensate

Storage Tank (CST)level dropped below 6800 gallons.Which ONE of the following describes the status of the HPCI system (assume no other operator actions have occurred)?

A.HPCI would be operating in pressure control with suction from the CST.B.HPCI would be pumping to the CST with suction from the Suppression

Pool.C.HPCI would be operating at shutoff head with suction from the Suppression

Pool.D.The HPCI turbine would trip on overspeed due to loss of suction during the transfer.Thursday, March 20, 2008 11:16:55 AM 3

0610 RO Final Examination

4.Which ONE of the following describes the basis forthereason that the Core Spray System is NOT on the list of preferred systems for low pressure injection for level restoration

if all control rods are NOT inserted during EOI execution?

A.Cold water from Core Spray creates a rapid pressure reduction and cooldown rates CANNOT be controlled.

B.Core Spray injects directly onto fuel bundles inside the shroud which could damage fuel and cause a power excursion.Core Spray injection creates a steam blanket at the top of the fuel bundles which inhibits heat transfer via steam flow past the fuel.D.Core Spray does NOT provide sufficient

flow to maintain adequate core cooling if an ATWS power level greater than or equal to 80%occurs.Thursday, March 20,2008 11:16:55 AM 4

0610 RO Final Examination

5.Given the following plant conditions:

• Unit 1 is operating at 100%power.*A fire inside the board causes a loss of the'1 B'480V Shutdown Board.*Fire Protection

reports that the fire cannot be extinguished.

• The Unit Supervisor (US)directs a manual scram.*NOT ALL control rods insert, and the following conditions

are noted:-Reactor Power-Suppression

Pool Temperature

15%108°F and rising*The'A'4kV Shutdown Board deenergized

due to an electrical

fault when'1 A'RHR pump was started for Suppression

Pool cooling lAW EOI-2.Which ONE of the following describes the action and method of injecting boron into the reactor?Transfer the ("--1_...)

to alternate and inject Standby Liquid Control (SLC)using the (2......)_)A.'1A'480V Shutdown Board;'1 A'SLC Pump.B.'1 B'480V Shutdown Board;'1 B'SLC Pump.C.'1A'480V Reactor MOV Board;'1 A'SLC Pump.D.'1 B'480V Reactor MOV Board;'1 B'SLC Pump.Thursday, March 20, 2008 11:16:55 AM 5

0610 RO Final Examination

6.Given the following plant conditions:

• Reactor Water Level Normal Control Range Instrument, 2-LIS-3-203A, has failed downscale.

Which ONE of the following describes the Analog Trip System Response?__________

and the contact in the Reactor Protection

System The trip relay will be (1)(RPS)Logic will be (2))A.de-energized;

closed B.de-energized;

open c.energized;

closed D.energized;

open Thursday, March 20, 2008 11:16:55 AM 6

0610 RO Final Examination

7.Given the following plant conditions:

• Unit 3 reactor startup preparations

are in progress with NO rods withdrawn.

• Instrument

Mechanics are performing

the Intermediate

Range Monitor (IRM)functional

surveillance.

• No IRMs are currently bypassed.*The Instrument

Mechanic technician

has placed the"INOP INHIBIT" toggle switch for the'H'Channel IRM in the"INHIBIT" position.Which ONE of the following describes the IRM trip function that is bypassed as a result of this action?A.IRM"High Voltage Low" INOP TRIP is bypassed.B.IRM"Loss of.+/-24 VDC" INOP TRIP is bypassed.C.IRM"Module Unplugged" INOP TRIP is bypassed.D.IRM"Mode Switch Out of Operate" INOP TRIP is bypassed.Thursday, March 20,2008 11:16:55 AM 7

0610 RO Final Examination

8.Given the following plant conditions:*A reactor startup is in progress following refueling, with ALL 8 Reactor Protection

System (RPS)Shorting Links removed.*The reactor is approaching

criticality.

• An electronic

failure in the'B'Source Range Monitor (SRM)drawer results in an SRM HIGH/HIGH output signal.Which ONE of the following describes the plant response?A.A Rod Out Block ONLY.B.A Rod Out Block and 1/2 Scram ONLY.c.A"SRM HIGH/HIGH" alarm ONLY.D.A Full Reactor Scram.Thursday, March 20, 2008 11:16:55 AM 8

0610 RO Final Examination

9.Which ONE of the following describes the expected response due to a"FAULT" in an Average Power Range Monitor (APRM)channel and the required action(s)in accordance

with 01-94B,"APRM System" to address this condition?

An APRM channel (1)will result in an INOP trip to (2)To continue plant operation, bypassing the APRM (3)required.)A.Critical Fault;ONL Y the respective

2/4 logic module voters;is NOT B.Non-critical

Fault;ONL Y the respective

2/4 logic module voters;is NOT C.Non-critical

Fault;ALL four of the 2/4 logic modules voters;is D.Critical Fault;ALL four of the 2/4 logic modules voters;is Thursday, March 20, 2008 11:16:56 AM 9

0610 RO Final Examination

10.Given the following Unit 2 conditions:

• The Control Room has been evacuated.

• Reactor Core Isolation Cooling (RCIC)is controlling

reactor water level.*A loss of the Division I Emergency Core Cooling System Inverter (Div 1 ECCS Inverter)occurs.Assuming no further operator action, which ONE of the following describes the RCIC system response?.The RCIC Flow Controller

---

A.lowers to minimum in auto ONLY.B.raises to maximum in manual ONLY.C.lowers to minimum in either manual OR auto mode.D.raises to maximum in either manual OR auto mode.Thursday, March 20, 2008 11:16:56 AM 10

0610 RO Final Examination

11.Given the following plant conditions:

• The Unit 1 and 2 Control Rooms have been abandoned.

• ALL Panel 25-32 Safety Relief Valve (SRV)Transfer Switches have been placed in EMERGENCY.

• ALL Panel 25-32 SRV Control Switches have been verified in CLOSE.Which ONE of the following describes the operation of the SRVs associated

with the Automatic Depressurization

System (ADS)?The associated

ADS valves will OPEN----------------

A.upon receipt of an ADS initiation

signal.B.in Safety mode, if their respective

pressure setpoints are exceeded.C.in Relief mode, if reactor pressure exceeds the relief mode setpoint.D.if their respective

control switches, on Panel 9-3, are placed in'OPEN.Thursday, March 20, 2008 11:16:56 AM 11

0610 RO Final Examination

12.Given the following plant conditions:

• Unit 2 is at rated power.*A loss of'2A'250 Volt RMOV Board has occurred.Which ONE of the following describes the effect on the Unit 2 Automatic Depressurization

System (ADS)valves and ADS logic?A.BOTH DivI&II ADS logics are operable.ALL ADS valves will operate automatically.

ALL ADS valves can be manually operated.B.BOTH DivI&II ADS logic is NOT operable.NO ADS valves will operate automatically.

Four (4)ADS valves can be operated manually.c.Div I ADS logic operable;Div II ADS logic is NOT operable.ALL ADS valves will actuate automatically.

ALL ADS valves can be operated manually.D.Div I ADS logic operable'IDiv

II ADS logic is NOT operable.ADS logic is ONLY capable of opening 4 ADS valves automatically.

Four (4)ADS valves can be operated manually.Thursday, March 20, 2008 11:16:56 AM 12

0610 RO Final Examination

13.Given the following plant conditions:

• During performance

of 2-SR-3.3.1.1.13,"Reactor Protection

and Primary Containment

Isolation Systems Low Reactor Water Level Instrument

Channel B2 Calibration," 2-LIS-3-203D

fails to actuate.*It is determined

that the failure is due to an inoperable

switch and a replacement

is NOT available for 4 days.*The Shift Manager has directed to place the inoperable

channel in a tripped condition per 2-01-99,"Reactor Protection

System." Which ONE of the following describes how this is accomplished

per 2-01-99,"Reactor Protection

System" and the effect on Unit status?A.Remove the fuse associated

with 2-LIS-3-203D.

A half scram will result and NO Primary Containment

Isolation Valves will realign.B.Remove the fuse associated

with 2-LIS-3-203D.

A half scram will result and PCIS Groups 2, 3 and 6 Inboard Isolation Valves will close.C.Place a trip into the Analog Trip Unit associated

with 2-LIS-3-203D.

NO half scram will result;however, ALL Primary Containment

Isolation Valves will realign.D.Place a trip into the Analog Trip Unit associated

with 2-LIS-3-203D.

A half scram will result and PCIS Groups 2, 3 and 6 Outboard Isolation Valves will close.Thursday, March 20, 2008 11:16:56 AM 13

0610 RO Final Examination

14.Accident conditions

on Unit 1 have resulted in an EOI-directed

Emergency Depressurization.

Reactor pressure is currently 106 psig.ALL systems function as designed.Regarding the High Pressure Coolant Injection (HPCI)System, which ONE of the following statements

describes the current status of the respective

indications

on the Containment

Isolation Status System (CISS)Panel and Panel 9-3 (assume ALL instruments/controls

actuate at the setpoint)?

The'amber'HPCI AUTO-ISOL LOGIC A/B lights, on Panel 9-3, are (1)The'amber'(HPCI)PCIS LOGIC A/B INTITIATION

lights, on the CISS Panel, are (2)The'green'(HPCI)pels LOGIC A/B SUCCESS lights, on the CISS Panel, are (3)(1)A.Extinguished.

Extinguished.

Extinguished.

B.Illuminated.

Illuminated.

Illuminated.

C.Illuminated.

Extinguished.

Illuminated.

D.Extinguished.

Illuminated.

Illuminated.

Thursday, March 20, 2008 11:16:56 AM 14

0610 RO Final Examination

15.Given the following plant conditions:

• The reactor is operating at 100%power and 1 000 psig.*A Turbine Control Valve malfunction

resulted in Safety Relief Valve (SRV)'1-4'lifting and failing to reseat.Which ONE of the following describes the expected SRV tailpipe temperature?

REFERENCE PROVIDED Thursday, March 20, 2008 11:16:56 AM 15

0610 RO Final Examination

16.Given the following plant conditions:*Unit2 is operating at 1000/0 power.*A complete loss of Drywell Control Air occurs (BOTH headers).*NEITHER crosstie with Containment

Atmosphere

Dilution (CAD), nor plant Control Air, can restore system pressure.Which ONE of the following statements

describes the effect on pneumatically

operated valves inside the Primary Containment

in accordance

with 2-AOI-32A-1,"Loss of Drywell Control Air?" A.ALL MSRV's can still be cycled five times due to the air system check valve arrangement.

B.ONLY ADS MSRVs can still be cycled five times due to the air system accumulator

and check valve arrangement.

C.Inboard MSIVs can be opened one time due to the air system accumulator

and check valve arrangement.

D.Inboard MSIVs will remain OPEN due to spring pressure until closed by a valid isolation signal.Thursday, March 20, 2008 11:16:56 AM 16

0610 RO Final Examination

17.Which ONE of the following describes the indications

and controls available when the Unit Operator transfers theUnit1 Reactor Feedwater Startup Level Controller

from MANUAL to AUTO?The Auto/Manual

(1)light extinguishes

and the (2)light illuminates.

The controller

is now controlling

in (3)Element with the controller

output changed from (4))A.Amber;Blue;Single;Demand output to Level Setpoint output.B.Amber;Blue;Single;Level Setpoint output to Demand output.C.Blue;Amber;Three;Level Setpoint output to Demand output.D.Blue;Amber;Three;Demand output to Level Setpoint output.Thursday, March 20, 2008 11:16:56 AM 17

0610 RO Final Examination

18.Unit 2 has experienced

a LOCA with the following plant conditions:*Drywell pressure is 51 psig and rising.*Suppression

Chamber (Torus)water level is 18.5 feet.*An Emergency Depressurization

has been conducted.

• The Torus is being vented through Standby Gas Treatment (SGT)'A'train.*Standby Gas Trains'B'and'c'are INOPERABLE

due to common mode failures.IF Standby Gas Train'A'were to suffer the same common mode failure under these conditions, which ONE of the following would be thenextsequential, EOI-directed

step to exhaust the primary containment

atmosphere?

Vent the (_1.....)__in accordance

with 2-EOI Appendix 13,"Emergency

Venting Primary Containment,".......(_2)_REFERENCE PROVIDED (1)A.Torus;via the Hardened Wetwell Vent System.B.Torus;allowing the Primary Containment

Vent Ducts to fail.C.Drywell;via the Hardened Wetwell Vent System.D.Drywell;allowing the Primary Containment

Vent Ducts to fail.Thursday, March 20, 2008 11:16:56 AM 18

0610 RO Final Examination

19.Given the following plant electrical

distribution

alignment:

• 4kV Shutdown Bus 1'43'Switch is in MANUAL.*ALL 4kV Shutdown Board'43'Switches are in AUTO.*A fault on'A'4kV Unit Board de-energizes

4kV Shutdown Bus 1.Which ONE of the following represents

how and when the'A'4kV Shutdown Board alternate supply breaker will auto close?A (1)transfer occurs when (2)voltage decays to less than 30%.(1)A.fast;4kV Shutdown Bus 1 B.slow;4kV Shutdown Bus 1 c.fast;'A'4kV Shutdown Board D.slow;'A'4kV Shutdown Board Thursday, March 20, 2008 11:16:57 AM 19

0610 RO Final Examination

20.Given the following plant conditions:

• Unit 3 is in a normal lineup.*The following alarm is received:-UNIT PFD SUPPLY ABNORMAL*It is determined

that the alarm is due to the Unit 3 Unit Preferred AC Generator Overvoltage

condition Which ONE of the following describes the result of this condition?

Unit 3 Breaker 1001 (1).Unit 2 Breaker 1003 (2_.)__;and the Motor-Motor-Generator (MMG)set (3)(1)A.trips OPEN;is interlocked

OPEN;automatically

shuts down.B.is interlocked

OPEN;trips OPEN;automatically

shuts down.C.trips OPEN;is interlocked

OPEN;continues to run without excitation.

D.is interlocked

OPEN;trips OPEN;continues to run without excitation.

Thursday, March 20,2008 11:16:57 AM 20

0610 RO Final Examination

21.Which ONE of the following statements

is correct regarding the'2B'250VDC Battery Charger?A.The normal power supply is'2A'480V Shutdown Board.B.Can supply (directly from the Unit 2 Battery Board Room)any of the six Unit&Plant 250VDC Battery Boards.C.Load shedding can NOT be bypassed until the Load Shed signal has been reset.D.Load shedding can be bypassed by placing the"Emergency

ON Select Switch" in the"EMERGENCY

ON" Position.Thursday, March 20, 200811:16:57

AM 21

0610 RO Final Examination

22.Given the following plant conditions:*Unit2 is operating at 1 00 otic>Power.*No Equipment is Out of Service.*A large-break

LOCA occurs in the drywell and the following conditions

exist:-Drywell Pressure peaked at 28 psig and is currently at 20 psig.-Reactor Pressure is at 110 psig.-Reactor Water Level is at (-)120 inches.-Offsite power is available.

Which ONE of the following describes the associated

equipment and proper loading sequence?A.'2B'RHR Pump and'2B'Core Spray Pump start 7 seconds after the accident signal is received.RHRSW pumps lined up for EECW start 28 seconds after the accident signal is received.B.'2C'RHR Pump and'2C'Core Spray Pump start 7 seconds after the accident signal is received.RHRSW pumps lined up for EECW start 28 seconds after the accident signal is received.C.'2A'RHR Pump starts immediately

and'2A'Core Spray Pump starts 7 seconds after the accident signal is received.RHRSW pumps lined up for EECW start 14 seconds after the accident signal is received.D.'2C'RHR Pump and'2C'Core Spray Pump start 14 seconds after the accident signal is received.RHRSW pumps lined up for EECW start 14 seconds after the accident signal is received.Thursday, March 20, 2008 11:16:57 AM 22

0610 RO Final Examination

23.Which ONE of the following lists the current power supplies to the Control and Service Air Compressor

motors?A.'A'and'B'are fed from 480V Common Board#1'c'and'0'from 480V Shutdown Boards'1 B'&'2B', respectively

'G'from 4KV Shutdown Board'B'and 480V Shutdown Board'2AE'from 480V Common Board#1 B.'A'and'0'are fed from 480V Common Board#1'B'and'C'from 480V Shutdown Boards'1 B'&'2B', respectively

'G'from 4KV Shutdown Board'B'and 480V RMOV Board'2AF'from 480V Common Board#3 C.'A'is fed from 480V Shutdown Board'1 BB'and'F'from 480V Common Board#3'c'from 480V Shutdown Board'1 A0'from 480V Shutdown Board'2AG'from 4KV Common Board#2 o.'A'is fed*from 480V Shutdown Board'1 BB'and'c'from 480V Common Board#1'0'from 480V Shutdown Board'2AG'from 4KV Shutdown Board'B'and 480V RMOV Board'2AE'from 480V Common Board#3 Thursday, March 20,2008 11:16:57 AM 23

0610 RO Final Examination

24.A LOCA has occurred on Unit 1 and the Drywell is being vented to the Standby Gas Treatment System (SBGT), when a loss of the Control Air System occurs.Which ONE of the following describes the impact of the loss of air, on the operation of DRYWELL VENT INBD ISOL VALVE (1-FCV-64-29), and PATH'B'VENT FLOW CONT VALVE (1-FCV-84-19)?

Both vent valves 1-FCV-64-29

&1-FCV-84-19

will fail CLOSED and------A.will automatically

re-open as soon as INST GAS SELECTOR VALVE (1-PCV-84-33)

automatically

swaps to CAD Nitrogen Storage Tank'A.'B.must be manually re-opened as soon as INST GAS SELECTOR VALVE (1-PCV-84-33)

automatically

swaps to CAD Nitrogen Storage Tank'A.'C.will automatically

re-open as soon as CAD SYSTEM'A'N2 SHUTOFF VALVE (0-FCV-84-5)

is manually opened from Main Control Room Panel 1-9-54.D.must be manually re-opened as soon as CAD SYSTEM'A'N2 SHUTOFF VALVE (0-FCV-84-5)

is manually opened from Main Control Room Panel 1-9-54.Thursday, March 20,200811:16:57

AM 24

0610 RO Final Examination

25.Unit 3 is at rated power with the following indications:

• RECIRC PUMP MTR'B'TEMP HIGH (3-XA-9-4B, Window 13).*RBCCW EFFLUENT RADIATION HIGH (3-XA-9-3A, Window 17).*RBCCW SURGE TANK LEVEL HIGH (3-XA-9-4C, Window 6).*RX BLDG AREA RADIATION HIGH (3-XA-9-3A, Window 22).*Recirc Pump Motor'3B'Winding and Bearing Temperature

Recorder (3-TR-68-84)is reading 170°F and rising.*RBCCW Pump Suction Header Temperature

Indicator (3-TIS-70-3)

is reading 104°F and rising.*RWCU NON-REGENERATIVE

HX DISCH TEMP HIGH (3-XA-9-4C, Window 17).*Area Radiation Monitor RE-90-13A and RE-90-14A are in alarm reading 55 mr/hr and rising.Which ONE of the following describes the actions that should be taken in accordance

with plant procedures?

REFERENCE PROVIDED Enter 3-EOI-3,"Secondary

Containment

Control" and_A.Trip and isolate'3B'Recirc Pump.Enter 3-AOI-68-1A"Recirc Pump Trip/Core Flow Decrease OPRMs Operable." B.Trip and isolate'3B'Recirc Pump.Commence a normal shutdown in accordance

with 3-GOI-1 00-12A,"Unit Shutdown." C.Trip RWCU pumps and isolate the RWCU system.Commence a normal shutdown in accordance

with 3-GOI-1 00-12A,"Unit Shutdown." D.Trip RWCU pumps and isolate the RWCU system.Close RBCCW Sectionalizing

Valve 3-FCV-70-48

to isolate non-essential

loads and maximize cooling to'3B'Recirc Pump.Thursday, March 20,200811:16:57

AM 25

0610 RO Final Examination

26.Unit 2 is operating at 1000/0 power, and the following annunciators

are received:*DRYWELL EQPT DR SUMP TEMP HIGH (2-XA-55-4C, Window 16)*RBCCW SURGE TANK LEVEL LOW (2-XA-55-4C, Window 13)*RBCCW PUMP DISCH HDR PRESS LOW (2-XA-55-4C, Window 12)*RBCCW 2-FCV-70-48

CLOSED (2-XA-55-4C, Window 19)Which ONE of the following describes the impact on the Reactor Building Closed Cooling Water (RBCCW)System and the required actions?A.RBCCW flow to the RWCU Non-Regenerative

Heat Exchanger has been lost.Enter 2-AOI-70-1,"Loss of RBCCW" and immediately

trip the RWCU pumps and ISOLATE the RWCU system.B.RBCCW flow to the Drywell has been lost.Enter 2-AOI-70-1,"Loss of RBCCW" and remove the RWCU pumps from service IF RBCCW suction temperature

cannot be maintained

below 105°F.C.RBCCW flow to the Drywell has been lost.Enter 2-AOI-70-1

,"Loss of RBCCW" and immediately

trip the RWCU pumps.D.RBCCW flow to the RWCU Non-Regenerative

Heat Exchanger has been lost.Enter 2-AOI-70-1,"Loss of RBCCW" and remove the RWCU pumps from service IF RBCCW suction temperature

cannot be maintained

below 105°F.Thursday, March 20,200811:16:57

AM 26

0610 RO Final Examination

27.Unit 1 has experienced

a failure of both CRD pumps.Which ONE of the following PROCEDURAL

reactor pressure limits should be adhered to, as required by 1-AOI-85-3,"CRD System Failure," and what is the basis for the limit?A.890 psig reactor pressure.This would be the lowest pressure a scram can be ensured due to the loss of accumulators.

B.890 psig reactor pressure.This would be the lowest pressure a scram can be ensured in the event of a loss of CRD pumps.C.940 psig reactor pressure.This would be the lowest pressure a scram can be ensured due to the loss of accumulators.

D.940 psig reactor pressure.This would be the lowest pressure a scram can be ensured in the event of a loss of CRD pumps.Thursday, March 20,2008 11:16:57 AM 27

0610 RO Final Examination

28.Which ONE of the following describes how the Rod Worth Minimizer (RWM)System INITIALIZATION

is accomplished?

A.INITIALIZATION

occurs automatically

when the RWM is unbypassed.

B.INITIALIZATION

must be performed manually when the RWM is unbypassed.

c.INITIALIZATION

occurs automatically

every 5 seconds while in the transition

zone.D.INITIALIZATION

must be performed manually when power drops below the Low Power Setpoint (LPSP).Thursday, March 20, 2008 11:16:58 AM 28

0610 RO Final Examination

29.Given the following plant conditions:

• Unit 3 is operating at 35%power with'A'&'c'Reactor Feed Pumps (RFP)running and'B'RFP idling.*Both Recirculation

Pump speeds are 53%.*The'A'RFP trips, resulting in the following conditions:

REACTOR WATER LEVEL ABNORMAL (2-ARP-9-5A

Window 8).REACTOR CHANNEL'A'AUTO SCRAM (2-ARP-9-5B

Window 1).REACTOR CHANNEL'B'AUTO SCRAM (2-ARP-9-5B

Window 2).*Indicated Reactor Water Level drops to (-)43 inches before'B'RFP is brought on line to reverse the level trend and level is stabilized

at (+)33 inches.Which ONE of the following describes the final condition of both Recirculation

Pumps?A.Running at 28%speed.B.Running at 45%speed.C.Running at 53%speed.D.Tripped on ATWS/RPT signal.Thursday, March 20, 2008 11:16:58 AM 29

0610 RO Final Examination

30.Given the following Unit 2 conditions:

• Preparations

are in progress to commence a startup following a refueling outage.*The Drywell Close-out inspection

is in progress with three personnel inside the Drywell.*Reactor Engineershavebegun running Traversing

In-Core Probe (TIP)traces.*RX BLDG AREA RADIATION HIGH (2-XA-9-3A, Window 22)is in alarm.*Area Radiation Monitor 2-RM-90-23,"TIP Drive Area R.B" indicates 16 mr/hr.Which ONE of the following describes the required actions?A.This is an expected indication

while running TIP traces, therefore TIP operation may continue.B.Verify the TIP mechanism automatically

shifts to REVERSE mode and begins a full retraction.

C.Manually retract the detector in FAST speed to the In-Shield position and close the ball valve.D.This is NOT an expected indication

while running TIP traces.Evacuate the Unit-2 Drywell and Reactor Building.Thursday, March 20,2008 11:16:58 AM 30

0610 RO Final Examination

31.Which ONE of the following indicates how raising recirculation

flow affects the Emergency System (Wide Range)3-58A/58B and Normal Control Range Level Indicators (e.g., LI-3-53)on Panel 9-5?Emergency System Range indication

will{_1)__and the Normal Control Range indication

will (2)(1)A.indicate lower;B.NOT be affected;C.indicate higher;D.indicate lower;Thursday, March 20, 2008 11:16:58 AM indicate lower.indicate higher.NOT be affected.NOT be affected'.

31

0510 RO Final Examination

32.Given the following plant conditions:

• Unit 2 is at 100%rated power with Residual Heat Removal (RHR)Loop II in Suppression

Pool Cooling.*A Loss of Off-Site Power has occurred.*Unit 1 experiences

a LOCA which results in a Common Accident Signal (CAS)initiation

on Unit 1.Which ONE of the following describes the current status ofUnit2 RHR system and what actions must be taken to restore Suppression

Pool Cooling on Unit 2?A.ALL four RHR pumps receive a trip signal.Place RHR Loop II in Suppression

Pool Cooling IMMEDIATELY.

8.'2A'and'2C'RHR Pumps are tripped.'28'and'2D'pumps are unaffected.

NO additional

action is required.C.ALL four RHR pumps receive a trip signal.Place RHR Loop II in Suppression

Pool Cooling after a 50-second time delay.D.'28'and'2D'RHR Pumps are tripped.'2A'and'2C'pumps are unaffected.

Place RHR Loop I in Suppression

Pool Cooling IMMEDIATELY.

Thursday, March 20,2008 11:16:58 AM 32

0610 RO Final Examination

33.Which ONE of the following sets of parameters

below must ALWAYS be addressed to determine when it is appropriate

to spray the drywell?A.-Drywell pressure-Drywell temperature

-Suppression

Chamber Air Space temperature

-Suppression

Pool Temperature

B.-Drywell pressure-Drywell temperature

-Suppression

Pool level-Reactor water level C.-Drywell pressure-Drywell temperature

-Reactor water level-Suppression

Chamber Air Space temperature

D.-Drywell pressure-Drywell temperature

-Reactor water level-Suppression

Pool Temperature

Thursday, March 20, 2008 11:16:58 AM 33

0610 RO Final Examination

34.Given the following Unit-1 plant conditions:

• Fuel movement is in progress for channel change-out

activities

in the Fuel Prep Machine.*Gas bubbles are visible coming from the de-channeled

bundle.*An Area Radiation Monitor adjacent to the Spent Fuel Storage Pool begins alarming.Which ONE of the following describes the IMMEDIATE action(s)to take per 1-AOI-79-1,"Fuel Damage During Refueling?" Immediately

STOP fuel handling,

A.notify the Control Room to sound the Containment

Evacuation

Alarm.B.notify RADCON to monitor&evaluate radiation levels.C.evacuate ALL non-essential

personnel from the Refuel Floor.D.obtain Reactor Engineering

Supervisor's

recommendation

for movement and sipping of the damaged fuel assembly.Thursday, March 20, 2008 11:16:58 AM 34

0610 RO Final Examination

35.Given the following plant conditions:*Unit2 is operating at 100%power.*Main Generator is at 1150 MWe.*TheChattanooga

Load Coordinator

requires a 0.95 lagging power factor.*Generator hydrogen pressure is 65 psig.Which ONE of the following describes the required action and reason if Generator hydrogen pressure drops to 45 psig?REFERENCE PROVIDED A.Reduce generator load below 1000 MWe.Pole slippage may occur at this generator load.B.Reduce generator load below 1000 MWe.Sufficient

cooling capability

still exists at this hydrogen pressure.C.Reduce excitation

to obtain a power factor of 1.00 to maintain current generator load.Pole slippage may occur at this power factor.D.Reduce excitation

to obtain a power factor of 1.00 to maintain current generator load.Sufficient

cooling capability

still exists at this hydrogen pressure.Thursday, March 20, 2008 11:16:58 AM 35

36 0610 RO Final Examination

36.Given the following plant conditions:

• BFN is in the process of discharging

the Waste Sample Tank to the Unit 1 Condensate

Storage Tank.*While moving resin containers, a forklift operator accidently

punctures the discharge line 4 feet downstream

of 0-RR-90-130 (Radwaste Effluent Radiation Monitor).*Water immediately

begins spraying out of the rupture.Which ONE of the following describes the expected system response?The discharge will

A.(1)automatically

terminate without any additional

operator action;Radwaste Discharge Isolation Valve will ONLY auto close on HIGH effluent radiation.

B.continue until manually terminated

per 0-01-77a,"Waste Collector/Surge

System Processing;" Radwaste Discharge Isolation Valve will.auto close on LOW CCW flow or HIGH effluent radiation.

C.(1)automatically

terminate without any additional

operator action;Radwaste Discharge Isolation Valve will ONLY auto close on LOW CCW flow.D.(1)continue until manually terminated

per 0-01-77a,"Waste Collector/Surge

System Processing;" Radwaste Discharge Isolation Valve will ONLY auto close on HIGH effluent radiation.

Thursday, March 20, 2008 11:16:58 AM

0610 RO Final Examination

37.Given the following plant conditions:

• The operator has transferred

the hydrogen controller

from"Power Determined

Setpoint" mode to"Operator Determined

Setpoint" mode.*Hydrogen flow is set at 14 SCFM.Which ONE of the following describes the plant response if reactor power is reduced?Main Steam Line radiation levels will{1_)the lowering of reactor power due to{_2__)_)A.rise in opposition

to;a rise in volatile Ammonia production.

B.lower in response to;a reduction in Nitrogen concentration.

C.lower in response to;a reduction in Hydrogen concentration.

D.rise in opposition

to;a rise in Nitrite and Nitrate production.

Thursday, March 20,2008 11:16:58 AM 37

0610 RO Final Examination

38.Given the following plant conditions:

• High radiation has been detected in the air inlet to the Unit 3 Control Room.*Radiation Monitor RE-90-259B

is reading 275 cpm above background.

Which ONE of the following describes the Control Room Emergency Ventilation (CREV)System response?A.NEITHER CREV unit will automatically

start at the current radiation level.B.BOTH CREV units will automatically

start with suction from the normal outside air path to Elevation 3C.C.The Selected CREV unit will automatically

start and will continue to run until Control Bay Ventilation

is restarted;

then, it will automatically

stop.D.The Selected CREV unit will automatically

start.The Standby CREV unit will begin to auto-start;

but, will ONLY run if the selected CREV unit fails to develop sufficient

flow.Thursday, March 20, 2008 11:16:59 AM 38

0610 RO Final Examination

39.Given the following plant conditions:

• You are the At-The-Controls (ATC)operator on Unit 1.*Unit 1 is operating at full power when 1A Recirculation

pump tripped.*The Unit Supervisor

has directed you to carry out the actions of 1-AOI-68-1

A,"Recirc Pump Trip/Core Flow Decrease OPRMs Operable." Which ONE of the following describes the action(s)that require assistance

from outside organizations?

A.Perform the actions of 1-SR-3.4.1 (SLO),"Reactor Recirculation

System Single Loop Operation." B.Use the ICS screens VFDPMPA(VFDPMPB)

and VFDAAL(VFDBAL)

to determine the cause of the Recirc Pump trip/core flow decrease.C.Perform the actions of 0-TI-464, Reactivity

Control Plan.D.Use the ICS screens associated

with the Recirc Drive and Recirc Pump/Motor

1A(1 B)on ICS and RECIRC PMP MTR 1A&1B WINDING&BRG TEMPS, 1-TR-68-71

to determine the cause of the Recirc Pump trip.Thursday, March 20, 2008 11:16:59 AM 39

0610 RO Final Examination

40.Which ONE of the following describes the Reactor Water Level response following a single Recirc Pump trip from 100%power?A.Rises initially due to swell, then returns to normal.B.Lowers initially due to shrink, then returns to normal.c.Rises initially due to swell and remains high due to a lower power level.D.Lowers initially due to shrink and remains lower due to the loss of core voids.Thursday, March 20, 2008 11:16:59 AM 40

0610 RO Final Examination

41.Given the following plant conditions:

• All three units were at 100%rated power when the 500KV PCB 5234 (Trinity 1 feed to Bus 1 Section 1)tripped and failed to auto close.*The signal which caused the Power Circuit Breaker (PCB)trip can NOT be reset.*The Chattanooga

Load Coordinator

has issued a Switching Order directing BFN to open Motor Operated Disconnect (MOD)5233 and 5235 to isolate 500KV PCB 5234 for troubleshooting.

Which ONE of the following describes your response to this Switching Order and the basis for that response?ENSURE the PK block for PCB 5234 is (1))to prevent (_2)_A.removed;electrical

arcing across the MOD contacts while being opened.B.removed;actuating the breaker failure logic and tripping the remainder of the PCBs on Bus1.C.installed;

actuating the breaker failure logic and tripping the remainder of the PCBs on Bus1.D.installed;

electrical

arcing across the MOD contacts while being opened.Thursday, March 20,2008 11:16:59 AM 41

0610 RO Final Examination

42.Given the following plant conditions:*A reactor startup is in progress onUnit3 and reactor power is on IRM Range 7.*The operator observes the following indications:

-SRM DOWNSCALE (3-XA-9-5A, Window 6)-IRM CH'A','C','E','G'HI-HI/INOP (3-XA-9-5A, Window 33)-IRM CH'A','C','E', and'G'indicate downscale.

Which ONE of the following power sources, if lost, would cause these failures?A.+/-24V DC Power Distribution

Panel B.+/-48V DC Power Distribution

Panel C.120V AC RPS Power Supply Distribution

Panel D.120V AC Instrument

and Control Power Distribution

Panel Thursday, March 20, 2008 11:16:59 AM 42

0610 RO Final Examination

43.Given the following plant conditions:

• Unit 1 is at 1000/0 rated power when the Desk Unit Operator notices that number 3 Main Turbine Stop Valve (MTSV)position indication

is reading 50%.*Numbers 1, 2, and 4 MTSV position indications

all read 100%**Maintenance

investigation

determines

that the cause of the MTSV position indicator failure is due to a mechanical

failure of the Linear Variable Differential

Transformer (L VDT).*The Unit 1 Main Turbine later receives a trip signal.Which ONE of the following describes the effect on Main Turbine/Generator

operation?

A.The RPS logic contact for the#3 MTSV will NOT function so a turbine trip will NOT initiate a scram.B.The RPS logic contact is already OPEN for the#3 MTSV so a turbine trip will initiate a scram.c.The Generator output breaker will NOT automatically

open on a turbine trip.D.The Generator output breaker will automatically

open on a turbine trip.Thursday, March 20, 2008 11:16:59 AM 43

0610 RO Final Examination

, 44.Given the following plant conditions:

• Power ascension is in progress on Unit 3 with the Main Turbine on line.*Control Rods are being withdrawn to increase power.*As reactor power approaches

35%, the Shift Technical Advisor (STA)notes that two (2)Turbine Bypass Valves are OPEN.Which ONE of the following describes the effect on the plant?Regarding the UFSAR Chapter 14 analyses for a turbine trip, the above condition is (1)conservative

than the assumptions

used in the UFSAR because (2)A.more;B.less;C.more;D.less;it lowers the peak vessel pressure for a design basis transient in regard to peak cladding temperature.

it raises the actual power level at which the RPS reactor scram on turbine trip is enabled.it lowers the peak vessel pressure for a design basis transient in regard to transition

boiling.it raises the actual power level for a design basis transient in regard to peak cladding temperature.

Thursday, March 20, 2008 11:16:59 AM 44

0610 RO Final Examination

45.In accordance

with 3-AOI-100-2,"Control Room Abandonment", a Suppression

Pool Temperature

limit of less than or equal to--.i1.L°F has been established.

The basis for this limit is (2)?)A.110°F;to prevent damage to the RCIC turbine from overheated

lube oil, which is cooled by the Suppression

Pool water.B.110°F;to prevent exceeding the design basis maximum allowable values for primary containment

temperature

or pressure.C.120 of;to prevent damage to the RCIC turbine from overheated

lube oil, which is cooled by the Suppression

Pool water.D.120 of;to prevent exceeding the design basis maximum allowable values for primary containment

temperature

or pressure.Thursday, March 20,2008 11:16:59 AM 45

0610 RO Final Examination

46.Which ONE of the following lists of components

would lose cooling upon closure of valve 2-FCV-70-48,"RBCCW NON-ESSENTIAL

LOOP ISOLATION VALVE?" A.Recirculation

Pump Seals Reactor Building Equipment Drain Sump RWCU Sample Cooler B.Drywell Atmospheric

Coolers Recirculation

Pump Seals Drywell Equipment Drain Sump Heat Exchanger C.Spent Fuel Pool Cooling Heat Exchanger Reactor Building Equipment Drain Sump RWCU Sample Cooler D.Drywell Equipment Drain Sump Heat Exchanger Reactor Building Equipment Drain Sump Recirculation

Pump Seals Thursday, March 20, 2008 11:16:59 AM 46

0610 RO Final Examination

47.Given the following plant conditions:*Unit2 was at 100%power when a transient occurred which resulted in a reactor scram.*After stabilizing

the unit, the scram signal is RESET.*All eight (8)Scram Solenoid Group lights are ON.*Approximately

ten minutes later, the following conditions

are present:-Raw Cooling Water (RCW)Low Pressure Alarm-CRDcharging

water High Pressure Alarm-Outboard MSIVs CLOSED, Inboard MSIVs are OPEN-Scram Discharge Volume (SDV)Vents and Drain Valves are CLOSED-Scram Solenoid Air Valves are OPEN Which ONE of the following describes the cause for the event?A.Loss of Control Air.B.Loss of both RPS busses.C.Loss of Drywell Control Air.D.Loss of 9-9 cabinet 5, Unit Non-Preferred.

Thursday, March 20, 2008 11:16:59 AM 47

0610 RO Final Examination

48.Given the following plant conditions:*Unit2 is aligned with RHR Loop I in Shutdown Cooling and RHR Loop II in standby readiness.*A leak occurs in the RPV, which results in the following conditions:

-RPV level at 0 inches and slowly lowering-Drywell Pressure at 3.0 psig and slowly rising-RHR Pumps'A'and'c'TRIPPED Which ONE of the following describes the minimum actions required to align RHR Loop II for injection to the RPV?A..After FCV-74-47 OR FCV-74-48 is closed, push the RHR SYS II SD CLG INBD INJECT ISOL RESET 2-XS-74-132.

B.After FCV-74-47 AND FCV-74-48 are closed, start RHR Loop II pumps, reset PCIS, and open the inboard injection valve.C.After FCV-74-47 OR FCV-74-48 is closed;reset PCIS, push the RHR SYS II SD CLG INBD INJECT ISOL RESET 2-XS-74-132, and open the inboard injection valve.D.After FCV-74-47 AND FCV-74-48 are closed, reset PCIS, push the RHR SYS II SD CLG INBD INJECT ISOL RESET 2-XS-74-132, and open BOTH injection valves.Thursday, March 20, 2008 11:17:00 AM 48

0610 RO Final Examination

49.Fuel loading is in progress on Unit 1 when you notice an unexplained

rise in Source Range Monitor (SRM)count rate and an indicated positive reactor period after lowering a fuel bundle into the core.Which ONE of the following actions is an appropriate

response in accordance

with 1-AOI 79-2,"Inadvertent

Criticality

During Incore Fuel Movements?" A.EVACUATE all personnel from the refuel floor ONLY.B.Manually SCRAM the reactor ONLY.C.Move the fuel assembly away from the reactor core.D.EVACUATE all personnel from the refuel floor AND manually SCRAM the reactor.Thursday, March 20, 2008 11:17:00 AM 49

0610 RO Final Examination

50.During operation at 1000/0 power a complete failure of both seals on Recirculation

Pump'B'increases Drywell Pressure to 2.0 psig.Which ONE of the following is the Reactor Coolant System status resulting from this condition?

The amount of the leak is approximately

(1)and is classified

as__(_2__)__leakage in accordance

with Technical Specifications.

)A.30 gpm;Identified

leakage B.30 gpm;Unidentified

leakage C.60 gpm;Identified

leakage D.60 gpm;Unide'ntified

leakage Thursday, March 20, 2008 11:17:00 AM 50

0610 RO Final Examination

51.Unit 2 has experienced

an inadvertent

Main Steam Isolation Valve (MSIV)closure and subsequent

reactor scram.Consequently, RCIC was placed in level control and is also maintaining

reactor pressure 900 to 1000 psig with the MSIVs still isolated.Given these plant conditions, the digital Electro-Hydraulic

Control (EHC)System is in (1)Pressure Control mode with the pressure setpoint set at (2)psig.)A.Reactor;700 B.Header;700 C.Reactor;970 D.Header;970 Thursday, March 20,2008 11:17:00 AM 51

0610 RO Final Examination

52.Given the following plant conditions:

• Unit 2 is currently testing SRVs at full power with current conditions

as follows:-Suppression

pool level:-Reactor pressure:-Suppression

pool single element temperature:

-Suppression

pool bulk temperature:

Which ONE of the following describes the required action?15 feet 980 psig 112°F 96°F A.Enter EOI-2,"Primary Containment

Control" and Operate ALL available Suppression

Pool Cooling.B.Enter EOI-1,"RPV Control" then SCRAM the reactor ONLY.C.Enter EOI-2,"Primary Containment

Control" and suspend testing of SRVs.D.Enter EOI-1,"RPV Control" then SCRAM the reactor and inject SLC.Thursday, March 20, 2008 11:17:00 AM 52

0610 RO Final Examination

53.Given the following plant conditions:*A Loss of Off-site power has occurred in conjunction

with a small LOCA on Unit 2.*Plant conditions

are as follows:-Reactor Water Level-Average Drywell Temperature

-Suppression

Chamber Pressure-Emergency Diesel Generators

-Reactor pressure (+)20 inches, steady 189°F, slowly rising 9 psig , steady rising Connected to 4 KV Sd Bds 800 psig*The Unit Supervisor

directs you to ensure all DW cooling is in service.Which ONE of the following conditions

would you expect for the drywell cooling systems?A.ALL Drywell coolers are operating;

Both RBCCW pumps are operating.

B.No Drywell coolers are operating;

Only 1 RBCCW pump is operating.

C.ALL Drywell coolers are operating;

Only 1 RBCCW pump is operating.

D.No Drywell coolers are operating;

Both RBCCW pumps are operating.

Thursday, March 20,2008 11:17:00 AM 53

0610 RO Final Examination

54.Given the following plant conditions:*A LOCA has caused gross fuel failure due to sustained level below TAF on Unit 3.*The Site Emergency Director (SED)/SRO has approved implementation

of EOI Appendix 18,"Suppression

Pool Water Inventory Removal and Makeup." to return level to the normal band for implementation

of SAMG strategies.

• While performing

EOI Appendix 18 via the RHR Drain Pump, the RHR Drain pump inadvertantly

tripped.*Suppression

Pool level is (-)3.5 inches and steady.Which ONE of the following describes the next appropriate

action(s)?

A.Open the HPCI Min Flow Valve.B.Continue draining the Suppression

Pool by directing the water to Radwaste.C.Continue draining the Suppression

Pool by directing the water to the Main Condenser.

D.Secure the drain path alignment.

Thursday, March 20, 2008 11:17:00 AM 54

0610 RO Final Examination

55.Given the following plant conditions:

• Unit 2 was operating at 98%power when an automatic scram occurs due to a Group I Isolation.

• ALL control rods fully insert as reactor water level immediately

drops below Level 2.*BOTH Recirc Pumps trip.*HPCI automatically

initiates but immediately

isolates due to a ruptured inner turbine exhaust rupture diaphragm.

• RCIC is currently tagged out of service to repair an oil leak.*ALL other systems are operable.*EOI-1, RPV Control, is entered.*Pressure control was established

with Safety Relief Valves (SRVs).The remaining high pressure injection systems are unable to maintain reactor water level which is currently at (-)150 inches and lowering.Which ONE of the following contingency

procedures

would be the next EOI procedure to execute?A.2-EOI-C1,"Alternate

Level Control." B.2-EOI-C2,"Emergency

RPVDepressurization"ONLY.

C.2-EOI-C4,"RPV Flooding." D.2-EOI-C5,"Level/Power

Control.II Thursday, March 20, 2008 11:17:00 AM 55

0610 RO Final Examination

56.A hydraulic ATWS has occurred on Unit 2 and the Operator At-The-Controls

is inserting control rods in accordance

with the following:

• EOI Appendix 1 D,"Insert Control Rods Using Reactor Manual Control System,"*EOI Appendix 1 F,"Manual Scram," and*EOI Appendix 2,"Defeating

ARI Logic Trips." During execution of these appendices,

A.ALL potential Control Rod Insert Block signals are bypassed.B.Rod Drift indication

is received once rod motion has begun.C.Stabilizing

Valves are OPEN to provide increased drive water pressure.D.ALL Reactor Manual Control System (RMCS)timer functions are bypassed except for the Settle Bus Timer.Thursday, March 20, 2008 11:17:00 AM 56

0610 RO Final Examination

57.Given the following plant conditions:

• Unit 2 has experienced

a LOCA with a loss of Primary Containment.

• You have volunteered

for a team, dispatched

from the Operations

Support Center (OSC), that will enter the Reactor Building and attempt to energize'20'480V RMOV board.*Due to environmental

and radiological

conditions

present in the Reactor Building, Radiation Protection

personnel provide each team member with a Sodium Chloride (NaCI)and Potassium Iodide (KI)tablet during the briefing.Which ONE of the following describes the benefit of ingesting Potassium Iodide prior to the Reactor Building entry?Potassium Iodide will reduce the (1)and Sodium Chloride will reduce the (2).A.('1)risk of dehydration

and heat stress.absorption

ofradioactiveIodine

by the thyroid.B.)absorption

ofradioactiveIodine

in the lungs.absorption

of radioactive

Strontium in the bones.C.absorption

of radioactive

Iodine by the thyroid.risk of dehydration

and heat stress D.)absorption

of radioactive

Strontium in the bones.absorption

ofradioactiveIodine

in the lungs.Thursday, March 20, 2008 11:17:00 AM 57

0610 RO Final Examination

58.Which ONE of the following describes the appropriate

fire extinguishing

agent for the specific class of fire that will minimize subsequent

damage to equipment?

A.Water used on Class'B'fires.B.Low pressure C02 used on Class'c'fires.C.Dry Chemical (PKP)used on Class'C'fires.D.Aqueous Film Forming Foam (AFFF)used on Class'A'fires.Thursday, March 20, 200811:17:01

AM 58

0610 RO Final Examination

59.Given the following Unit 1 plant conditions:

• Due to multiple high pressure injection system failures, 1-EOI-C1,"Alternate

Level Control" has been entered.*RHR Pump'1 A'is running and lined up for LPCI injection.

• Core Spray Pumps'1 B'and'1 D'are running and lined up for injection.

• Drywell Temperature

is 240 OF and rising slowly.Which ONE of the following conditions

describes the appropriate

point where Emergency Depressurization

may be performed in accordance

with 1-EOI-C1,"Alternate

Level Control?" Post Accident Flooding Range Level Instrument, 3-LI-3-52, is reading (1)with reactor pressure at (2)REFERENCES

PROVIDED (1)A.(-)205 inches;350 psig B.(-)210 inches;500 psig C.(-)220 inches;900 psig D.(-)225 inches;800 psig Thursday, March 20, 2008 11:17:01 AM 59

0610 RO Final Examination

60.Given the following plant conditions:

• Unit 2 is Operating at full power.*Ground isolation is in progress on 2C 480 Volt RMOV Board.*Troubleshooting

will require the Drywell Blowers, that are powered from this board, be removed from service.Which ONE of the following is the highest Drywell Air Temperature

before troubleshooting

should be stopped and the reason for this limitation.

Maintain Drywell Air Temperature

at or below (1)to ensure (2)A.(1)150 of;the Design Basis Analysis remains valid by limiting the initial conditions.

B.(1)150 of;equipment for accident mitigation

is available under accident conditions.

the Design Basis Analysis remains valid by limiting the initial conditions.

D.(1)160 of;equipment for accident mitigation

is available under accident conditions.

Thursday, March 20,200811:17:01

AM 60

0610 RO Final Examination

61.Which ONE of the following describes why the Automatic Depressurization

System (ADS)is inhibited once Standby Liquid Control injection has begun in accordance

with EOI-1,"RPV Control" path RC/Q?A.The operator can control reactor vessel pressure better than ADS.B.ADS actuation would impose a severe pressure and temperature

transient on the reactor vessel.C.Severe core damage from a large power excursion could result.D.If only steam driven high pressure injection systems are available, an ADS actuation could lead to a loss of adequate core cooling.Thursday, March 20,200811:17:01

AM 61

0610 RO Final Examination

62.Unit 2 was at 1000/0 rated power when a spurious Group I Isolation occurred.The pressure transient caused a small-break

LOCA to occur inside the Drywell.Which ONE of the following describes the basis for actions with respect to 12 psig Suppression

Chamber Pre'ssure?

A.Drywell sprays must be initiated prior to this pressure to prevent opening the Suppression

Chamber to Reactor Building vacuum breakers and de-inerting

the containment.

B.Drywell sprays must be initiated above this pressure because almost all of the nitrogen and other non-condensible

gases in the drywell have been transferred

to the torus and chugging is possible.C.Above this pressure indicates that almost all of the nitrogen and other non-condensible

gases in the torus have been transferred

to the drywell air space and Suppression

Chamber Sprays will be ineffective.

D.Above this pressure indicates that almost all of the nitrogen and other non-condensible

gases in the drywell have been transferred

tothetorus so initiating

Drywell Sprays may result in containment

failure.Thursday, March 20, 200811:17:01

AM 62

0610 RO Final Examination

63.Given the following plant conditions:

• Unit 2 experiences

a Main Steam Line break at full power.*Both Inboard and Outboard Main Steam IsolationValves(MSIVs)

on the'B'steam line fail to isolate.*The reactOr scrams and ALL rods fully insert.*Steam Leak Detection Panel 9-21 indications

are as follows:-2-TI-1-60A

-2-TI-1-60B-2-TI-1-60C

-2-TI-1-60D

320 of 323 of 337 of 318 of*NO other temperature

indications

are alarming.*Area Radiation Monitor indications

are as follows:-2-RM-90-22A

indicates 1 000 mr/hr-2-RM-90-21A

indicates 730 mr/hr-2-RM-90-20A

indicates 800 mr/hr*NO other Area Radiation Monitors are alarming.Which ONE of the following describes the appropriate

operator actions and the reason for those actions?REFERENCE PROVIDED A.Emergencydepressurize

the reactor due to two (2)areas being above Max Safe in 2-EOI-3,"Secondary

Containment

Control." B.Enter 2-EOI-1,"RPV Control" due to one (1)area being above Max Safe in 2-EOI-3,"Secondary

Containment

Control." C.Rapidly depressurize

the reactor due to one (1)area above Max Safe and one (1)area approaching

Max Safe in 2-EOI-3,"Secondary

Containment

Control." D.Enter 2-GOI-1 00-12A,"Unit Shutdown" and commence a normal cooldown due to a primary system discharging

outside Primary Containment.

Thursday, March 20, 2008 11:17:01 AM 63

0610 RO Final Examination

64.Given the following plant conditions:

• Unit 2 is at 1000/0 rated power.*A Reactor Water Cleanup (RWCU)drain line cracks and is spilling into the Reactor Building.*Area Radiation Monitors in the Reactor Building read as follows: Reactor Building Elevation 593 Reactor Building Elevation 565 West Reactor Building Elevation 565 East Reactor Building Elevation 565 Northeast All other Reactor Building areas>1000 mRlhr 800 mRlhr 850 mRlhr>1000 mRlhr NOT ALARMED*Approximately

one (1)minute later, RWCU is successfully

isolated.Which ONE of the following describes the required action that MUST be directed by the Unit Supervisor

and/or Shift Manager?REFERENCE PROVIDED A.Enter 2-EOI-1,"RPV Control" and initiate a Reactor Scram.B.Scram the reactor and Emergency Depressurize

the reactor.C.Rapidly depressurize

the reactor, to the Main Condenser, with the Main Turbine Bypass Valves.D.Enter 2-GOI-1 00-12A,"Unit Shutdown" and commence a normal shutdown/cooldown.Thursday, March 20, 2008 11:17:01 AM 64

0610 RO Final Examination

65.Given the following plant conditions:

• Unit 2 is at 100%power.*During the backwash of a Reactor Water Cleanup (RWCU)Demineralizer, the Backwash Receiving Tank ruptured.*The RWCU system has been isolated.*Secondary Containment

conditions

are as follows:-ALL Reactor and Refuel Zone radiation monitors trip on high radiation.

-ONLY Standby Gas Treatment (SGT)train'c'can be started.It is operating at 10,000 scfm and taking suction on the Refuel and Reactor Zones.-Refuel zone pressure:-Reactor zone pressure:-AREA RADIATION LEVELS RB EL 565 W, 565 E, 565 NE: RB EL 593 RB EL 621 (-)0.12 inches of water (+)0.02 inches of water 250 mr/hr upscale upscale Which ONE of the following describes the required action and the type of radioactive

release in progress?REFERENCE PROVIDED A.Initiate a shutdown per 2-GOI-100-12A,"Unit Shutdown." An Elevated radiation release is in progress.B.Initiate a shutdown per 2-GOI-1 00-12A,"Unit Shutdown." A Ground-level

radiation release is in progress.C.Scram the reactor and Emergency Depressurize

the RPV.An Elevated radiation release is in progress.D.Scram the reactor and Emergency Depressurize

the RPV.A Ground-level

radiation release is in progress.Thursday, March 20,200811:17:01

AM 65

0610 RO Final Examination

66.Which ONE of the following describes the protective

function(s)

required to be OPERABLE for the specified mode and/or condition?(Each list is NOT all inclusive)

A.Starting up in Mode 2 with IRM's on range 1 to 2: IRM Hi Scram function Banked Position Withdrawal

Sequence (BPWS)Rod Block Monitor (RBM)APRM Hi (setdown-15%).B.Starting up in Mode 2 with APRM downscales

clear: APRM Hi (setdown-15%)APRM Hi (120%)Mode Switch-Shutdown position Rod Worth Minimizer (RWM).c.Shutting down in Mode 2 with IRM's on range 1 to 2: IRM Hi Scram function Banked Position Withdrawal

Sequence (BPWS)Manual Scram push buttons Rod Worth Minimizer (RWM).D.Shutting down in Mode 2 with average SRM readings at-5x10.1 cps: IRM Hi Scram function APRM Hi (setdown-15%)OPRM upscale trip Rod Worth Minimizer (RWM).Thursday, March 20, 200811:17:01

AM 66

0610 RO Final Examination

67.Which ONE of the following announcements

is the correct method for making an announcement

using the Plant Paging System in accordance

with OPDP-1,"Conduct of Operations?" A."This is a drill.All personnel evacuate the Unit 2 Reactor Building due to high radiation, all personnel evacuate the Unit 2 Reactor Building due to high radiation.

" B."This is a drill.All personnel evacuate the Unit 2 Reactor Building due to high radiation.

This is a dri11." C."This is a drill.All personnel evacuate the Unit 2 Reactor Building due to high radiation, all personnel evacuate the Unit 2 Reactor Building due to high radiation.

This is a drilL" D."All personnel evacuate the Unit 2 Reactor Building due to high radiation.

This is a drill.All personnel evacuate the Unit 2 Reactor Building due to high radiation.

This is a drilL" Thursday, March 20, 2008 11:17:01 AM 67

0610 RO Final Examination

68.Which ONE of the following is the appropriate

method for documenting

a"Late Entry" in the Operator's

Station Log in accordance

with OPDP-1,"Conduct of Operations" after the log turnover has been completed?

Each"Late Entry" SHALL contain the words LATE ENTRY,__(_1__)_the entry that was missed from the previous shift.A.(1)The Current Time.(2)The operator's

name who missed the original entry.B.(1)The operator's

name on shift when the"Late Entry" was made.(2)The time the entry should have been made.C.(1)The operator's

name on shift when the"Late Entry" was made.(2)The operator's

name who missed the original entry.D.(1)The Current Time.(2)The time the entry should have been made.Thursday, March 20, 2008 11:17:02 AM (2), and 68

0610 RO Final Examination

69.In accordance

with SPP-10-2,"Clearance

Procedure to SafelyControlEnergy," which ONE of the following describes the requirements

when placing a clearance on Air-Operated

Valves (AOVs)?An Air-Operated

Valve that fails_A."OPEN" on loss of air, shall have its air supply electrically

or mechanically

isolated and the air supply must be tagged.B."OPEN" on loss of air, shall be held closed with a gagging device that is tagged as a clearance boundary.C."AS-IS" on loss of air shall NOT be used for blocking purposes until it is verified closed and a gagging device installed.

D."CLOSED" on loss of air shall NOT be considered

closed for blocking purposes unless it is held closed with a gagging device.Thursday, March 20,2008 11:17:02 AM 69

0610 RO Final Examination

70.Given the following plant conditions:-A reactor startup is in progress with power currently at 3%-Rod Worth Minimizer (RWM)is latched into Group 8 (12 control rods)-Group 9 rods are the same rods as Group 8.-Sequence Control: ON-Group 8 Limits: 08-12-Group 9 Limits: 12-16 Which ONE of following sets of conditions

describes when the RWM will automatically

latch up to Group 9?A.ALL rods EXCEPT 1 in group 8 are withdrawn to Notch 12 and the final rod is withdrawn to Notch 14.ALL rods EXCEPT 2 in group 8 are withdrawn to Notch 12, and a rod in group 9 is selected.B.ALL rods in group 8 have been withdrawn to Notch 12 and a rod in group 9 is selected.ALL rods EXCEPT 2 in group 8 are withdrawn to Notch 12, and a rod in group 9 is selected.C.ALL rods EXCEPT 1 in group 8 are withdrawn to Notch 12 and the final rod is withdrawn to Notch 14.All rods in group 8 are withdrawn to Notch 12 and the in-sequence

rod in group 9 has NOT been selected.D.All rods in group 8 are withdrawn to Notch 12 and the in-sequence

rod in group 9 has NOT been selected.ALL rods EXCEPT 1 in group 8 are withdrawn to Notch 12 and the final rod is withdrawn to Notch 14.Thursday, March 20,200811:17:02

AM 70

0610 RO Final Examination

71.Given the following conditions

at a work site.Airborne activity: 3 DAC Radiation level: 40 mr/hr Radiation level with shielding:

10 mr/hr Time to place shielding:

15 minutes Time to conduct task with respirator:

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Time to conducttaskwithout

respirator:

30 minutes Assume the following:

-the airborne dose with a respirator

will be zero (0).-a dose rate of 40 mr/hr will be received while placing the shielding.

-all tasks will be performed by one worker.-shielding can be placed in 15 minutes with or without a respirator.

Which ONE of the following would result in the lowest whole body dose?A.Conduct the task WITHOUT a respirator

or shielding.

B.Conduct the task with a respirator

and WITHOUT shielding.

C.Place the shielding while wearing a respirator

and conduct the task with a respirator.

D.Place the shielding while wearing a respirator

and conduct the task WITHOUT a respirator.

Thursday, March 20,2008 11:17:02 AM 71

0610 RO Final Examination

72.Unit2 reactor shutdown is in progress and primary containment

de-inerting

has been authorized.

Which ONE of the following is the basis for preventing

the simultaneous

opening of BOTH the SUPPR CHBR ATM SPLY INBD ISOLATION VLV (2-FCV-64-19)

and the DRYWELL ATM SUPPLY INBD ISOLATION VLV (2-FCV-64-18

)during the performance

of this evolution?To prevent the high flow rate from causing unplanned damage to the non-hardened

ventilation

ducts during a LOCA.B.To prevent the possibility

of overpressurizing

the primary containment

during a LOCA.C.To prevent release of the drywell atmosphere

through an unmonitored

ventilation

flow path during a LOCA.D.To prevent creating a high differential

pressure between the drywell and the torus air space during a LOCA.Thursday, March 20,2008 11:17:02 AM 72

0610 RO Final Examination

73.Given the following plant conditions:

• Reactor pressure is being maintained

at 25 psig.*Temperature

near the water level instrument

run in the Drywell is 265 of.*The Shutdown Vessel Flooding Range Instrument (LI-3-55)is reading (+)35".Which ONE of the following describes the highest Drywell Run Temperature

at which the LI-3-55 reading (+)35 inches is considered

valid?REFERENCE PROVIDED A.200 of B.250 of c.265 of D.300 of Thursday, March 20, 2008 11:17:02 AM 73

0610 RO Final Examination

74.Given the following plant conditions:

• Unit 2 has scrammed and multiple control rods failed to insert.*The Unit Supervisor

has entered 2-EOI-1,"RPV Control", and 2-EOI-C-5,"Level/Power

Control."*You have been designated

to assist the crew by performing

EOI Appendicies

as they are assigned.Which ONE of the following precludes the use of a handheld radio to communicate

with Control Room personnel?

A.2-EOI Appendix 2 in the 2A Electrical

Board Room.B.2-EOI Appendix 16H at the'2C'250V RMOV Board.C.2-EOI Appendix1C in the Auxiliary Instrument

Room.D.2-EOI Appendix1B on the Reactor Building 565'Elevation.

Thursday, March 20, 2008 11:17:02 AM 74

0610 RO Final Examination

75.Which ONE of the following describes the use of Event-Based

procedures

during Symptom-Based

Emergency Operating Instructions (EOI)execution?

Event-Based

procedures

are_A.NOT used during Symptom-Based

EOI execution.

B.ONLY used if specifically

directed by an EOI flowchart step.c.ONLY used if they do NOT interfere with EOI implementation.

D.MUST be used if equipment or plant status require their implementation.

You have completed the test!Thursday, March 20, 2008 11:17:02 AM 75