ML020510571

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Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

8. 4-25 002/ 3,4/ / 0680103002/ G2.3.11/ 2.7/3.2/ 33-[2/3]/ RM

The following conditions exist:

-

The plant is in Mode 5.

-

The "A" decay heat removal train is in operation.

-

The Nuclear Services Closed Cycle Cooling Raw Water (SW-RW) system has

been shutdown to repair a leak in the common RWP discharge piping.

The Primary Plant Operator (PPO) reports that he is trying to start a primary side release but

can not get WDV-892, Liquid Release Discharge Isolation Valve, to open.

Which of the following describes the operation of WDV-892 under these conditions?

A.

WDV-892 should open as long as RM-L2 is not in high alarm.

B.

WDV-892 will not open if SDV-90, SDT-l Release Isolation Valve, is open.

C.

WDV-892

running.

should open as long as RWP-3A, Decay Heat Raw Water Pump, is

"D.

WDV-892 will not open unless RM-L2/7 bypass is in bypass.

Reasons:

A. WDV-892 should open as long as RM-L2 is not in high alarm. For WDV-892 to

open you must have RM-L2 reset and one of the RW-SW pump running OR

RM-L2 reset and the RM-L2/7 bypass switch is in bypass.

B. WDV-892 will not open if SDV-90 is open. There are no interlocks between

SDV-90 and WDV-892. SDV-90 does use the RM-L2/7 bypass key switch.

C. WDV-892 should open as long as RWP-3A is running. The interlock for

WDV-892 uses only contacts from RWP-1, RWP-2A, or RWP-2B. SDV-90 uses

contacts from RWP-3A or RWP-3B.

D. Correct, WDV-892 will not open unless RM-L2 reset and one of the RW-SW

pump running OR RM-L2 reset and the RM-L2/7 bypass switch is in bypass,

neither of these conditions are met.

I/

Page: 10

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

8. 4-25 002/ 3,4// 0680103002/ G2.3.1 / 2.7/3.2/ 33-[2/31/ RM

NOB 2002 NRC exam KEH 10/12/01

LOI-99-01 FPCF; LOI1-T8AR/T8AS; LOI1-T8BR/T8BS

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

13,4

1

k680103002

IG2.3.1,1

.7

13.2

b3-[2/31

ANSWERS:

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IIKEICIKABCDA

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Page: II

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

9. 4-28 001/ 4// 0010102011/ 001A4.04/ 3.9/ 3.6/ 33-[1]/ CRD

Given the following plant conditions:

-

All Integrated Control System (ICS) stations are in "automatic".

- Reactor power is 100%.

It is desired to adjust power imbalance using the Axial Power Shaping Rods (APSRs).

Which of the following is the minimum action required for all the APSRs to respond to the

IN/OUT switch?

A.

The diamond control station must be placed in "Manual" and "Group Select

Switch" must be selected to "Group 8" position.

B.

"Sequence Override" must be selected at the diamond control station and "Group

Select Switch" must be selected to "Group 8" position.

C.

The "Single Select Switch" must be in "All" and "Group Select Switch" must be

selected to "Group 8" position.

,D.

The "Group Select Switch" must be in the "Group 8" position.

OP-502 Section 4.5

A,B,C: Group 8 may be moved manually without disturbing AUTO operations, only need to

select group 8 on the group select switch and they are at the control of the operator.

NRC 11-93; CP FPC final; ROTs M - 5B; ROTs N - FPCF; ROTs 0 - T5

ADDITIONAL K/A 014A4.02 3.4/3.2

BANK QUESTION 2002 NRC EXAM (RO ONLY) 5/10/2001 KEH

BANK

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

14

1

10010102011

001A4.04

9

13.6

b3-1

CR0

ANSWERS:

Points

=

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D

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d

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

10. 4-28 002/ 3/ /0010102009/ 014A2.04/ 3.4/3.9/ 33-[1]/ CRD

Given the following plant conditions:

-

Group 7, Rod 3 (Rod 7-3) had been previously stuck.

-

Rod 7-3 has been freed using procedure OP-502.

-

The Relative Position Indication (RPI) on the Position Indication (PI) panel for

does not agree with its Absolute Position Indication (API).

Page: 12

Rod 7-3

What is required to realign Rod 7-3 RPI to match Rod 7-3 API?

A.

Move all group 7 rods to Rod 7-3 API and realign all group 7 rods with Rod 7-3

RPI.

B.

Insert all group 7 rods to the in-limit and realign all the rods to the Zero position,

using RPI.

C.

Withdraw all group 7 rods to the nearest zone indicating lamp and realign all group

7 rods (API and RPI) to the zone reference indication.

"-D.

Select Rod 7-3 on the group and single select switch, and use the reset pulser to

align RPI with API.

OP-502 section 4.18

A,B,C: RPI is a stepping motor that must be electrically reset to the actual position. Due to

freeing the stuck rod the motor would have moved without the rod actually moving.

NRC 11-93; ROT-4-28 B15 & B16; ROTs J - TlOA; CP FPC final; ROTs M - T7; ROTs N

T2 & T2A; ROTs 0 - T5

ADDITIONAL K/A 005A 1.05 3.4/3.4

BANK QUESTION 2002 NRC EXAM (RO ONLY) KEH 5/10/2001

BANK

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO

13

1

10010102009

1014A2.0

ANSWERS:

Points

=

Import

Initial/Re

4

13.4

13.9

133"41]

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Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

Page: 13

11. 4-29 001/6//0330103008/033K3.03/3.0/3.3/88-[1i/SF

The following plant conditions exist:

- Spent fuel pool temperature is increasing.

-

Spent fuel pool boron concentration is constant.

-

Nuclear Services Surge Tank, SWT-1, low-low level alarm has been received.

The spent fuel pool:

A.

B.

C.

has an increased number of fuel assemblies.

ventilation has been secured.

level is decreasing.

1D.

cooling has been lost.

A- SWT level would not be affected from fuel assemblies added

B- Ventilation would not affect temperature fast enough to see a rise

C- Level decreasing would not be in the SFP with SWT level decreasing

D- Correct. A level decrease in SWT would tend toward a loss of SW and loss of cooling

NRC 11-93; CP FPC final; ROTs M - T4

BANK QUESTION 2002 NRC EXAM (RO ONLY) KEH 5/10/2001

BANK

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

16

10330103008

033K3.03

b.0

.3

88-11

sF

ANSWERS:

Points

=

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D

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

Page: 14

12. 4-31 001 / 2//0190502002/ 035K4.01/ 3.6/3.8/ 33-[2/3]/

Following an overcooling accident the following conditions exist:

- EFIC has actuated

- EFIC has been bypassed on all 4 channels

- EFW is the only FW source to the OTSGs

- "A" OTSG level is 14".

- "A" OTSG pressure is 400 psig.

- "B" OTSG level is 32".

- "B" OTSG pressure is 900 psig.

- RCS pressure is 1900 psig

- RCP-1A is shutdown.

Which of the following describes how EFIC will control the fill rate for "A" OTSG?

,'A.

EFIC will attempt to fill the "A" OTSG as quickly as possible (no rate limit) until

Low Level Limit conditions are established.

B.

EFIC will attempt to fill the "A" OTSG as quickly as possible (no rate limit) until

OTSG pressure is above 600 psig.

C.

EFIC will raise the level in "A" OTSG at a rate between 2" and 8" per minute based

on OTSG pressure.

D.

EFIC will raise the level in "A" OTSG at a rate between 2" and 8" per minute based

on RCS cooldown rate.

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

12. 4-31 001 / 2//0190502002/ 035K4.01/ 3.6/3.8/ 33-[2/31/

Reasons:

A. Correct: The "A" OTSG is has no rate limit restriction other than the

cavitating venturis because the level is below LLL and at least one RCP is

running. FOGG is not a factor in the feeding of the OTSGs because EFIC

has been bypassed, removing the FOGG logic.

B. The "A" OTSG is has no rate limit restriction other than the

cavitating venturis because the level is below LLL and at least one RCP is

running. However, this control method does not end based on OTSG pressure

It will continue until Low Level Limits are established or all RCPs are

shutdown.

C. Below Low Level Limits with RCPs in operation the

effect.

D. Below Low Level Limits with RCPs in operation the

effect.

2"-8" ramp rate is not in

New question written for Sept 2000 RO and SRO exam. (3-22-2000 mg)

REPEAT

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Imp

12

10190502002

135K4.01

3.6

h.8

ANSWERS:

Version Answers:

Points

1B0123456789

SPoints[

i]

Z~IKIZ

I IIIB c IA IABI

ort

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System

b3-tz3]

I

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Page: 15

w

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

Page: 16

13. 4-37 001/2//0600502001/061K1.01/4.1/4.1/33 [1]/AFW

Which of the following identifies the seismic class isolation between the Auxiliary Feedwater

Pump (FWP-7) and the OTSG system?

AFW pump discharge valve FWV-215.

AFW control valves FWV-216/217.

AFW isolation valves FWV-222/223.

AFW check valves FWV-269/270.

A. This valve is normally open at the pump discharge and is not the class isolation.

B. These control valves are normally closed however, they are not class isolation valves.

C. These manual isolation valves are normally open and are not used as class isolation valves.

D. CORRECT: these safety grade check valves are used as the class isolation vavles.

NEW 2002 NRC EXAM KEH (INPO BANK) 8/28/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

12

1

b600502001

I106 K1.Q1

.1

k.1

h3 11

FW

ANSWERS:

Points

"-

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wd

A.

B.

C.

v/D.

Friday, January 18, 2002 @ 06:52 AM

I2KKU.SINJX

14. 4-60 001 / 7/ / 0020202002/ 003A2.01 / 3.5/ 3.9/11 -[2/31/ RCP SEAL

Given the following plant conditions:

The plant is operating at 100% power

Slowly over the last month RCP seal parameters have been changing

The following is todays RCP seal data:

RCP SEAL STAGE PRESSURE (psig)

RCP-1A

2nd

3rd

Time

Stage

0100

0400

0700

1000

1300

Dumpster

clicks per

minute at

1300.

1300

1325

1300

1325

1350

3

700

725

700

725

RCP-1B

2nd

Stage

3rd

Stage

1400

1375

1400

2

RCP-1C

2nd

Stage

800

825

800

3rd

Stage

1550

1575

1550

1575

3

RCP-1D

2nd

3rd

Stage

900

925

950

1035

1125

1425

1400

1450

2

Based on the above data which of the following describes the proper course of action?

A.

Immediately trip RCP-1C and go to AP-545, Plant Runback.

B.

Reduce power to < 90% per AP-5 10, Rapid Power Reduction, trip RCP-IC and go

to AP-545, Plant Runback.

eC.

Reduce power to < 72% per OP-204, Power Operations, and trip RCP-1C.

D.

Immediately trip the reactor and enter EOP-02, Vital System Status, monitor

RCP-1C per OP-302, RCP Operations.

Page: 17

725

775

800

A TT" A lrlk A

lr*l lk TT*

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

Page: 18

14. 4-60 001 / 7// 0020202002/003A2.01 / 3.5/3.9/11 -[2/3]/RCP SEAL

Reasons:

A., B. & D.

RCP-1C total seal leakage is 2.55 gpm and increasing gradually.

Per OP-302, RCP Operation, the correct action is to reduce power

to < 72% per OP-204, Power Operations, and trip RCP-IC.

From Enclosure 3 CBO flow is 1.88 gpm and Dumpster flow is .7 gpm from enclosure 4. The

two are added together to be 2.58 gpm and the flow has increased gradually. OP-302 has the

power reduced and trip RCP when >2.5 gpm. OP-302 step 4.7.2.4

Provide OP-302; ROTs 0 - T13, NRCM;

ADDITIONAL K/A 015AK2.07 2.9/2.9

MODIFIED 5/10/2001 KEH READY TO USE ON NRC EXAM 2002 (RO ONLY)

MODIFIED BANK

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

17

1

b020202002

1003A2.01

.5

.9

11-2/31

IRPSEAL

ANSWERS:

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N

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Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

Page: 19

15. 4-60 002/3,4,8// 0020302001 / 010K2.03/ 2.8/ 3.0/33 [1]/ PORV

Given the following plant conditions:

Loss of Main Feedwater

Reactor Trip

PORV opened and then closed

"PORV Safety Valve Open" alarm (1-5-1) is actuated

Which of the following will reset and clear the "PORV Open" alarm?

A.

B.

C.

"/D.

A.

B.

C.

D.

Manually depress the alarm acknowledge pushbutton.

Automatically will reset once the ultrasonic monitor needle drops back below the

red portion of the meter.

Automatically will reset once tailpipe temperature decreases below 150'F.

Manually reset in Tsat cabinet in the "B" ES 4160V switchgear room.

The alarm is locked in until reset in the 4160V SWGR room.

No auto reset from ultrasonic, the slide bar alarm setpoint will reflash the alarm.

No auto reset from tailpipe temperatures.

CORRECT: This alarm locks in, and must be reset locally in "B" 4160V SWGR room.

NEW 2002 NRC exam KEH 10/4/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

13,4,8

1020302001

Io 02.c

ANSWERS:

Points [4

RO Import.

SRO Import

Initial/Re

.8

3.0 o3

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0

Friday, January 18, 2002 @ 06:52 AM

16. 4-61 001/ 9// 0710403004/071 K5.04/ 2.5/ 3.1/11-[2/31/

During normal operation, you receive the following sample results on WDT-1A,

Gas Decay Tank.

the "A" Waste

Hydrogen concentration is 6% by volume.

Oxygen concentration is 3% by volume.

Which of the following describes the required actions for this condition?

A.

Without delay take action to reduce the hydrogen concentration to less than 4%.

Waste gas additions to the tank may continue.

B.

Without delay take action to reduce the hydrogen concentration to less than 4%.

Immediately suspend all waste gas additions to the tank.

'C.

Without delay take action to reduce the oxygen concentration to less than 2%.

Waste gas additions to the tank may continue.

D.

Without delay take action to reduce the oxygen concentration to less than 2%.

Immediately suspend all waste gas additions to the tank.

Reasons:

A. Per the ODCM, actions are taken to reduce oxygen concentration, not

hydrogen.

B. The ODCM does not prohibit waste gas additions.

C. Correct, per ODCM 2.18.

D. The ODCM does not prohibit waste gas additions.

Provide the ODCM; New question written for LOI-99-01 SRO and RO Audit exam. (8-2-2000

jo)

BANK

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

9

0710403004

071K5.04

.5.1

11-[2/3

I

Page: 20

2K2RO.BNK

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

Page: 21

16. 4-61 001/ 9/ / 0710403004/071 K5.04/ 2.5/3.1/ 11-[2/3]/

ANSWERS:

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Points

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DI AI

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Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

Page: 22

17. 4-92 001/ 5//1150102003/COCG2.1.17/3.5/3.6/33-[11/AI-412

The Superintendent Shift Operations (SSO) directs you, with a face to face communication, to

line up the "B" Make-Up Pump (MUP-i B) for a surveillance.

What communication requirement is NOT necessary for this exchange?

The use of:

A.

Repeat backs or paraphrasing the message.

"*B.

Title/name identifiers.

C.

Confirmation from the SSO.

D.

Proper names and equipment numbers.

A. Required per AI-412.

B. CORRECT: This may be deleted when face to face communication is used.

C. Required per AI-412.

D. Required per AI-412.

OPSA1.BNK 2002 NRC exam KEH 10/13/01

NRC 11-93; CP FPC final; ROTs M - T6A; ROTs M - T6B; ROTs N

T4B & T4BA

- T4 & T4A; ROTs N -

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

15

1

11150102003

ICOCG2.1.17 ý.5

h.6

13-[1]

,1-412

Version Answers:

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IP nC ID I1A IB ICF

lW

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[

ANSWERS:

Points

=*

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

Page: 23

18. 5-01 001/ 9/ / 1190302001 / ECG2.2.25/ 2.5/3.7/33 [1]/ ITS

Given the following plant conditions:

Loss of Offsite Power

Loss of all feedwater

Reactor does not trip

RPS failure

RCS is on the safety limit curve (figure 2.1.1-1) at 2090 psig, 620'F.

Which of the following would move the plant by the largest margin into the acceptable region

of the Safety Limit curve?

A.

Increase pressure; increase temperature.

vB.

Increase pressure; decrease temperature

C.

Decrease pressure; decrease temperature.

D.

Decrease pressure; increase temperature.

A. This moves you along the line that you are already sitting on.

B. CORRECT: This will move you both up and to the right from the curve into the acceptable

region which is to the right side of the curve.

C. This moves you along the line that you are already sitting on.

D. This will move you farther into the unacceptable region.

NEW 2002 NRC exam KEH 10/4/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

19

11190302001

ANSWERS:

Points

K/A

RO Import.

JECG2.2.25

12.5

Version Answers:

0123456

SRO Import

Initial/Re

System

.7

133 [1

ITS

789

E Scramble Choices

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d

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

Page: 24

19. 5-01 002/ 2//1190302001/ 2.2.22/ 3.4/4.1/33 [1]/ SP-317

Which of the following will require initiation of a reactor shutdown per Technical

Specifications?

A.

B.

C.

"vD.

Unidentified RCS leakage of 0.4 gpm.

Identified RCS leakage of 4.0 gpm.

RCP Controlled Bleed off flow of 8.0 gpm.

Primary to Secondary leakage of 1.4 gpm.

A. ITS and SP-317 is 1.0gpm

B. ITS and SP-317 is 10.Ogpm

C. SP-317 is 10.Ogpm

D. CORRECT: ITS 3.4.12 and SP-317 is .lgpm (150gpd)

NEW 2002 NRC EXAM KEH (INPO BANK) 8/28/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

12

1

11190302001

1.2.22

h.4

k.1

h3 [11

ISP-317

ANS*RWSn.

Version Answers:

0123456789

IDPointsIDAIB CDICIA

E Scramble Choices

Scramble Range: A -

Points[=

Friday, January 18, 2002 @ 06:52 AM

20. 5-100 001/ 5//1150502011/ 055EA2.04/ 3.7/4.1/33 [1]/ EOP-12

Which of the following component(s) is stopped/secured within 30 minutes of the initiating

event, per EOP-12, "Station Blackout" to reduce the drain on the IE station batteries?

TBP-3 Turbine-generator bearing oil pump.

VBIT- 1E Inverter.

TBP-10 Generator air side seal oil pump.

D.

MUP-5A/B/C Makeup pump backup gear oil pumps.

A. This is not an 1E battery supply

B. This is for heat requirements not battery drain.

C. This is not an IE battery supply

D. CORRECT: these are from DPDP5A/5B and are stopped W/I 30 minutes.

NEW 2002 NRC EXAM KEH (IINPO BANK) 8/28/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

15

1

11150502011

I55EA2.04

.7

.1

3 1

EOP-12

AKIOC10l.

Version Answers:

Points

=

0 1 2 3 4 5 6 7 8 9

ED Scramble Choices

ID IA 1B [C ID JA 1B IC ID JA

Scramble Range: A-

R

A.

B.

C.

Page: 25

2K2RO.BNK

Friday, January 18, 2002 @ 06:52 AM

21. 5-101 001/3// 1150502005/ 038EA2.15/4.2/4.4/33 [1]/ EOP-6

EOP-6, Steam Generator Tube Rupture, step 3.17 sates:

IF at any time, adequate SCM exists,

THEN maintain minimum adequate SCM.

Which of the following is the reason for minimizing SCM?

A.

Ensure MSSV's remain closed.

B.

Prevent reactor head bubble formation.

"C.

Minimize primary to secondary leakage.

D.

Maximize HPI flow into the core.

A. SCM will not ensure the MSSV's remain closed

B. Head bubble formation is a function of cooldown.

C. CORRECT: Reduces the delta P for leakage

D. Will allow for more flow but not a factor in the tube rupture step.

NEW 2002 NRC EXAM KEH (INPO BANK) 8/28/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

13

1

11150502005

038EA2.1 5

.2

k.4

1

EoP6

ANSWERO.

Version Answers:

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Pn[IIAIIP D IB

o

Ic ID I

0 Scramble Choices

Scramble Range: A -

E

Page: 26

2K2RO.BNK

Points=

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

Page: 27

22. 5-103 001 / 9/ / 1150102004/G2.1.23/ 3.9/4.0/ 33-[2/3]/ MFW

Which of the following is the order in which the Main Feedwater system is placed in service

during a Plant Heatup (OP-202)?

1.

2.

3.

4.

1.

2.

3.

4.

Long cycle clean-up is completed with the Feedwater

Main Feedwater Pumps are placed on turning gear.

The Start-up Feedwater Block Valves are opened.

One Main Feedwater Pump is started.

Long cycle clean-up is completed with the Feedwater

Main Feedwater Pumps are placed on turning gear.

One Main Feedwater Pump is started.

The Start-up Feedwater Block Valves are opened.

Booster Pumps.

1. Main Feedwater Pumps are placed on turning gear.

2. Long cycle clean-up is completed with the Feedwater Booster Pumps.

3. One Main Feedwater Pump is started.

4. The Start-up Feedwater Block Valves are opened.

1. Main Feedwater Pumps are placed on turning gear.

2. Long cycle clean-up is completed with the Feedwater Booster Pumps.

3. The Start-up Feedwater Block Valves are opened.

4. One Main Feedwater Pump is started.

A.

B.

C.

,'D.

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

22. 5-103 001 / 9/ / 1150102004/ G2.1.23/ 3.9/4.0/ 33-[2/31/ MFW

Reasons:

A. Feedwater Booster Pumps are not placed in service prior to drawing a vacuum

in the condenser. Main Feedwater Pumps are placed on turning gear prior to

drawing a vacuum in the condenser. Steps 1 and 2 are reversed.

B. Steps 1 and 2 are reversed.

Startup Feedwater Block Valves are opened prior to starting the Main

Feedwater Pump so that the feedwater lines can be warmed when the bypass

valves around the Startup Feedwater Control Valves are opened. Steps 3 and 4

are reversed.

C. The Startup Feedwater Block Valves are not opened until the feedwater is

ready to be admitted to the OTSG. Steps 3 and 4 are reversed.

D. Correct, the Main Feedwater Pumps are placed on turning gear prior to

drawing a Condenser vacuum. Once vacuum is established the Feedwater

Booster Pumps are started to support cleanup. When the lines are ready to be

warmed-up and feedwater supplied to the OTSG the Startup Feedwater Block

Valves are opened. Finally one Main Feedwater Pump is started, after the line

is warm.

New question written for Sept 2000 RO and SRO exam. (3-9-2000 mg)

REPEAT

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Im

19

1150102004

JG2.1.23

ANSWERS:

port

Initial/Re

b.g

k.o

k3-[2/31

Version Answers:

0 1 2 3 4 5 6 7 8 9

[ZScrambleChoices

iIDA lB Ic ID IA lB IC ID IA

Scramble Range: A -

Page: 28

System

DI

Points=

Friday, January 18, 2002 @ 06:52 AM

IIKU.

23. 5-14 001/ 51/1190402001/ 022K3.01/ 2.9/ 3.2/ 33-(1]I Al-505

Given the following plant conditions:

- *r - n a-'

Page: 29

A Large break LOCA has occurred.

RCS temperature is 2870F.

RCS pressure is 47 psig.

RB temperature 260'F.

RB pressure is 44 psig.

Instruments qualified to which of the following standards would be used for mitigation and

operator actions for the given conditions?

"C.

D.

A. This is for design of protection systems

B. This is for fire standards

C. CORRECT: This is for EQ of instruments for mitigation and operation of EOPs and APs.

AI-505.

D. This is for training standards

NEW 2002 NRC exam KEH 10/13/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

15

1

1190402001

22K3.ol

1.9

h.2

h3-[1j

1,-505

ANSWERS:

Points[

1

Version Answers:

01234567

Ic DIAIB

II

I

8 9

E] Scramble Choices

I i

Scramble Range: A -

W

A.

B.

,BNK

Friday, January 18, 2002 @ 06:52 AM

24. 5-31 001 / 7// 1190402001/ 068G2.4.34/ 3.8/ 3.6/ 33-1]/ AP-990

Given the following plant conditions:

Fire in the cable spreading room

AP-990 has been implemented and transfer is complete

Step 3.35 states; "Notify RO to CONCURRENTLY PERFORM Enclosure 1, OTSG isolation

in this procedure."

This enclosure has the RO ensure OTSG isolation from which of the following locations?

Remotely at the electrical switchgear.

Locally at the component.

Remotely at the EFIC cabinets.

Locally at the RSD panel.

A. Isolation is completed from the EFIC panels. May or may not work depending on plant

conditions

B. Isolation is completed from the EFIC panels. To many locations and time to manually

operate each component.

C. CORRECT: Isolation is completed from the EFIC panels.

D. Isolation is completed from the EFIC panels. The valve controls are not available at the

RSD.

NEW 2002 NRC exam KEH 10/13/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

17

11190402001

1068G2.4.34

.8

13.6

13-[11

lAP-990=

ANSWERS:

Version Answers:

0123456789

PoitsIC

ID IA LBI

DJ

B IC ID I~lk~

LE Scramble Choices

Scramble Range: A-

wý

A.

B.

"VC.

D.

Page: 30

Points=

2K2RO.BNK

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

Page: 31

"25. 5-50 001/1/5-50 1/ 0340402001 / 034A4.02/ 3.5/3.9/11-[2/3]/ FH

Refueling is in progress with eight (8) fuel assemblies in the core. As the ninth assembly is

being placed in the core the following NI readings are observed:

- NI-I increases from a base count of 203 to 430 cps.

- NI- 14-N 1 increases from a base count of 250 to 480 cps.

- NI-2 and NI-15-NI are out-of-service.

Which of the following actions, if any, should be taken by the refueling supervisor?

A.

No action is required, this is an expected NI response.

B.

Once the assembly is placed in the core, reactor engineering should be contacted to

perform a subcritical multiplication.

C.

Cease insertion of the fuel assembly and submit a sample request for boron

concentration of the reactor coolant system.

'D.

Withdraw the fuel assembly, stop any other core alterations in progress, perform

Co/Ci calculations, and obtain a boron analysis.

Reasons:

A. An action is required, count rate has increased by more than 1.5 times. The

required action for an NI increase of this type is to withdraw the fuel assembly

in question, immediately cease all other core alterations, perform a subcritical

multiplication and obtain a boron analysis of the RCS.

B. The assembly should not be placed into the core.

C. The fuel assembly being inserted should be removed, not just cease insertion.

D. Correct, the fuel assembly should be removed, core alterations suspended and

an engineering evaluation performed.

NOB 2002 NRC exam KEH 10/12/01 TASK# 1150101004

FP-203 Step 3.2.1.1.1 (SUPPLY FP-203)

(NOB [4-26 002 obj 4,7])

LOI-99-01 FPCF; LOII-T9BS

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

25. 5-50 001/1/5-50 1/0340402001/ 034A4.02/3.5/3.9/ 11-[2/3]/ FH

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO

I1 15-501

10340402001

1034A4.02

b.5

13.9

ANSWERS:

Points=

Version Answers:

01 23456789

Page: 32

) Import

Initial/Re

System

111-[2/31

IFH

[

Scramble Choices

IABCD

A

Scramble Range: A-

R

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

Page: 33

26. 5-50 002/1// 1190102008/ EQCG2.2.28/ 2.6/3.5/ 33-[1]/ FH

FP-203, Defueling and Refueling Operations, limit and precaution states,

"Irradiated fuel assemblies shall NOT be placed in the new fuel elevator regardless of the

circumstances."

Which of the following describes the basis for this limit and precaution?

A.

To prevent the top of the assembly from drying and creating an airborne radiation

hazard as the irradiated assembly is raised.

B.

To prevent exposing personnel in the SF area to a lethal dose of radiation as the

irradiated assembly is raised.

C.

To prevent damage to the new fuel elevator because of the increased weight of a

spent fuel assembly.

D.

To prevent the spent fuel assembly from being physically damaged while inside the

new fuel elevator carriage.

A. Leaving the pool would cause enough exposure versus the assembly drying.

B. CORRECT: The exposure due to the radiation levels of spent fuel.

C. The weight does not change from new to old significantly.

D. Any movement may damage a fuel assembly, but the new fuel elevator has no higher risk

associated with its operation.

OPSA1.BNK 2002 NRC exam KEH 10/13/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

11

1

11190102008

IEQGG2.2.28

ý.6

1.5

1 3-1l]

JFH

ANSWERS:

-ini

e

Points II

Version Answers:

0123456

7 8 9

E Scramble Choices

W

1BICIDIJA1ICID A1BCIC

Scramble Range: A -

Friday, January 18, 2002 @ 06:52 AM

27. 5-61 001/ 7//1150402016/ 009G2.4.24/ 3.3/3.7/ 33-[1]/ AP-330

Given the following conditions:

-

Mode 2 Reactor startup in progress at POAH.

-

Instrument Air pressure indicates 80 psig.

-

NSCCCS valve, SWV-1 10, "Return from the CRDMS," has failed closed causing

multiple CRDs to come into alarm with temperatures above 1800F.

-

The Reactor Building sump level is slowly increasing.

Which of the following is the appropriate control room operator actions.

A.

Sample the Reactor Building sump to identify type of leakage.

B.

Perform a controlled shutdown at the maximum safe rate.

C.

Trip the reactor coolant pumps and perform EOP-09, "Natural Circulation

Cooldown."

,/D.

Trip the reactor and concurrently perform EOP-02, "Vital Systems Status

Verification."

A. Sampling the sump would identify the source leakage, but the priority is the plant and the

CRDM alarms.

B. Controlled S/D is time consuming and this requires a Reactor trip.

C. Tripping the RCPs would trip the reactor but this needs to be a trip and enter EOP-02.

D. CORRECT: Per AP-330 and AI-505 must trip the reactor if CRDM temps are >180°F if the

plant is in MODEs 1-4.

OPSA1.BNK 2002 NRC exam KEH 10/13/01

ROTs J - TIOA

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

17

1

11150402016

[009G2.4.24

.3

h.7

33-[1

P-330

ANSERS:.

Version Answers:

Points

=

0 1 2 3 4 5 6 7 8 9

FýScrambleChoices

I IA IB I1C ID ]A

Scramble Range: A -

W

Page: 34

2K2RO.BNK

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

Page: 35

28. 5-96 001 / 6//0450402001 / 039A4.01 / 2.9/2.8/33 [1]/ EOP-02

Given the following plant conditions:

Reactor trip

Performing Immediate Actions

Depress Turbine trip pushbutton, Throttle valves and Governor valves DO NOT close

Which of the following is the appropriate contingency action(s)?

A.

Reduce governor valve position using the position limiter.

B.

Close governor valves using "GV/Fast" pushbutton.

"VC.

Close the main steam isolation valves.

D.

Send someone to trip the turbine at the turbine pedestal.

A. This is not the contingency and would be too slow.

B. This is not the contingency and would be too slow.

C. CORRECT: This will isolate all steam to the turbine and therefore remove the heat sink

from the reactor.

D. This is not the contingency and would be too slow.

BANK 2002 NRC exam KEH 10/3/01 (INPO BANK)

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO

16

450402001

39A4.01

ý.9

ANSWERS:

Version A

Points=

0D 2I

Import.

SRO Import

nswers:

456789

ID

]IElIZIEIElo

Scr

Initial/Re

System

3 [11

EOP-02

Scramble Choices

amble Range: A-

Friday, January 18, 2002 @ 06:52 AM

2K2RO.BNK

Page: 36

29. 5-97 001/ 3/ / 1150502006/ 074G2.4.21/ 3.7/4.3/33 [1J/ EOP

In EOP-7 with the RCS in Inadequate Core Cooling (ICC) Region 3, the following CAUTION

states:

"Hot leg high point vents must remain open until RCS forced flow is established or cooldown

is completed"

Which of the following is the reason for this caution?

A.

Provides RCS de-pressurization therefore increasing HPI flow through the core.

vB.

Promotes boiler condenser/natural circulation cooling via the OTSGs.

C.

Provides a flow path from the RCS to the RB to ensure a water source for RCS

cooling.

D.

Prevents formation of voids in the reactor vessel head.

A- the lines are too small to rapidly de-pressurize the RCS, and this is not the specific reason

for this caution.

B- CORRECT; these valves will remove non-condensable gases and therefore will not block

the flow path from the RCS to the OTSGs.

C- These valves are too small to effectively pass enough water for recirc cooling.

D- These valves are for gases in the hot leg, they will not stop the formation of voids in the RX

Vessel head.

NEW 2002 RO exam KEH 7/11/01

KEY WORDS:

Objective

Lesson Pla

Task Numt

13

1115050200

ANSWERS:

PointsF71

be

K/A

RO Import.

)6 1074G2.4.21

13.7

Version Answers:

0123456

IBClDIIcl

SRO Im

7.3

78

9

port

Initial/Re

h3 [1]

[

Scramble Choices

Scramble Range: A -

System

IEOP

w

[A

Page: 1

Friday, January 18, 2002 @ 06:51 AM

1. 1-47 001/15//1150402016/035K5.01/3.4/3.9/33-[11/

Which of the following states when the potential reactivity effects of a steam line break are

most severe?

Effects remain the same over core life.

Beginning of core life.

Middle of core life.

'D.

End of core life.

Reasons:

As the core ages MTC becomes increasingly more negative. A steam line break results in a

cooldown of the RCS and MTC adds positive reactivity as this occurs. Because MTC has a

larger negative value as the core ages, the effect of the steam line break gets greater also.

NOB 2002 NRC exam KEH 10/12/01

Unmodified bank question for LOI-99-01 SRO and RO Audit exam (7-28-2000 CMC

[039K5.08 3.4/3.9]

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

115

1150402016

035K5.01

.4

3.9

3-[1

ANSWERS:

Version Answers:

Points=

0 1 2 3 4 5 6 7 8 9

Ivj Scramble G,,uhei

IDIA1BIC ID

IA

[B

DA=

Scramble Range: A -

d

A.

B.

C.

2kcom.bnk

Page: 2

Friday, January 18, 2002 @ 06:51 AM

2. 1-50 001 / 7//0150102001/ 032AA2.02/ 3.6/3.9/33 [2/3]/ RX S/U

Given the following plant conditions:

Reactor Startup in progress.

Initial Source Range counts NI-I = 70 cps; NI-2 = 80 cps.

ECP 50% on group 6.

Rods are currently at 75% on group 5 and holding.

NI-1/2 count rate is stable.

Which of the following count rates for NI-1/2 would you expect for this condition?

A.

105/120

"-B.

140/160

C.

350/400

D.

2100/2400

A. This is a factor of 50% increase the rods have moved 50% of travel but the counts are not a

factor Of 50% higher.

B. CORRECT: a factor of two if you have added half of the reactivity which is 50 % of the rod

movement. Therefore, twice the initial CR at this level.

C. Factor of 5 doublings is for criticality from initial CR not at 50 % of rod motion.

D. Factor of 30 times the inital CR is for not reaching criticality within the ECP.

NEW 2002 NRC KEH/MKG 8/9/01 no reference required, thumbrules and OP-2 10.

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

7

105002001

032AA2.02

.6

3

33 23

IRX S/U

ANSWERS:

Version Answers:

Ti

.

1e

Points

0 1 2 3 4 5 6 7 8 9

"jScrambler

,ouw ces

1BIcIDAI1B Ic IDABCI

Scramble Range: A -

wd

2kcom.jbnk

Page: 3

Friday, January 18, 2002 @ 06:51 AM

3. 2-32 001 / 12/ GT-001 R 24/1190102008/ G2.3.2/ 2.5/ 2.9/ 33-[1]/

A valve needs to be repositioned for the completion of a surveillance. The valve is located in

the Make-up Demin Valve Alley. Lead shielding is draped over the valve handwheel. Which

of the following is an accepted ALARA practice for repositioning the valve?

A.

Reposition the lead shielding along the valve piping enough to reposition the valve;

replace the shielding to its original position; inform Health Physics when you have

completed the task.

Reposition the lead shielding so that it stays between you and the valve; reposition

the valve by reaching around the shielding; replace the shielding to its original

position.

Remove the lead shielding; reposition the valve; leave the lead shielding for the

Health Physics technician to replace.

Remove the lead shielding with the permission of Health Physics; reposition the

valve; replace the lead shielding.

Reasons:

A., B., and C. Lead shielding must not be moved without permission from Health Physics.

D. Lead shielding can only be moved with prior permission from Health Physics.

New question written for Sept 2000 RO exam. (3-15-2000 mg)

REPEAT

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

12

GT-001R24

1190102008

JG2.3.2

1.5

I29

33-1

ANSWERS:

Points=

Version Answers:

0 1 2 3 4 5 6 7 8 9

Scramble Choices

IDIAIB iclIAIB

Scramble Range: A-

[

B.

C.

vD.

2kcom.bnk

Page: 4

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

4. 2-34 001 / 8/ / 1150502005/ 037AK1.01/ 2.9/3.3/11 [2/3]/ SGTL

Given the following plant conditions:

"A" OTSG primary to secondary leak in progress.

Reactor is tripped.

A Main Steam Safety Valve (MSSV) is cycling at 950 psig.

Which of the following temperatures is the maximum RCS temperature to maintain OTSG

pressure equal to 950 psig?

(All temperatures are rounded to the nearest whole number)

A.

C.

D.

5240F.

5400F.

5550F.

5650F.

A. Assume 950 - 125 bias = 825psig + 15 = 840psia, sat temp = 523.8

B. CORRECT: 950 +15 = 965 psia, sat temp = 540.2

C. Assume 950 + 125 bias = 1075 psig + 15 = 1090 psia, sat temp = 555.1

D. Assume EOP-6 number of 565 from procedure.

NEW 2002 NRC KEH/MKG 8/9/01 need steam tables

KEY WORDS:

Objective

Lesson Pia

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

18

11150502005

037AK1.0,1

1.9

13.3

I11 [2/31

SGTL

ANSWERS:

Version Answers:

Points

=

0 1 2 3 4 5 6 7 8 9

LX]JScrambleUChoices

IB Ic ID*

IB IC

Scramble Range: A-

Ed

Friday, January 18, 2002 @ 06:51 AM

5. 2-34 002/5, 15// 0020402013/ 008AK3.02/ 3.6/4.1/33 - [1]/

Given the following plant conditions:

100% power

RCV-8 is leaking

Tailpipe temperature is less than the saturation temperature of the pressurizer.

Which of the following identifies this type of process?

A.

Isobaric

B.

Isometric

"VC.

Isenthalpic

D.

Isentropic

A- Constant pressure, not for PZR to RCDT

B- Constant volume, not for PZR to RCDT

C- Constant enthalphy, through a valve this is CORRECT!

D- Constant entropy, not for PZR to RCDT

LP 2-34 definition and constant enthalpy process section.

NEW for 2002 NRC EXAM KEH 5/8/2001

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

15,15

1

10020402013

1008AK3.02

13.6

k.1

133- 1]

ANSQWERS.

Version Answers:

PointsF--*

0 1 2 3 4 5 6 7 8 9

E Scramble Choices

D

A B

D

Scramble Range: A-

w

Page: 5

2kcom.bnk

Page: 6

Friday, January 18, 2002 @ 06:51 AM

6. 3-20 001/ 3//1150502002/ E03EK3.1/ 3.2/3.8/33 [2/3]/ EOP-3

Given the following plant conditions:

- The reactor is tripped.

- RCS subcooled margin is zero.

Which of the following actions would result in increasing RCS subcooling margin?

Decrease RCS pressurizer level.

Decrease RCS hot leg flow.

Increase RCS loop pressure.

Increase RCS hot leg temperature.

A- This would further reduce RCS pressure, if a bubble still exists in the PZR, level may

increase if voids are forming.

B- This would decrease the ability to transfer heat, and therefore would not increase SCM

C- CORRECT Raising pressure will increase the SCM by moving the RCS up and to the left

on the SPDS trace moving away from the saturation and zero SCM line.

D- This would move the RCS to the right on the SPDS trace and therefore decrease RCS SCM.

NEW 7/9/01 KEH

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

13

1

,50502002

(

EO3EK3.1

.2

1.8

33 2/3

EoP-3

ANSWERS:

Version Answers:

0 1 2 3 4 5 6 7 8 9

ZScramble Choices

Points Lull

ICIDIAICID AjBICD

Scramble Range: A-

W

A.

B.

",-C.

D.

2kcom.bnk

Page: 7

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

7. 4-07 001 / 4//0860402001 / 086A1.01/ 2.9/3.3/33 [2/3]/ FIRE

Given the following plant conditions:

"A fire is in progress on the startup transformer

"A Loss of Offsite Power

Fire header pressure has decreased to 100 psig.

Which of the following will provide fire fighting water pressure'?

A.

FSP-1, Electric driven fire service pump.

,/B.

FSP-2AJB, Diesel driven fire service pumps.

C.

FSP-3, Jockey fire pump.

D.

FST-3, Fire service surge tank.

A. The LOOP will de-energize ACDP-7, no power.

B. CORRECT: The LOOP will de-energize ACDP-7, loss of power to the battery chargers

would start these pumps, with pressure at 100 psig the pressure setpoints have not been reached

for starting.

C. The LOOP will de-energize ACDP-7, no power.

D. The surge tank is for damping system surge pressure, not adequate to supply fire header

pressure during actuation of fire system.

NEW 2002 NRC exam KEH 10/2/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

14

10860402001

1086A1.O

ANSWERS:

Points=

RO Import.

SRO Import

Initial/Re

,1

.9

3.3

33 [2/3

Version Answers:

0 1 2 3 4 5 6 7 8 9

E] Scramble Choices

IB IC IDIAIBIc IDIAIBc

Scramble Range: A-

System

IFIRE

[

Friday, January 18, 2002 @ 06:51 AM

8. 4-09 001 / 3,7/ / 0160402005/016G2.1.31/ 4.2/3.9/33 [2/3]/ SASS

Given the following RCS instruments, during full power operation:

INSTRUMENT

PZR Level

RCS Tcold (NR)

PZR Temp

RCS Press (NR)

LABEL

RCI-LT1

RC5A-TE I

RC2-TE1

RC3A-PT1

INITIAL

220

555

648

2155

FINAL

208

557

665

2135

Instrument signal failure rates are rapid from the inital value to the final value.

Which instrument would the Smart Auto Signal Selector (SASS)

TRANSFER?

module perform an automatic

,/A.

PZR Level

B.

RCS Tcold

C.

PZR Temp

D.

RCS Press

A. CORRECT, (0 - 320) X .03 = 9.6"; this was 12"

B. (520 - 620) X .03 = 30; this was 20 .

C. (0 - 700) X .03 = 210; this was 170, in addition SASS does not control this instrument.

D. (1700 -2500) X .03 = 24#; this was 20#.

NEW 2002 KEH (8/7/01)

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

13,7

1

160402005 ]016G2.1.31

14.2

13.9

133 2/3

ISASS

ANSWERS:

Points[ffi

Version Answers:

01 23456789

[] Scramble Choices

IBCDA

B

Scramble Range: A -

D

Page: 8

2k2com.bnk

Friday, January 18, 2002 @ 06:51 AM

9. 4-09 002/ 3,4,7/ / 0160102003/ 027AA1.01 / 4.0/3.9/ 33-[2/31/ 01 CYC2

The following plant conditions exist:

- RC-3A-PT1, RCS narrow range pressure transmitter, is selected for control

pressure transmitter failed high.

when the

- SASS failed to transfer to the alternate instrument.

Based on these failures which of the following describes the resulting plant response?

A.

ES Channel I will be inoperable.

B.

Channel A of the Diverse Scram System (DSS) will actuate.

C.

RCS pressure will decrease slowly.

vD.

RCS pressure will decrease rapidly.

Reasons:

A.

Wide range pressure transmitters feed the ES system. This failure has no

effect on ES.

B.

This transmitter does not feed DSS so no actuation will occur.

C.

The PZR heaters are receiving a false high pressure signal.

D.

RCS pressure will decrease rapidly due to the Spray valve and PORV

opening.

OPS 4-09 Section 1-4 and Figure 5; KA #'s 027AA2.11 4.0/4.1, 010KI.03 3.6/3.7, 010K3.01

3.8/3.9, 010K4.03 3.8/4.1, 010A3.02 3.6/3.5, 016K1.08 3.4/3.4, 016K3.08 3.5/3.7; Task #

0020402013

NRCM; LOIl-T5

BANK

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

13,4,7

1

10160102003

1027AA1.01

.0

13.9

133-[2/3]

1CYC2

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2k2com.bnk

9. 4-09 002/ 3,4,7//0160102003/ 027AA1.01 / 4.0/3.9/33-[2/31/01 CYC2

ANSWERS:

Version Answers:

0123456789

P~i÷*

D A B C D

A B C D A

Page: 10

W Scramble Choices

Scramble Range: A -

W

o n

Friday, January 18, 2002 @ 06:51 AM

10. 4-10 001/ 5/ / 0150102003/ 015A4.01/ 3.6/ 3.6/ 33 [2/3]/ NI

Given the following plant conditions:

NI-5 88%

NI-6 90%

NI-7 90%

NI-8 89%

SASS is selected to NI 7/8

NI-7 fails high

SASS mismatch alarm (K-3-2) is actuated

SASS transfer alarm (K-3-3) is actuated

Which of the following is the input to the ICS for reactor power?

A.

"/B.

C.

D.

NI-5

NI-6

NI-7

NI-8

A. 5/6 is a high autioneer and 6 is the highest.

B. CORRECT: 5/6 is a high autioneer and 6 is the highest, the transfer was to 5/6.

C. 7 fails high but the transfer takes that input away

D. 8 is still selected by sass but the transfer took that selection away.

NEW 2002 NRC exam KEH 10/4/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

15

10150102003

1015A4.01

.6

h.6

133 2/31

INI

AMNWCER.

Version Answers:

01 23456

7 8 9

Z Scramble Choices

Poins [I

A Is Ic IOIA I C I

[

Page: I I

Points=

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2kcom.bnk

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

11. 4-10 002/3//1150402016/ 002K5.10/ 3.6/ 4.1/33-[2/31/

The initial power escalation following a refueling outage is

power level is stabilized to perform testing. The following

operator at the control board:

NI-5

NI-6

NI-7

NI-S

T-hot Loop A

T-hot Loop B

T-cold Loop.

T-cold Loop I

Tave

Page: 12

being performed. The reactor

indications are available to the

26.0%

29.0%

26.0%

29.0%

588.50 F

588.00 F

A 570.00 F

B 569.50 F

579.00 F

Which of the following is an accurate estimate of the thermal power level of the reactor at this

point?

A.

B.

C.

372 MWt

661 MWt

738 MWt

,D.

1070 MWt

Friday, January 18, 2002 @ 06:51 AM

11. 4-10 002/ 3//1150402016/ 002K5.10/ 3.6/4.1/ 33-[2/31/

Reasons:

A, B, C. Due to the change in Tcold on a power increase, the NIs will need calibrating at

approximately 25% power increments. Using alternate indications, such as core delta-T is a

more accurate indication of power level. A core delta-T of 18.5' F indicates a power level of

approximately 42% with a corresponding thermal power level of approximately 1070 MWt.

A.

If the student uses 100% power Megawatt Electric instead of Megawatt

Thermal, this answer will be obtained.

(18.50 F X 1% power/.44° F X 885 MWe/% power = 372 MWe)

B.

If the student uses the value of power displayed on NI 5 and NI 7, this

answer will be obtained.

(.26 X 2544 MWt = 661 MWt)

C.

If the student uses the highest value of power displayed on NI 6 and NI 8,

this answer will be obtained.

(.29 X 2544 MWt = 738 MWt)

D.

18.50/44' dT=.42x2544= 1069.63= 1070

Unmodified repeat question from LOI 99-01 program; NRCN

Modified 8-2-00 CMC Modified 6/29/2001 KEH ( 18.50 dT = new 1070)

REPEAT

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

13

11150402016

1002K5.1

ANSWERS:

1ge

Points=

RO Import.

SRO Import

Initial/Re

S

13.6

4.1

3- 2/3

Version Answers:

0 1 2 3 4 5 6 7 8 9

[Scramble Choices

ID1AB

B IC IDI1A

Scramble Range: A -

System

W

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Page: 13

Friday, January 18, 2002 @ 06:51 AM

12. 4-10 003/5,6/5-01/1150402016/033AK3.01 /3.2/3.6/33-[2/3]/

A reactor start-up is in progress with power indicating 10

amps on NI-3 and NI-4. Which of

the following describes the changes in indication and power level restrictions if the auxiliary

power supply for NI-3 fails?

NI-3 will indicate greater than 10-10amps and power is restricted to less than 5%.

NI-3 will indicate less than 10-10amps and power is restricted to less than 5%.

NI-3 will indicate greater than 10-10amps and power is restricted to less than % x

10-9amps

NI-3 will indicate less than 10-10amps and power is restricted to less than 1 x

10-9 amps

Correct Answer. Loss of compensating voltage will cause the NI to see

both neutron and gamma flux. This will increase the indication on NI-3.

ITS 3.3. 10, condition A requires repair of the Intermediate Range NI

prior to entry into Mode 1 which occurs at 5% power.

B.

Loss of compensating voltage will cause the NI to see both neutron and

gamma flux. This will increase the indication on NI-3.

C.

ITS 3.3.10, condition A requires repair of the Intermediate Range NI

prior to entry into Mode 1 which occurs at 5% power.

D.

Loss of compensating voltage will cause the NI to see both neutron and

gamma flux. This will increase the indication on NI-3. TS 3.3.10,

condition A requires repair of the Intermediate Range NI prior to entry

into Mode I which occurs at 5% power.

New Question written for Sept. 2000 RO exam. (2-29-00 CMC); Additional Task#

1190302001

REPEAT

-A.

B.

C.

D.

Reasons:

A.

Page: 14

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2k2com.bnk

12. 4-10 003/5,6/5-01/1150402016/ 033AK3.01 / 3.2/3.6/ 33-[2/31/

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Impc

15,6

5-01

1150402016

033AK3.01

13.2

ANSWERS:

Version Answei

Pt

I012345

Sige

]Points[

W]IAIBICIDEI

Page: 15

rt.

SRO Import

Initial/Re

13.6

b3-[2/3]

rs:

6 7 8 9

[

Scramble Choices

]I-IZlI

Scramble Range: A -

System

II

W

Friday, January 18, 2002 @ 06:51 AM

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Page: 16

13. 4-12 001/4//0010502002/054AK3.01/ 4.1/4.4/33 [1]/]RPS

An anticipatory reactor trip (ARTS) is designed to prevent which of the following condition(s)?

A.

Challenges to OTSG tube integrity.

B.

Exceeding core thermal limits (fuel centerline melt).

"VC.

Challenges to the PORV and code safeties.

D.

Exceeding core DNBR limits.

A. They would be stressed but still within design limits.

B. These limits are based on LOCAs.

C. CORRECT; based on limiting the pressure spike on the loss of heat sink.

D. These are based on RCS flow, temperature, and flux.

NEW 2002 KEH (8/7/01)

KEY WORDS:

Objective

Lesson Pla

14

ANSWERS:

S1ge

Points

Task Numbe

K/A

RO Import.

SRO Import

010502002

54AK3.01

k.1

4.4

Version Answers:

0123456789

I

1

7]I[Zlll~eIPDIAIB le

5crSo

Initial/Re

r3

[11

Scramble Choices

amble Range: A -

System

IRPS

Ed

Friday, January 18, 2002 @ 06:51 AM

14. 4-12 003/4/ / 0120102010/ 012K6.04/ 3.3/3.6/33 [2/31/ RPS

Which of the following is correct concerning RPS "MANUAL BYPASS" interlock?

Takes both channels out of "MANUAL BYPASS" when the second RPS channel is

place in "MANUAL BYPASS".

The first RPS channel in "MANUAL BYPASS" will trip the second RPS channels

Reactor Trip Module, if that channel is placed in "MANUAL BYPASS".

The first RPS channel in "MANUAL BYPASS" prevents placing any additional

channels in "MANUAL BYPASS".

The reactor trips if a second RPS channel is placed in "MANUAL BYPASS".

A. Admin and electrical interlock prevent two channels in bypass at same time see (C.)

B. Admin and electrical interlock prevent two channels in bypass at same time see (C.)

C. CORRECT: this interlock will actuate a relay that will prevent any of the remaining three

channels to be placed in bypass.

D. Admin and electrical interlock prevent two channels in bypass at same time see (C.)

NEW 2002 NRC EXAM KEH 8/27/01 (INPO BANK)

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

14

1

10120102010

012K6.04

.3

.6

13 [2/31

RPs

nIckICOAfl.

Version Answers:

0123456789

E Scramble Choices

Points

ID

l

A

l

B

IC ID

Scramble Range: A-

A.

B.

",/C.

D.

[A

Page: 17

Points[=

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Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

15. 4-12 004/4//0120402007/045K1.18/3.6/3.7/33 [2/31/ RPS

The following plant conditions exist:

PARAMETER

Rx power

Linear amp power range

RCS Thot

RCS pressure

RCS flow

RB pressure

RCP monitor

Turbine auto-stop oil

Both MFW control oil

DATA

75%

top 35%

5970

bottom 40%

2155#

9 x 107 lbm/hr

+0.5 psig

A 8,300 kw

B 7,100 kw

C 9,500 kw

D

0 kw

99 psig

114 psig

Based on the above data which of the following parameter changes will require immediate entry

into EOP-2, Vital System Status Verification? (consider each option independently)

RB pressure

RCS pressure

3.5 psig

1911 psig

RCP monitor

Turbine auto-stop oil

B 2152 kw

44 psig

Reasons:

A.

RB Pressure would need to be >4 psig

B.

Pressure would need to be < 1900# for the low pressure trip or < 1881# for

the variable low pressure trip.

C.

RCP pump monitor setpoint is <1152 kw.

D.

CORRECT: Turbine control oil pressure setpoint is 45 psig.

A.

B.

C.

,/D.

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

15. 4-12 004/4//0120402007/ 045K1.18/ 3.6/3.7/33 [2/3]/ RPS

TS Table 3.3.1-1; COLR; EOP-2 Step 1.0; OPS 5-01; KA #'s E02EK2.I 3.8/4.0, 003K3.04

3.9/4.2

LOI I-T7BR/T7BS

Bank 9/20/01 KEH

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

14

1

10120402007

1045K1<8

.6

.7

h3 2/3

IRPS

ANSWERS:

Points

i

Version Answers:

0 1 2 3 4 5 6 7 8 9

ZScramble Choices

DAB

Scramble Range: A -

W1

Page: 19

Page: 20

Friday, January 18, 2002 @ 06:51 AM

16. 4-12 005/4,5//0450402001/A04AK3.2/3.4/3.6/33 [2/31/AMSAC

Given the following plant conditions:

52% power

AMSAC channel "B" is in TEST/CAL

"A" main feedwater flow instrument fails to 0%

Which of the following identifies the plant conditions?

'A.

AMSAC does not actuate.

B.

AMSAC actuates the "A" channel of EFIC.

C.

AMSAC actuates and trips the turbine, the reactor will not trip.

D.

AMSAC actuates and trips the turbine, which trips the reactor.

A. CORRECT: With a channel in TEST the other channel is blocked, no trip or actuation will

occur.

B. The channel signal to EFIC is blocked and it will not actuate.

C. The channel is blocked no turbine trip will occur.

D. The channel is blocked no turbine trip will occur or reactor.

NEW 2002 NRC exam KEH 10/2/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

4,5

0450402001

04AK3.2

13.4

h.6

133 2/31

AMSAC

ANSWERS:

Version Answers:

Points

0 1 2 3 4 5 6 7 8 9

,LXJcrambleG oces

IAIBCICD [AIl

I

Scramble Range: A -

V

P

2k2com.bnk

Page: 21

Friday, January 18, 2002 @ 06:51 AM

17. 4-12 006/4/ / 0020102009/015AA1.03/ 3.7/3.8/ [2/3y/

The following conditions exist:

The plant is operating at 85% power.

One RCPPM channel test switch (SS6) is placed in "TEST" for RCP-1D.

Which of the following indicates the plant response should RCP- 1 C experience a locked rotor?

A.

Only RPS Channel "C" trips.

vB.

All RPS Channels trip.

C.

Only EFIC Channel "C" trips.

D.

All EFIC Channels trip.

A- With the test on RCP- 1D, and RCP- 1C trips; RPS will see a loss of two RCPs and each

RPS pump monitor will trip their respective RPS channel.

B- CORRECT With each RPS pump monitor tripping their respective channel then all RPS

channels will be tripped.

C & D EFIC looks for all four RCPs to be tripped to trip (actuate) the EFIC system.

OPS-4-12 RPS (OBJ. 4), section on RCPPM

OPS-4-31 EFIC (OBJ 2), section on actuation and ITS

NEW for 2002 NRC exam KEH 4/30/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

14

10020102009

15AA1.03

37

.3

2I

ANSWERS:

Version Answers:

Points

=

0 1 2 3 4 5 6 7 8 9

wI'ScrarnbleChoices

1B IIILC ID

AB C

Scramble Range: A -

Wj

2kcom.bnk

Friday, January 18, 2002 @ 06:51 AM

18. 4-13001 / 2//0130502001/ 013K3.02/ 4.3/ 4.5/33 [2/31/ ES

Given the following plant conditions:

The reactor is shutdown.

The "HPI BYPASS PERMIT" lights are WHITE.

At 1700 psig, the operator bypasses all three channels for both trains of HPI.

An RCP seal leak then develops, causing the operator to trip the affected RCP and increase the

plant cooldown rate.

RCS pressure decreases to 900 psig.

Select the appropriate ES response:

HPI initiates on low RCS pressure due to the RCS leak.

The HPI "BISTABLE TRIPPED" lights are BLUE.

LPI initiates on low RCS presssure due to the RCS leak.

The LPI "BISTABLE TRIPPED" lights are BLUE.

A. HPI was bypassed and will not actuate.

B. CORRECT: The bistables will trip and light the lights, but will not actuate.

C. LPI setpoint is not actuated at this pressure

D. LPI bistables will not trip at this pressure.

NEW 2002 NRC EXAM KEH 8/27/01 (INPO BANK)

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

12

1

10130502001

1013K3.02

14.3

14.5

133 2/31

IES

ANSWERS:

Version Answers:

Points

=

01 23456789

E Scramble Choices

IB IC

I

Scramble Range: A -

d

A.

C.

D.

2kcom.bnk

Page: 22

[3 IC 113

1A 1B IC ID IA

Friday, January 18, 2002 @ 06:51 AM

19. 4-13002/51 / 0130102006/013K2.01/ 3.6/3.8/33-[2/31/

At 100% full power the following Engineered Safeguards (ES) conditions exist:

-

Reactor coolant (RCS) pressure is 1950 psig.

-

ES channel 3 has the pressure bistable in the "test/operate" position for

maintenance.

What will be the status of the ES system if ES channel I loses power?

A.

No ES channels are tripped for these conditions; no ES actuation will occur.

B.

Only channel 1 will be tripped; no ES actuation will occur.

C.

Both channels 1 and 3 will be tripped; only "A" side ES actuation will occur.

"vD.

Both channels 1 and 3 will be tripped; both "A" and "B" side ES actuations will

occur.

Reasons:

A. and B. ES actuation is de-energize to actuate, channel I would be

tripped. Channel 3 would also be tripped because it is in "test/operate".

A full actuation should occur.

C. With both channels 1 and 3 tripped the 2 out of 3 logic is made and both an

"A" and "B" ES actuation should occur.

D. Correct, ES actuation is de-energize to actuate, channel 1 would be

tripped. Channel 3 would also be tripped because it is in "test/operate".

A full actuation should occur.

NOB 2002 NRC exam KEH 10/12/01

LOI-99-01 FPCF; LOII-T9BR/BS

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

15

1

10130102006

10 13K2.01

13.6

3.8

133-213

ANSWERS:

Version Answers:

Points

=

0 1 2 3 4 5 6 7 8 9

LjScrambleChoices

IDAI

B

IC IDIJA

Scramble Range: A-

Wd

Page: 23

2kcom.bnk

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

Page: 24

20. 4-13 003/ 2// 0130502001/ 006A3.03/ 4.1/ 4.1/ 33-[1]/ ES

The plant has just received a valid engineered safeguards actuation system (ESAS) signal. A

motor operated valve (MOV) in the high pressure injection system is repositioning to its ES

position.

Which of the following is the expected sequence of ES status monitor light changes for this

MOV as it repositions?

green -- off -- amber

green -- white -- amber

amber -- off -- green

amber -- white -- green

A- Amber is the non-ES position which is the normal alignment

B- See above and there is no white light associated with the status lights

C- Correct. Amber to green and during the stroke the light would be off

D- There is no white light associated with the status lights

BANK QUESTION 2002 NRC EXAM KEH 5/10/2001 COMMON BANK

BANK

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

]ES

2

o i30502001

1006A3.0

ANSWERS:

S]

Points Iii

'3

14.1

14.

b3-[l1

Version Answers:

0 1 2 3 4 5 6 7 8 9

ZScramble Choices

IC IDAIBIC ID11IB IC ID I

Scramble Range: A -

A.

B.

'/C.

D.

D

Friday, January 18, 2002 @ 06:51 AM

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Page: 25

21. 4-14 001 / 3// 0410402001/ 003AK1.13/ 3.2/ 3.6/33 [2/3/1 CS

Given the following plant conditions:

- Reactor is at 70% power.

- ICS Reactor Bailey and Diamond stations are in MANUAL.

- All other ICS stations are in AUTOMATIC.

- Group 5 rod 6 is dropped fully into the core.

Which of the following indicates the core power distribution concern, and the Tave parameter

response?

ASSUME NO OPERATOR ACTIONS.

A.

Negative Quadrant Power Tilt; Tave decreases and remains low.

B.

Negative Quadrant Power Tilt; Tave decreases and returns to setpoint.

C.

Positive Quadrant Power Tilt; Tave decreases and remains low.

,/D.

Positive Quadrant Power Tilt; Tave decreases and returns to setpoint.

A/B/C. QPT will become more negative in the quadrant the rod is dropped into but the main

operator limit concern is the flux shift and the positive QPT for the other 3 quadrants. Tave will

return to setpoint as MFW has Tave control with the reactor in manual

D. CORRECT; As the rod is fully dropped into the core, power distribution is changed between

the quadrants. The quadrant that the rod is dropped into is poisoned and the flux decreases and

shifts the flux to the other quadrants. The quadrant that contains the dropped rod will indicate a

negative QPT value and the other quadrants will indicate positive. These positive quadrants are

producing most of the power and is the operators main power distribution limit concern. Tave

will return to setpoint as MFW has Tave control with the reactor in manual.

NEW 2002 KEH (7/13/01) No references required

OPS 5-01(ITS) Obj 2,3; OPS 5-68 (AP545) Obj. 6,7 Task # 1150402013

KEY WORDS:

Objective

Lesson Pla

Task Numbe

13

1

0410402001

ANSWERS:

Points E*]

K/A

RO Import.

SRO Import

Initial/Re

1003AK1.13

.2

13.6

3 2/3

Version Answers:

0 1 2 3 4 5 6 7 8 9

W1 Scramble Choices

IDLIIIDABCDA

Scramble Range: A -

System

ICS

D

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

Page: 26

22. 4-14 002/3,5/ / 0410402013/ 059K1.07/ 3.2/3.2/ 33-[2/31/

Reactor power has been reduced to 80% to investigate indicated Main Feedwater flow

oscillations in the "A" loop. With the plant stable at this power, the "A" Main Feedwater flow

transmitter fails low. Assuming no SASS transfer occurs, which of the following describes the

expected ICS response to this failure? Consider the results if the transient is allowed to

continue for at least one minute.

-'A.

ICS will increase FW to both OTSGs. Reactor Power will decrease.

B.

ICS will increase FW to the "A" OTSG and decrease FW to the "B" OTSG. Reactor

Power will decrease.

C.

ICS will increase FW to both OTSGs. Reactor Power will increase.

D.

ICS will increase FW to the "A" OTSG and decrease FW to the "B" OTSG. Reactor

Power will increase.

Reasons:

A.

Correct Answer. Feedwater will increase on the "A" side due to the

failed transmitter. This will decrease Tc on that side. The delta Tc

circuit will attempt to decrease flow to the affected side (unable to

decrease due to failed instrument) while increasing flow to the other

OTSG. The net result is an increase in feedwater flow to both OTSGs.

When the transimitter fails, a large reduction in indicated feedwater

flow will result. The indicated flow will be more than 5% below demand

and therefore result in a feedwater to reactor cross limit reducing

reactor demand by the amount of error above 5%.

B.

FW to the "B" OTSG will increase due to the actions of the delta Tc

circuit discussed above.

C.

Reactor power will decrease because of the feedwater to reactor cross

limit discussed above.

D.

FW to the "B" OTSG will increase and reactor power will decrease as

discussed above.

Friday, J

22.

Page: 27

anuary 18, 2002 @ 06:51 AM

2k2com.bnk

4-14 002/3,5//0410402013/ 059K1.07/ 3.2/3.2/ 33-[2/3]/

New question written for Sept. 2000 RO and SRO exam. (3-15-00 CMC)

Additional KA # 1150402016

REPEAT

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

13,5

0410402013

059K1.07

b.2

ANSWERS:

Version Answers:

0123456789

AC

bZqo

]Points[ II

IAIBC oAB lII

Sc

Scramble Choices

ramble Range: A -

Initial/Re

System

33-[231

2

Wd

Friday, January 18, 2002 @ 06:51 AM

23. 4-14 003/3//0410402001/ 003K3.05/ 3.6/ 3.7/ [2/3Y/

Given the following plant conditions:

Plant is at 85% power

All ICS stations are in AUTOMATIC

RCP- 1 D trips its breaker on overcurrent

Which of the following identifies the initial ICS response?

A.

Feedwater flow will re-ratio based on the total feedwater flow control circuit.

B.

"TRACK" will be actuated based on the "Feedwater limited by Reactor" cross limit.

"v C.

The Integrated Master will decrease demand at a rate sufficent to block the

calibrating integral.

D.

The Unit Load Demand will decrease demand to the low load limit setpoint.

Reasons

A- the total feedwater flow control will not control any feedwater flow until one OTSG is on

low level limits, and the RCP trip (RCP flow circuit) will re-ratio feedwater

B- Track is actuated by a cross limit that would not be actuated based on the conditions during

the runback.

C- Correct. The runback will be at 50%/min which is faster than the 2%/min rate that blocks

the calibrating integral.

D- The ULD will decrease its demand but based on the runback to 75%, NOT the low load

limit of 129 MWe

NEW NRC 2002 KEH 5/2/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

13

b410402001

003K3.05

13.6

13.7

1[2/31

ANSWERS:

Version Answers:

Points=I]

0 1 2 3 4 5 6 7 8 9

VLflcrambleunoices

tICDAI IC IlDABI

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Wd

Page: 28

2kcom.bnk

Friday, January 18, 2002 @ 06:51 AM

24. 4-16 001/ 3/ / 1010402004/ 068AK2.07/ 3.3/3.4/33 [2/3]/ RSP

Given the following plant conditions:

Fire in the cable spreading room, the Control Room has been evacuated and transfer to the

Remote Shutdown Panel has been completed.

Following the transfer, RCS pressure decreased to 1400# and initiated Engineering Safeguards.

Which of the following identifies the starting status of the Emergency Diesel Generators for

this scenario?

Must be started locally.

Must be started at the Remote Shutdown Panel.

Should have started when the transfer switches transferred control to the Remote

Shutdown Panel.

Should have auto started as a result of the Engineering Safegaurds actuation.

A. Local start is not required, auto start still functions.

B. There is no remote start capabilities at the RSP.

C. The transfer switch will not start the EDG

D. CORRECT, ES actuates on low RCS pressure, AND this is the one circuit that ES will still

actuate when control is transfered to the RSP.

OPS-4-16 page 7 refers to the EDG ES actuation, Objective 3

NEW 2002 KEH 8/1/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

13

11010402004

1068AK2.07

13.3

.4

133 2/31

IRSP

ANS=WERc.

Version Answers:

1e

Points=E

0 1 2 3 4 5 6 7 8 9

WScramble Choices

1D1A1BIC D lA

IC IDA

Scramble Range: A -

A.

B.

C.

"vO.

d

Page: 29

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Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

25. 4-21 001 / 2/ / 1150502002/ EO3EK1.2/ 3.8/4.0/33 [2/31/ SPDS

Given the following SPDS indication of SCM:

Which combination would allow the operator to throttle or terminate HPI flow?

/A.

Black number(s) on Green background of +2.

B.

Black number(s) on Yellow background of -2.

C.

White number(s) on Red background of +20.

D.

White number(s) on Red background of -20.

A. CORRECT: Green is ASCM numbers are +

B. Yellow is ISCM numbers are

C. Red is Superheat numbers are +

D. Red is Superheat numbers are +

NEW NRC exam 2002 KEH 9/25/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

12

11150502002

ANSWERS:

Points[

I

K/A

IE03EK1

RO Import.

SRO Import

.2

13.8

k.0

Version Answers:

0 1 2 3 4 5 6 7 8 9

1AIB c IC

1)IAIB c

IC1)IAI1B I Scr

Initial/Re

System

h3 [2/3]

SPFDS

Scramble Choices

amble Range: A -

Page: 30

W

Friday, January 18, 2002 @ 06:51 AM

26. 4-25 001/7//0720402013/061AA1.01/3.6/3.6/33 [2/3]/RM

Which of the following would cause the control board operator to request chemistry to sample

for failed fuel?

A.

Power has been stable at 80% rated thermal power for the last 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; RM-A7,

nuclear sample room monitor, is in warning.

",B.

Power has been stable at 80% rated thermal power for the last 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; RM-L I,

letdown monitor, is in warning.

C.

Power decreased rapidly 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago, but is now stable at 55% rated thermal power;

RM-G3, aux building sample room monitor, is in warning.

D.

Power decreased rapidly 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago, but is now stable at 55% rated thermal power;

RM-L7, disharge canal monitor, is in warning.

A. Sample room does not indicate failed fuel.

B. CORRECT; Stable power with a letdown monitor warning, the AR has the operator call for

a sample.

C. Sample room does not indicate failed fuel.

D. Down power can create a spike and it is anticipated after a down power, RM-L7 would not

be the first indication of failed fuel.

INPO Bank: KEH 9/25/01 NRC 2002 exam

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

17

10720402013

061AA1.01

13.6

3.6

33 23

ANSWES.

Version Answers:

1e

Points

0 1 2 3 4 5 6 7 8 9

E Scramble Choices

FB c DIoAIB lC ID IAl1le

Scramble Range: A-

d

Page: 31

2k2com.bnk

Friday, January 18, 2002 @ 06:51 AM

27. 4-25 002/ 4//0720102001/ 072A4.03/ 3.1/3.1/33 [1]/ RM

Placing an RMG ratemeter module check source switch in the "CHECK SOURCE" position

will provide which of the following indications in the control room?

A.

No scale reading change on the detector, both warning and high alarm lights will be

lit.

/B.

Up scale reading on the detector, warning and high alarm lights may or may not be

lit.

C.

Mid-scale reading on the detector, the warning alarm light will be lit.

D.

Full scale reading on the detector, the high alarm light will be lit.

A. This checks the detector movement, the alarms would not light without meter movement.

B. CORRECT: This shows the detector response, and depending on the strength of the source it

may actuate the warning or even the high alarms.

C. This will move based on the strength of the source and the warning may or may not be lit.

D. The movement may move to full scale, however, the warning light should also be lit, prior

to the high alarm.

NEW 2002 NRC exam KEH 10/1/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

14

1

b720102001

172A4.03

b.1

h.1

133 [1

AhNSWERS:

Version Answers:

PointsF _5]

0 1 2 3 4 5 6 7 8 9

EN Scramble Choices

IB C IDIAJIBIcDIABIC I Scramble Range: A -

R

Page: 32

2kcom.bnk

Friday, January 18, 2002 @ 06:51 AM

28. 4-25 003/3/ / 0070402004/ 068K6.10/2.5/2.9/ 33-[2/3]/

The following plant conditions exist:

- The plant is in Mode 6 with refueling operations in progress.

- The 'A' DH Train is in service.

- Control room operators notice a slow decreasing trend in refueling canal water

level.

Which of the following combination of indications could be used to determine the reason for

the decrease in refueling canal water level?

A.

If the leak is into the SF cooler; RM-L3 would increase and DHCCC surge tank

level would increase.

"-B.

If the leak is into the DHHE; RM-L5 would increase and DHCCC surge tank level

would increase.

C.

If the leak is into the SF cooler; RM-L5 would increase and SW surge tank level

would increase.

D.

If the leak is into the DHHE; RM-L3 would increase and SW surge tank level would

increase.

Reasons:

A.

RM-L3 will not detect a leak into the SF system.

B.

CORRECT. RM-L5 will detect a leak into the DC system.

C.

RM-L5 will not detect a leak into the SF system.

D.

RM-L3 will not detect a leak into the DC system.

ROT 4-25 Table 3, OPS 4-55 Obj. 3; AR-301 EP 0204; K/A #'s 068K1.01 2.4/2.6, 034A1.02

2.9/3.7, 008K1.04 3.3/3.3, A08AK2.2 3.8/4.0; Task # 0020402013

NRCN; LOI1-T5

BANK

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

r3

1

10070402004

1068K6.10

ý.5

2.9

133-[2/3]

Page: 33

2kcom.bnk

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

28. 4-25 003/3//0070402004/ 068K6.10/2.5/2.9/ 33-[2/3]/

ANSWERS:

Version An

Points

ID01 23

Page: 34

swers:

4 5 6 7 8 9

E Scramble Choices

C

Scramble Range: A -

R

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

Page: 35

29. 4-25 004/4//1190101031/060AA1.02/2.9/3.1/ 33-[1J/01CYC2

A waste gas leak has just developed in the Waste Gas Decay Tank area. RM-A2, Auxiliary

Building Exhaust Duct Monitor; RM-A3, Auxiliary Building Exhaust Duct Waste Gas Area;

and RM-A8, Auxiliary Building Exhaust Duct Monitor, are in high alarm. The RO reports the

following fan status:

- AHF-9A, Penetration Cooling Fan is tripped.

- AHF-9B, Penetration Cooling Fan is off.

- AHF- 10, Fuel Handling Area Supply Fan is running.

- AHF-l lA, Auxiliary Building Supply Fan is off.

- AHF-I lB, Auxiliary Building Supply Fan is off.

- AHF-30, Chemistry Laboratory Supply Fan is running.

- AHF-34A, Hot Machine Shop Welding Hood Exhaust Fan is tripped.

Which of the following components may need to be evaluated for proper operation?

A.

RM-A3 because AHF-9A and AHF-34A are tripped.

B.

RM-A3 because AHF-10 and AHF-30 are running.

"C.

RM-A2 because AHF-10 and AHF-30 are running.

D.

RM-A2 because AHF-9A and AHF-34A are tripped.

Reasons:

A. and B. RM-A3 in high alarm automatically trips AHF-11A and AHF-1 lB. There is no

interlock between RM-A3 and AHF-9A, AHF- 10, AHF-30 and AHF-34A.

C. Correct, RM-A2 in high alarm automatically trips AHF-9A, AHF-9B, AHF-10,

AHF-1 1A, AHF-I IB, AHF-30, and AHF-34A.

D. RM-A2 in high alarm automatically trips AHF-9A, AHF-9B,

AHF- 10, AHF- I1A, AHF-1 1B, AHF-30, and AHF-34A.

New question written for LOI-99-01 SRO Audit exam (3-1-2000 mg)

Removed any mention of operability and now is a common question KEH 5/21/2001

BANK

Friday, January 18, 2002 @ 06:51 AM

hKWCom.Dl

29. 4-25 004/4//1190101031/ 060AAI .02/ 2.9/ 3.1/33-[11 / 01CYC2

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

R

14

11190101031

060AA1.

ANSWERS:

PointsF

1

1K

Page: 36

0 Import.

SRO Import

Initial/Re

System

101CYC2

.02

2.9

b.1

133-[1]

Version Answers:

0 1 2 3 4 5 6 7 8 9

ZScramble Choices

Scramble Range: A -

w

Friday, January 18, 2002 @ 06:51 AM

30. 4-25 005/4//0720402002/ 029K1.01 / 3.4/3.7/33-111/

Given the following plant conditions:

- Mode 5

- RB purge in progress

- RMA- 1 (RB purge exhaust duct radiation monitor) gas high alarm actuates

Which of the following components are interlocked (stop or close) in this condition?

A.

AHF-6A/6B (RB purge supply fans)

B.

AHF-7A/7B (RB purge exhaust fans)

C.

AHFL- 1 A/l B (RB purge exhaust dampers)

,/D.

AHV- I A/1 B/ IC/ID (RB purge supply/exhaust valves)

Reasons:

A/B Per AP-250 the fans must be tripped manually

C- these dampers are to the charcoal filters and are not interlocked with RMA- I

D- CORRECT RMA- 1 is interlocked to close AHV- I A/B/C/D

Other K/A 069AA 1.01 3.5/3.7/ 029K4.03 3.2/3.5

MODIFIED BANK

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

14

1

10720402002

29K1.01

.4

13.7

133- 1

ANSWERS:

Version Answers:

0123456789

ige

Points[=

I1 IA

1B IC D IA IB IC In

lAI

E Scramble Choices

Scramble Range: A -

Wý

Page: 37

2kcom.bnk

Friday, January 18, 2002 @ 06:51 AM

31. 4-28 001 / 4// 0080402011 / 001 K1.09/ 2.8/ 3.1/ 33 [2/3y/C RD

Given the following plant conditions:

CRD system is de-energized

Which of the following provide the Service water / Control Rod Drive interlock for the "A" and

"B" CRD breakers?

Service water flow switch in parallel with both CRD breakers closing coils.

Service water flow switch in series with each CRD breakers closing coil.

Service water pump(s) breaker contact(s) in parallel with both CRD breakers closing

coils.

Service water pump(s) breaker contact(s) in series with each CRD breakers closing

coil.

A. The flow switch can not be in parallel, it would not ensure SW flow.

B. CORRECT; The flow switch is in series with the closing coil of each breaker.

C/D. SW pump breaker contacts are not used.

NEW 2002 NRC KEH 8/9/01 No reference needed.

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

14

I080402011

I001K1.09

o

.8

13.1

3 [2/3]

ORD

ANSWERS:

Version Answers:

Points

=

0 1 2 3 4 5 6 7 8 9

LlScramble Choices

IB

DIA

IDIAIB

I Scramble Range: A-

[

A.

"/B.

C.

D.

Page: 38

2kcom.bnk

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

Page: 39

32. 4-28 002/4//0450402001/ 007EK2.02/ 3.5/3.6/33 [2/3]/ CRD

Given the following plant conditions:

Reactor trip from 100% power

Which of the following actuates the turbine trip?

A.

RPS reactor trip module will energize the reactor trip lockout relay.

"vB.

Redundant trip confirm circuit will energize the reactor trip lockout relay.

C.

RPS reactor trip module will energize the turbine trip lockout relays.

D.

Redundant trip confirm circuit will energize the turbine trip lockout relays.

A. The RTM does not interface with the Rx Trip [JO

B. CORRECT; Redundant trip confirm will actuate the Rx Trip [JO to trip the turbine.

C. RTM does not interface with the Turbine [JO relays

D. Redundant trip confirm does not interface with the Turbine trip [JO relays.

OPS 4-28 page 20 of 77 refers to the reactor trip lockout relay

NEW 2002 KEH 8/2/01

KEY WORDS:

Objective

Lesson Pla

T

14

0

ANSWERS:

ine

Points [

1

ask Numbe

K/A

RO Import.

450402001

1007EK2.02

13.5

Version Answers:

01 23456

1B

CID1A1ICD

7

1A

SRO Im

F.5

89

port

Initial/Re

133 [2/31

N Scramble Choices

Scramble Range: A -

System

ICRD

wý

I

I"

Friday, January 18, 2002 @ 06:51 AM

33. 4-28 003/3,4//0010402004/014K4.04/2.6/2.9/33-[1]/CRD

Given the following plant conditions:

- A power increase is in progress.

- Group 7 rods are at 50% withdrawn

- Rod 7-4 is stuck at 47% withdrawn.

- PI panel indication is selected to RPI.

Which of the following indications would indicate that rod 7-4 is no longer moving?

A.

Individual control rod position indication on PI panel.

B.

Individual control rod position indication on plant computer.

C.

Group average indication on MCB or plant computer.

vD.

Individual control rod position on zone reference position panel.

Reason:

A. & B.

With RPI selected neither the PI panel or plant computer will

indicate actual rod position, only rod position as a function of field

rotation.

C.

The group average cannot determine which particular rod is

D. CORRECT: the zone reference would show all the other rods at the

not moving.

50% zone reference

point and rod 7-4 would not have reached the 50 % level.

NOB 2002 NRC exam KEH 10/12/01

ROT 4-28 Section 1.4.8; [KA # 001K4.01 3.5/3.8; 001A3.05 3.5/3.5 ; Task # 0010402022;

0010402013

NRCN; ROTs 0- T8 & T8S; LOI1-TI

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

13,4

1

10010402004

1014K4.04

12.6

12.9

133-[1]

ICRD

ANSWERS:

Version Answers:

01 23456789

Pont

IA 1B ICMD IA lB IC IDJA I

LM Scramble Choices

Scramble Range: A -

Page: 40

Points=

2kcom.bnk

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

Page: 41

34. 4-28 004/5/ / 0010402019/001 G2.1.32/ 3.4/3.8/ 33-[2/31/

The following conditions exist:

- A reactor startup is in progress.

- Control rod groups 1 through 3 are fully withdrawn.

- Group 4 rod withdrawal is stopped at 48%

- Source range NI counts are 540 cps and slowly increasing on NI- I and NI-2

- Start-up rate is 0.2 DPM and constant on NI-I and NI-2

- All rod motion has been stopped

Which of the following states the appropriate actions for the conditions stated above?

A.

Monitor the increasing count rate and verify power stabilizes below the point of

adding heat before continuing rod withdrawal.

B.

Insert group 4 control rods, verify a Shutdown Margin of more than 1% exists and

inform the Reactor Engineer of plant conditions.

C.

Insert groups 1 through 4 sequentially, request Chemistry to resample the RCS for

boron concentration, and recalculate the ECP.

"VD.

Trip the reactor and enter EOP-2, Vital System Status Verification.

Reasons:

A.

The indications in the stem of this question show that the reactor has

achieved criticality on Safety Rods. Limits and Precautions of OP-502

direct the crew to immediately trip the reactor and enter EOP-2.

Continued power increase should not be permitted.

B.

Insertion of all safety rods is required for these conditions. Insertion of

only group 4 rods is not adequate.

C.

The safety rods should be inserted by tripping the reactor, not

sequential insertion.

D.

Correct Answer: The indications in the stem of this question show that

the reactor has achieved criticality on Safety Rods. Limits and

Precautions of OP-502 direct the crew to immediately trip the reactor

and enter EOP-2.

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

34. 4-28 004/ 5//0010402019/ 001 G2.1.32/ 3.4/3.8/ 33-[2/3]/

New question written for Sept. 2000 RO and SRO exam. (3-8-00 CMC)

Additional Task # 0010102004, 0010502001

REPEAT

KEY WORDS:

Objective

Lesson Pla

151

ANSWERS:

Points

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

10010402019

100G2.1.32

13.4

h.8

-h3-[2/31

Version Answers:

0 1 2 3 4 5 6 7 8 9

Scramble Choices

1IDIE

JI IoIIIABcDA

Scramble Range: A -

System

I

Wd

Page: 42

Friday, January 18, 2002 @ 06:51 AM

35. 4-28 005/3//1150502001 / 014A2.01/ 2.8/ 3.3/ 33-[1]/

Following a loss of off site power, what are the indications, if any, that Control Rod groups I

through 7 are fully inserted?

A.

The CRD panel is de-energized, there are no indications that CRD groups 1 through

7 are fully inserted.

B.

All in-limit lights on the position indication panel and the diamond control panel are

on.

V'C.

Only the in-limit lights on the position indication panel are on.

D.

Only the in-limit lights on the diamond control panel are on.

Reasons:

A. Following a plant modification made in 1999 (MAR 96-07-17-03) a battery

backup power supply was added that powers the position indication in-limit

lights following a loss of off-site power. The in-limit lights on the position

indication panel would be on.

B. The CRD system is de-energized, only the in-limit lights on the position

indication panel would be on.

C. Correct, because of the installation of MAR 96-07-17-03 only the in-limit lights

on the position panel would be on.

D. The in-limit lights on the diamond control panel will be de-energized.

New question written for Sept 2000 RO and SRO exam. (3-22-2000 mg)

REPEAT

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

13

1

11150502001

1014A2.01

12.8

13.3

133-[1]

1

ANSWERS:

Version Answers:

0 1 2 3 4 5 6 7 8 9

ZScramble Choices

Ic D

1A IB I ID 1A I IC ID I Scramble Range: A -

Page: 43

FD]

Points=[

2k2com.bnk

Friday, January 18, 2002 @ 06:51 AM

36. 4-52 001/ 3,4//0040402006/ 004G2.1.30/ 3.9/ 3.4/ 33-[11/ MUP

Given the following plant conditions:

- 100% full power.

- "B" MUP is in operation.

- Channel "B" (LT-2) is selected for MUT indication.

Which of the following describes the response of the makeup system if the Channel "A"

(LT- 1), MUT level transmitter fails low?

"/A.

B.

C.

D.

Only "A" side BWST suction valve (MUV-73) will receive an open signal.

Only "B" side BWST suction valve (MUV-58) will receive an open signal.

Both "A" and "B" side BWST suction valves (MUV-73/58) will receive an open

signal.

Neither BWST suction valve (MUV-73/58) will receive an open signal.

Reasons:

A. CORRECT: LT-I ("A" Channel) supplies the signal to MUV-73

B., C. & D.

These transmitters control their individual BWST suction valves.

OPSA1.BNK 2002 NRC exam KEH 10/12/01 [004A3.09 3.3/3.2]

NRCM; ROTs 0 - T13; LOI1-T9AR/T9AS

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

13,4

1

10040402006

1004G2.1.30

.9

13.4

b3-[1]

IMUP

Version Answers:

0123456789

Z Scramble Choices

Pn B ICDA

B

Scramble Range: A -

ANSWERS:

W

Page: 44

Points=E*

2kcom.bnk

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

Page: 45

37. 4-52 002/3,4,7//1150402016/057AA1.05/3.2/3.4/33-[l ]/MUP

Given the following plant conditions:

100% power

NNI-X power is lost.

Which of the following describes how seal injection flow to the RCPs would be controlled via

MUV-16, seal injection control valve?

vA.

Will respond in the manual mode.

B.

Will respond in auto from a backup power supply.

C.

Will fail closed, the bypass valve, MUV-452, will need to be throttled.

D.

Will fail open, the auxiliary building operator will need to control flow locally.

A. CORRECT: Will control in manual with a loss of NNI-X

B. No auto power backup exist.

C. The valve does not fail closed.

D. The valve does not fail open.

OPSA1BNK 2002NRC exam KEH 10/12/01

ROTs K - T2; ROTs M - T6B

KEY WORDS:

Objective

Lesson Pla

Task Numbe

13,4,7

1

11150402016

ANSWERS:

inge

JPoints

=

K/A

RO Import.

SRO Import

Initial/Re

System

157AA1.05

1.2

13.4

h3-[l

IMUP

Version Answers:

0123456

789

[

Scramble Choices

A

IScramble

Range: A -

Wd

Friday, January 18, 2002 @ 06:51 AM

38. 4-55 001 / 7/ / 0070402005/ 026A1.06/ 2.7/3.0/ 33-[2/3]/ DHCC

Given the following plant conditions:

- Reactor Coolant pressure is 1600 psig.

- Reactor Building pressure is 2.1 psig.

- The "B" Decay Heat Closed Cycle Cooling Pump (DCP-lB) is tagged out for

maintenance.

Which of the following safety related equipment will be without cooling water?

A.

MUP-1C, RWP-2B and BSP-lB are without cooling water.

B.

MUP-1B, RWP-3B and BSP-1B are without cooling water.

C.

MUP-LB, RWP-2B and BSP-1B are without cooling water.

vD.

MUP-IC, RWP-3B and BSP-IB are without cooling water.

A. RWP-2B is cooled from SW

B. MUP- IB is cooled from SW

C. MUP-1B and RWP-2B are cooled from SW

D. CORRECT: All of these pumps are cooled from DC "B"

OPSA1.BNK 2002 NRC exam KEH 10/12/01

ROTs 0 - T8 & T8S; LOIL-T8AR/T8AS

KEY WORDS:

[008K1.02 3.3/3.4]

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

17

1

10070402005

1026A1.06

.7o

.3-[2/3]

IDHCC

ANSWERS:

Version Answers:

0123456789

LJ Scramble Choices

Pn A ABCD

A

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w

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Page: 46

Points=

Friday, January 18, 2002 @ 06:51 AM

39. 4-56 001/ 4/ / 0080402006/ 008K4.09/ 2.7/2.9/ 33-[11/SW

Given the following plant conditions:

-

The "C" Nuclear Services Closed Cycle Cooling Water Pump (SWP-1C) is in

operation.

-

An accident in the seawater room results in completely shearing off the SW

surge tank suction line.

Which of the following describes the initial response of the SWPs?

A.

SWP-1B auto starts and SWP-1C trips. SWP-lA remains in standby.

vB.

SWP-1B auto starts first; then SWP-1A auto starts and SWP-IC trips.

C.

SWP-1A auto starts first; then SWP-1B auto starts and SWP-IC trips.

D.

Both SWP- 1 A and SWP- I B auto start and SWP- 1 C continues to run.

Reasons:

A. SWP-LA auto starts 8 seconds later.

B. CORRECT: SWP-LB starts first, the loss of suction low pressure would require SWP-IA.

The first Emergency SWP that starts, will then tripSWP-1C 15 seconds later

C.

SWP-IB auto starts first.

D. SWP-IC trips 15 seconds after SWP-LA or lB starts.

NOB 2002 NRC exam KEH 10/12/01

K/A # 076K4.02 2.9/3.2; 008K4.01 3.1/3.1;

NRCN; LOI-99-01 FPCF; LOI1-T9BR/BS

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

14

1

k)080402006

108K4.09

1.7

12.9

133-[li

Sw

ANSWERS:

Version Answers:

Points

01 23456789

[E Scramble Choices

[D Jk Scramble Range: A -

W

Page: 47

2kcom.bnk

IF IC D

TATC

II D I

Friday, January 18, 2002 @ 06:51 AM

40. 4-57001 / 7//0760402003/075K1.01/2.5/2.5/33-[2/3J/RW

Given the following plant conditions:

- A controlled plant shutdown is in progress due to a shaft failure of RWP-2A.

- The reactor is critical with RCS temperature at 5450 F.

- PZR level is 95".

- The SPO reports that CWTS-2 is completely clogged with debris and will not

the flume water level is almost empty.

start and

Which of the following actions, and applicable reasons for these actions, should be performed?

No action required, RWP-1 and RWP-2B are not affected.

Trip the reactor and initiate EFIC due to the loss of CW cooling to the condenser.

Trip the reactor due to low PZR level.

,D.

Trip the reactor due to the loss of SW RW flow.

Reasons:

A. This failure will render RWP- 1 and RWP-2B inoperable. The reactor

should be tripped due to the loss of SW RW flow.

B. CW cooling is not affected by this failure.

C. During a plant startup or shutdown PZR level is allowed to be < 100"

without tripping the reactor.

D. CORRECT: The reactor should be tripped due to the loss of SW RW flow. Al-505 memory

item.

OPSA1.BNK (5-14 001) 2002 NRC exam KEH 10/11/01

NRCN; ROTs O - T13 K/A # G2.4.1 4.6/4.6

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

17

01760402003

1075K1.01

.5

I.5

133-[2/3]

IRW

ANSWERS:

Version Answers:

01234567

8 9

E] Scramble Choices

Pn l LDJAI

Scramble Range: A -

A.

B.

C.

d

Page: 48

PointsF-1]

2kcom.bnk

ID

1A113eICID A1B IC

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

Page: 49

41. 4-59 001/ 4,5,7/ / 1150402011/ 059AK2.01 / 2.7/2.8/33 [2/3]/ RWL

During a liquid release, the control board operator receives an RM-L2 trip on a valid high

radiation condition.

Which of the following combinations of actions must be performed by operations?

A.

The auxiliary building operator must be notified to ensure that the release isolation

valve (SDV-90) has automatically closed; the same liquid radwaste release permit

will apply when the release is restarted.

B.

The auxiliary building operator must be notified to ensure that the release isolation

valves (WDV-891/892) have automatically closed; the same liquid radwaste release

permit will apply when the release is restarted.

C.

The auxiliary building operator must be notified to ensure that the release isolation

valve (SDV-90) has automatically closed; the liquid radwaste release permit will be

closed out.

vD.

The auxiliary building operator must be notified to ensure that the release isolation

valves (WDV-891/892) have automatically closed; the liquid radwaste release

permit will be closed out.

A. Valve (secondary release) and the release permit must be regenerated.

B. Release permit must be regenerated.

C. Valve (secondary release).

D. CORRECT; isolate release, and must start the release process over.

INPO bank: KEH NRC exam 2002 9/25/01

WORDS:

ctive

Lesson Pla

Task Numbe

K/A

1

11150402011

059AK2"

ANSWERS:

Points LIII

RO Import.

SRO Import

Initial/Re

.01

12.7

k.8

k3 [2/3]

Version Answers:

0 1 2 3 4 5 6 7 8 9

Scramble Choices

IIAiIDA1

A

Scramble Range: A -

KEY

Obje4

4,5,7

System

IRWL

d

Friday, January 18, 2002 @ 06:51 AM

42. 4-60 001 / 7//0020402003/ 004K3.04/ 3.7/ 3.9/33 [2/3/ RCP

Given the following plant conditions:

100% power.

MUV-16 (RCP seal flow control valve) fails closed.

Service water flow to the RCPs is maintained.

Which of the following action(s) is correct with regard to the RCPs?

A.

Trip all RCPs within 2 minutes.

B.

Trip all RCPs within 5 minutes.

C.

Trip all RCPs within 30 minutes.

D.

No action is required.

A. This is the action if loss of both Seal injection and SW both.

B. This is the action if loss of SW to the RCPs.

C. This is the action if loss of SW to the RCPs if in an EOP.

D. CORRECT: as long as SW is available you can operate without seal injection.

NEW 2002 NRC KEH/MKG 8/9/01 No references required these are L&Ps in OP-302 and

402.

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

17

1

0020402003

b04K3.04

13.9

133 [2/3

oRCP

ANSWERS:

Version Answers:

Points

=

0 1 2 3 4 5 6 7 8 9

LE Scramble Choices

I DA1BICIDIAICIDIJAI

Scramble Range: A -

d

Page: 50

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Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

Page: 51

43. 4-62 001/ 3/2-30/0260502004/ 027G2.1.28/ 3.2/ 3.3/33-[11 /

Which one of the following parameters is controlled to limit the amount of iodine in the RB

atmosphere following a LOCA?

A.

The volume of galvanized metal inside containment.

B.

The volume of aluminum inside containment.

"C.

The pH of the RB sump.

D.

The temperature of the RB atmosphere.

Reasons:

A.

B.

This parameter is limited to reduce the amount of post-LOCA hydrogen

and does not affect iodine in the RB atmosphere.

This parameter is limited to reduce the amount of post-LOCA hydrogen

and does not affect iodine in the RB atmosphere.

C.

Correct Answer. TSP baskets inside containment adjust the pH of the

RB sump to between 7.0 and 11.0. This range of pH creates non-volatle

iodine and limits the amount of iodine in the RB atmosphere.

D.

RB spray limits containment pressure by spraying liquid into the steam

atmosphere but any reduction of RB temperature is a byproduct of this

pressure reduction and not intended to limit iodine in the RB

atmosphere.

New Question written for Sept. 2000 RO and SRO exam. (3-6-00 CMC)

Additional Task numbers; 1150502007, 1150402016

REPEAT

KEY WORDS:

0 13

bjective

Lesson Pla

Task Numbe

ý-30

10260502004

ANSWERS:

Points

K/A

RO Import.

SRO Import

Initial/Re

0272.1.28

.2

13.3

133- [1

Version Answers:

0 1 2 3 4 5 6 7 8 9

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Scramble Range: A -

System

I

Wd

Friday, January 18, 2002 @ 06:51 AM

44. 4-63001/4//1030402002/103A1.01/3.7/4.1/33[2/31/RB VENT

Given the following plant conditions:

Small RCS leak.

Containment temperature 150 0F.

AHF-IA is running in slow speed (AHF-I A/B are ES selected).

ES actuates.

Which of the following is the final containment cooling fan configuration?

,A.

AHF-1A remains running in slow speed, AHF-1B is off.

B.

AHF-1A remains running in slow speed, AHF-1B starts in slow speed.

C.

AHF-1A trips, AHF-1B starts in slow speed.

D.

AH-IF-lA trips, AHF-1A starts in slow speed.

A. CORRECT: AHF- 1 A will continue to run in slow speed.

B. AHF-lB will not start even though it is ES selected.

C. AHF-1A will not trip, nor will AHF-1B start.

D. AHF-lA will not trip.

NEW CR-3 (MODIFIED INPO BANK) KEH 2002 NRC 8/21/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

14

1030402002

1,03A1.01

13.7

k.1

13 2/31

IRBVENT

ANSWERS:

Version Answers:

01 23456789

M Scramble Choices

PA 1t iBC ID IA 13 1

Scramble Range: A-

d

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Page: 52

Points=

Friday, January 18, 2002 @ 06:51 AM

45. 4-63002/3/ / 0620402007/ 022K2.01/ 3.0/3.1/ 33-[1/]

An electrical fault has resulted in ES MCC 3AB being de-energized.

Which of the following components will be unavailable as a result of this malfunction?

"/A.

Reactor Building Air Handling Fan 1C (AHF-IC)

B.

Nuclear Services Raw Water Pump IC (RWP-1C)

C.

Inverter IC (VBIT-IC)

D.

Make-up Pump IC Main Lube Oil Pump (MUP-2C)

Reasons:

A.

Correct Answer: AHF-IC is powered from ES MCC 3AB and would be

lost if this component is de-energized.

B.

RWP-IC is a 4160V load not powered from ES MCC 3AB..

C.

Inverter IC is not dependent on a single power supply and does not

receive power from ES MCC 3AB.

D.

MUP-2C is not powered from ES MCC 3AB.

New question written for Sept. 2000 RO and SRO exam. (6-20-00 CMC)

Additional Task # 0620402010

REPEAT

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

13

1

0620402007

1022K2.01

I.0

13.1

133-[11

ANSWERS:

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0123456789

E] Scramble Choices

Points

ID JA

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d

Page: 53

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Points=

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

Page: 54

46. 4-63 003/ 5,7/ /0880102014/ G2.3.9/ 2.5/3.4/ 33-[2/31/

Given the following plant conditions:

- Plant in MODE 5

- Containment purge in operation

- Outside ambient air temperature is 640F

- Both CFTs are being depressurized for maintenance and are currently at 100

psig.

- Rosemont pressure transmitters associated with RCS Pressure are being

calibrated by a team of I&C technicians in the RB.

A failure of all purge heaters has resulted in the following RB conditions:

- 95' RB Air Temperature is 650F

- 119'RB Air Temperature is 66°F

Which of the following statements describe action required for these conditions and the basis of

those actions?

A.

Depressurize both Core Flood Tanks to less than or equal to 40 psig to prevent

possible brittle fracture.

B.

Fully depressurize and drain both Core Flood Tanks to prevent boron stratification

and rocking up of core flood system piping.

"/C.

Suspend Rosemont transmitter calibration until RB Air Temperature is at or above

70 0F to ensure design input data is within analyzed conditions.

D.

Verify I&C calibration is temperature corrected to ensure base line data meets the

new RB temperature conditions.

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

46. 4-63 003/ 5,7/ / 0880102014/ G2.3.9/2.5/3.4/ 33-[2/3]/

Reasons:

CFTs are already below the 140 psig brittle fracture value associated

with RB temperatures below 70'F. No requirement exists to further

depressurize the tanks to 40 psig.

Temperatures below 70°F pose a brittle fracture concern if CFTs are

pressurized above 140 psig but no requirement exists to depressurize

and drain a CF' that is below this temperature. Normal CFT boron

concentrations would not lead to boron coming out of solution at ambient

temperatures of 68°F or 69°F.

Correct Answer. Per the Limits and Precautions of OP-417,

Containment Operating Procedure, the crew must maintain RB air

temperature at or above 70'F during instrument calibration. The basis

of the L&P states that this is to ensure design inputs utilized and

specified by design calculation are maintained in order to keep the plant

within analyzed conditions.

No temperature correction of calibration base line data is required.

Further calibration should not occur until RB air temperature is at or

above 70'F.

New Question Written for Sept. 2000 RO and SRO exam. (3-29-00 CMC)

Additional Task # 1150402016

REPEAT

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

15,7

1

10880102014

0G2.3.9

.5

13.4

ANSWERS:

Version Answers:

0 1 2 3 4 5 6 7 8 9

Scn

SPoints=*

C D1

s*

I AF C

Scr,

Initial/Re

33-[2/3]

Scramble Choices

amble Range: A -

System w

W

Page: 55

A.

B.

C.

D.

Friday, January 18, 2002 @ 06:51 AM

47. 4-68 001/ 3,4/ / 0590102009/ 039A4.03/ 2.8/2.8/33 [1]/M FW

Which of the following is available on the main control board (ICS section) for the main

feedwater turbine?

,A.

Control valve position.

B.

First stage pressure.

C.

Steam pressure (chest).

D.

Turbine rotor position.

A. CORRECT: The control valve position on scale 0 - 100 % just above rpm meter.

B. Main Turbine indication in control room, NOT MFW turbine.

C. Main Turbine indication in control room, NOT MFW turbine.

D. Main Turbine indication in control room, NOT MFW turbine.

NEW NRC exam 2002 KEH 10/1/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

13,4

10590102009

139A4.03

1.8

V8

1331]

I FW

ANSWERS:

Version Answers:

Points

0123456789

N Scramble Choices

I A lB ICIDiJA

JAJjB

Scramble Range: A-

N

Page: 56

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Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

Page: 57

48. 4-69 001/ 4//0590402001/ 056K1.03/ 2.6/2.6/ 33-[1]/

Which of the following describes the direct signal that decreases condensate flow demand on a

loss of one MFW pump at 80% power?

that compares existing

CD

pump speed with FW flow and hotwell level.

pump speed with FW flow and deaerator level.

flow with FW flow and hotwell level.

flow with FW flow and deaerator level.

A.

FW flow and CD pump speed do not modifiy condensate demand.

B.

FW flow and CD pump speed do not modifiy condensate demand.

C.

FW flow and CD flow are compared to modifly condensate demand. Hotwell

level will increase but this will only modify the position of CDV-88, not

actual CD demand.

D.

FW flow and CD flow are compared to modifiy condensate demand.

Deaerator level is another part of the comparison.

This question also addressed K/A #'s 056K6.03 2.1/2.4, 059K1.01 2.3/2.3; Unmodified repeat

question from LOI 99-01 program; NRCN

BANK

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

Sys

14

1

0590402001

1056K1.03

.6

12.6

b3'[ 1

ANSWERS:

Version Answers:

0 1 2 3 4 5 6 7 8 9

Scramble Choices

Points

DAB

]

Scramble Range: A -

A

A.

B.

C.

,D.

Reasons:

signal

tern

d

Page: 58

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

49. 4-90 001/ 3,4,9//1150502011/055EA1..06/4.1/4.5/33 [2/3]/ ELEG DIST

Given the following plant conditions:

Recovering from a station blackout condition.

No offisite power available.

Only the "A" EDG operable.

Which of the following is correct?

A.

The EDG output breaker handle must be momentarily held in the "close" position to

override the ES bus undervoltage relay.

/B.

The EDG output breaker will automatically close once the EDG has started and all

other feeder breakers to it's respective bus are open.

C.

The EDG output breaker will automatically close once the EDG has started and 2

minutes have elapsed from the engine ready light being energized.

D.

The EDG should be used to backfeed the "B" 480 VAC ES bus to restore essential

loads.

A. This is for a feeder breaker from offsite power source, with no EDG running.

B. CORRECT: Cross tie blocking has all feeders open then the EDG breaker will auto close.

C. The 2 minutes is if the EDG had tripped then the SDR has a 2 minute timer.

D. This would cross tie the ES busses, no train separation.

NEW 2002 NRC exam KEH 10/1/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

13,4,9

1

11150502011

1055EA1.06

k.1

k.5

b3 [2/3

IELEC DIST

Version Answers:

ANSWERS:

Points [D

0 1 2 3 4 5 6 7 8 9

H Scramble Choices

IB IDJIA

cDA

C

Scramble Range: A -

d

Friday, January 18, 2002 @ 06:51 AM

50. 4-90 002/3,4,7// 0640402001/ 064K3.02/ 4.2/4.4/ 33-[1]/ EDG

Given the following plant conditions:

A High Pressure Injection (HPI) actuation has started the "A" Emergency Diesel Generator

(EDG- IA).

Undervoltage on the "A" ES bus occurs

Which of the following would prevent EDG-1A automatic breaker (3209) closure?

EDG-lA is operating at 61 Hz and 4200 volts.

EDG-lB is running with its output breaker (3210) closed.

The under-voltage relays are tripped and the normal feeder breaker is still closed.

The synchronizing check relays sense an out of phase condition.

Reasons:

A. These conditions would not prevent breaker closure.

B. This is not a cross-tie blocking situation.

C. CORRECT: With the UV condition and the feeder still closed this is in the close circuit for

3209, a "b" contact for the feeder breaker.

D. The sync. check relays are not in the automatic breaker closure circuit.

OPSA1.BNK 2002 NRC exam KEH 10/12/01 [064A4.06 3.9/3.9]

NRC 6-97; ROTs M - T6A; ROTs N - T4 & T4A; ROTs 0 - T14

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

13,4,7

1

10640402001

1064K3.02

I.2

.4

133-[11

JEDG

ANSWERS:

Version Answers:

0123456789

IC I l 1B C ID

I

AoIA

C

Ic D I

E Scramble Choices

Scramble Range: A -

A.

B.

"/C.

D.

Page: 59

2kcom.bnk

Points=

Friday, January 18, 2002 @ 06:51 AM

eK2C

51. 4-90 003/ 4//0640202001 / A05AK2.1/ 4.0/3.8/ 33-[2/3]/

The following light indications are present

on the main control board.

Startup

BEST

Unit Aux

EDG

OPT

3203

3205

3207

3209

3211

3204

3206

3208

3210

3212

E SE,-L DU A

EPUSF

I

t.R

FtECK CL OsYN3

SCTLA TIED 31tE

A.CT1J A TED :Y*5

EtECPC CL Ol5[N'D

ACTUA TED 32L7]

A plant startup is in progress with reactor power at 10%. Which of the following sets of

conditions will cause the above indication? Assume sufficient time for automatic actions to

have occurred.

A.

The offsite power transformer is OOS (tagged out) for oil leak repair.

SP-354A is in progress with Breaker 3209 closed.

A spurious 'A' train ES actuation has just occurred.

B.

SP-354A is in progress with Breaker 3209 closed.

The Startup Transformer is OOS (tagged out) for oil leak repair.

A loss of Off-Site power has just occurred, Bkr 3211 has failed to open.

'/C.

SP-354B is in progress with Breaker 3210 closed.

The Startup Transformer is OOS (tagged out) for oil leak repair.

A loss of Off-Site power has just occurred, Bkr 3212 has failed to open.

D.

The offsite power transformer is OOS (tagged out) for oil leak repair.

SP-354B is in progress with Breaker 3210 closed.

A spurious 'B'train ES actuation has just occurred.

om.bnk

0

a

Page: 60

Friday, January 18, 2002 @ 06:51 AM

51. 4-90 003/4/1/ 0640202001/ A05AK2.1/ 4.0/3.8/33-[2/31/

CHECK ENABLE LIGHT-should be on

Reasons:

A.

These conditions have 3205, 3206 and 3209 closed. 3210 will be blocked.

B.

These conditions have 3209, 3211 and 3212 closed. 3210 will be blocked.

D.

These conditions have 3205, 3206 and 3210 closed. 3209 will be blocked.

NRCM; ROTs 0 - T13

Additional K/A A05AK3.1 3.2/3.4

BANK QUESTION 2002 NRC EXAM 5/10/2001 KEH

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

14

1

ý640202001

V05AK2.1

.0

.8

3-2/3

ANSWERS:

Version Answers:

0123456789

[ý Scramble Choices

Pn I

D I

Scramble Range: A -

W

Page: 61

Points[=

2k2com.bnk

Ic ID1 I BC

IDIoIA 113

Friday, January 18, 2002 @ 06:51 AM

52. 4-91 001 / 3,5// 0620102001 / 062A3.04/ 2.7/2.9/33 [1]/ AC DIST

While starting an inverter (A,B,C,D) in accordance with OP-703 section 4.7 you must

"DEPRESS and HOLD" the precharge pushbutton.

Which of the following is the reason for this action?

A.

This will auto close the battery input breaker (DC) to the inverter once the inverter

output voltage reaches 120VAC.

v B.

This bypasses the battery input breaker (DC) to the inverter to minimize in rush

current.

C.

This charges the 85 second time delay relays to prevent unnecessary shifting of

inverters between the input supplies.

D.

This energizes the output auctioneer initially to select the AC input and maintain the

DC input in standby.

A. There is no auto closure of any input breakers on the inverters.

B. CORRECT: This will allow the DC side to charge and minimize the current rush.

C. The 85 second time delay relays are there but they do not need any charging.

D. The auctioneer is set to select the AC input as the preferred source.

NEW 2002 NRC exam KEH 10/1/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

13,5

1

0620102001

062A3.04

2.7

1.9

133 [11

AC DIST

ANSWERS:

Version Answers:

Points

0123456789

SICBI

ID IA

1B

I

C

I IA I

[I Scramble Choices

Scramble Range: A-

d

Page: 62

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Friday, January 18, 2002 @ 06:51 AM

53. 4-91 002/6/ /0620402017/ 057AK3.01/ 4.1/4.4/ 33-[2/31/

With the plant at 100% power a catastrophic failure of VBIT-1C rendered it inoperable and

caused both of the VBXSs that it feeds to fail "as is" (no transfer to their alternate power

supply).

Which of the following describes the EOP/AP action(s), if any, that should be taken?

AP-58 1, Loss of NNI-X, should be entered.

AP-582, Loss of NNI-Y, should be entered.

AP-430, Loss of Control Room Alarms, should be entered.

Trip both MFW pumps and the reactor due to the loss of ICS power. EOP-2, Vital

System Status Verification, and Rule 3, EFW Control, should be entered.

Reasons:

A. The ABT for NNI-X should transfer to VBDP-1 on a loss of VBDP-5.

B. Neither VBDP-5 or 9 feed NNI-Y therefore no loss of power should occur.

C. Correct, VBDP-5 powers the annunciator monitor and typer.

D. This would be the correct response for a loss of ICS power however neither

VBDP-5 or 9 feed ICS therefore no loss of power should occur.

NRCM; ROTs 0 - T13; Bank question (4-91 1) used for LOI-99-01 SRO and RO Audit exam

(8-8-2000 mg)

BANK

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

16

10620402017

1057AK3.01

14.1

.4

133-[2/3]

ANSWERS:

Version Answers:

0 1 2 3 4 5 6 7 8 9

SScramble Choices

Pn IDABC

D

Scramble Range: A-

Wd

A.

B.

D.

Page: 63

Points [=

2kcom.bnk

Friday, January 18, 2002 @ 06:51 AM

54. 4-93 001/ 4, 7, 9//0780402006/055K3.01/ 2.5/2.7/33-[2/3]/

The following plant conditions exist:

-

The plant is at 50% power, 437 MWe.

-

The "A" Condenser Air Removal pump, ARP-IA is in normal-after-start and

running.

-

There is a small condenser air leak.

-

Condenser vacuum has decreased to 6 inches Hg absolute and is

stable at that value.

If no actions are taken by operations personnel to mitigate these conditions, which of the

following describes the condition of the ARPs ?

A.

ARP-LA is running in the holding mode with the air ejector in service and the Main

Control Board low vacuum white lights are lit.

,B.

ARP-1A and ARP-1B are running in the holding mode with their air ejectors in

service and the Main Control Board low vacuum white lights are OFF.

C.

ARP-IA is running in the hogging mode with the air ejector bypassed and the Main

Control Board low vacuum white lights are lit.

D.

ARP-1A and ARP-1B are running in the hogging mode with the air ejector bypassed

and the Main Control Board low vacuum white lights are OFF.

Reasons:

A. ARP-LA is already running and the light should be OFF.

B. Correct, both ARPs should be running at 4" and the vacuum lights turn OFF at

4". However this condition is at 6".

C. ARP-1A is running, hogging mode starts at 7" and the vacuum lights turn

OFF at 4".

D. Hogging mode starts at 7".

New question written for LOI-99-01 SRO and RO Audit exam (8-4-2000 kh)

BANK

Page: 64

2kcom.bnk

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

54. 4-93 001/ 4, 7, 91 / 0780402006/055K3.01/2.5/2.7/33-[2/3]/

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO 1

14, 7, 9

780402006

1055K3.01

ý.5

ANSWERS:

Version Ans

01 23'

Points=

]I

IPIDins1

Page: 65

mport.

SRO Import

Initial/Re

12.7

133-[2/3]

swers:

4 5 6 7 8 9

[

Scramble Choices

Scramble Range: A -

System

I

d

Friday, January 18, 2002 @ 06:51 AM

55. 4-93 002/5,6,8// 0450402005/ 051AA2.02/ 3.9/4.1/11-[1l/

The following plant conditions exist:

- The plant is at 50% power.

- Condenser vacuum is 25 in-Hg and steady.

- Low pressure turbine exhaust temperature is 2580 F.

Based on these conditions which of the following action(s) should be taken?

A.

Restore vacuum to > 26.5 in-Hg within five minutes or trip the turbine.

B.

Immediately reduce power to < 30% and trip the main turbine within five minutes.

"C.

Trip the main turbine immediately.

D.

Increase hood spray flow.

Reasons:

A.

B.

If reactor power was less than 30% then this would be the correct action

to take, based on vacuum only.

If vacuum was < 24.5 in-Hg then this would be the correct action to take,

based on vacuum only.

C.

CORRECT. Vacuum is adequate for this power level however with low

pressure turbine exhaust temperature > 250' F OP-607 requires the

turbine to be tripped immediately.

main

Vacuum is adequate for this power level however with low pressure

turbine exhaust temperature > 250' F OP-607 requires the main turbine

to be tripped immediately. Hood spray is a fixed value. Flow cannot be

increased.

OPS 4-93 Section 1-8.A; OP-607 Steps 3.2.4 & 4.5.8; AR-603 EP 1634; KA #'s G2.1.32

3.4/3.8, G2.2.22 3.4/4.1

NRCM

BANK

D.

Page: 66

2kcom.bnk

Friday, January 18, 2002 @ 06:51 AM

2kWcom.bnk

55. 4-93 002/ 5,6,8// 0450402005/ 051AA2.02/ 3.9/4.1/11 -[1]/

KEY WORDS:

Objective

Lesson Pla

Task Numbe

KIA

RO Import.

SRO Import

Initial/Re

System

5,6,8

1

ANSWERS:

Points L

10450402005

1051AA2.02

3.9

4'

Ii'1-[1

Version Answers:

0 1 2 3 4 5 6 7 8 9

Scramble Choices

IC1fA1IIDAI

Scramble Range: A -

Page: 67

d

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

Page: 68

56. 4-93 003/6, 8// 0550402001/ 2.4.48/3.5/3.8/ [1]/

Given the following plant conditions:

The plant is performing a power increase and just completed passing through the Main

Feedwater Block valves.

The Turbine Vacuum Pre-Trip alarm (0-3-3) has actuated.

Main Condenser Vacuum (CD-007-PIR) indicates 5.5" Hg Absolute.

Which of the following parameter(s) can you check from the control room to identify a possible

cause of this low vacuum condition?

A.

Deaerator Level

B.

Gland Water pressure

"/C.

Hotwell Level

D.

Feedwater Pump Gland Seal Pressure

A,Monitored on the Main Control Board but should not affect vacuum

B,& D- Indication in the Turbine Bldg., not monitored in the Main Control Room

C- CORRECT on MCB, low or high level in hotwell can result in a Low vacuum.

NEW question for 2002 NRC exam 5/1/2001 1

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

16,8

I550402001

.4.48

ANSWERS:

Points

RO Import.

SRO Import

Initial/Re

13.5

13.8

111

Version Answers:

0 1 2 3 4 5 6 7 8 9

WScramble Choices

IC EI IA1B IC I1 IAIB IID

Scramble Range: A -

System

[

Page: 69

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

57. 5-01 001/ 4/ / 1190302001 / 076AA2.02/ 2.8/ 3.4/11 [2/3]/ RCS ACT

Given the following plant conditions:

Plant at 100% power

Plant at 80% power

Chemistry sampled the RCS

Chemistry analysis indicates:

Dose equivalent 1-131 concentration is 1.5uCi/gm

RCS specific activity is 50 uCi/gm

Gross specific activity is < 100/E(bar)

Which of the following Tech Spec actions if any would be required?

Reduce RCS activity to less than the Tech Spec limit immediately or be in MODE 3

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Reduce RCS activity to less than the Tech Spec limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in MODE

3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Reduce RCS activity to less than the Tech Spec limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in

MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

No action required, chemistry results are within the Technical Specification limits.

A. Actions are required but not immediately

B. Actions are required but more than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is allowed

CORRECT; See T.S. 3.4.15 condition A and B 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or MODE 3 W/I 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

Activity is outside of the TS limits

NEW 7/9/2001 KEH (Provide T.S. 3.4.15)

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

14

1

11190302001

1076AA202

12.8

13.4

i11 [2/3

IRCS ACT

ANSWERS:

Points

Version Answers:

01 23456

IC 1D 1A 1B IC 11 1A

7

TB

8 9

E Scramble Choices

C

Scramble Range: A -

d

0600

0700

1030

1230

A.

B.

D.

C.

D.

Page: 70

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

58. 5-100001/5//1150502008/056AK3.02/4.4/4.7/33 [1]/EOP-12

Given the following plant conditions:

Loss of the 230 KV switchyard

Both ES busses are de-energized

Reactor tripped

Loss of SCM has occurred

"B" OTSG MSSV sticks open

"B" OTSG is dry

Which of the following procedures contains the appropriate actions for these conditions?

A.

EOP-03, Inadequate Subcooling Margin.

B.

EOP-04, Inadequate Heat Transfer.

C.

EOP-09, Natural Circulation Cooldown.

"vD.

EOP-12, Station Blackout.

A. EOP-03 ISCM is next priority behind EOP- 12 for station blackout.

B. EOP-04 IHT has a lower priority

C. EOP-09 will not apply until NOT in any other EOP (entry condition)

D. CORRECT: per step 3.17 with a station blackout even with a loss of SCM remain in this

procedure

NEW 2002 NRC exam KEH 10/4/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

[5

1

I1150502008

056AK3.02

k.4

k.7

133

1

IEOP-12

ANSWERS:

[Sn1e

Version Answers:

0123456789

E Scramble Choices

IP IAiB IC ID

J

A15 IC ID 1A

Scramble Range: A -

N

Points [=

Page: 71

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

59. 5-101 001/1/ / 1150502005/ EPP2.4.2/ 3.9/4.1/33 [2/31/ EOP-06

Given the following plant conditions:

100% power

RCS pressure 2155 psig

RCS temperature 5790F

RCS makeup flow has increased from 60 to 65 gpm

Pressurizer level is slowly decreasing

RM-A2, (Auxiliary Building Ventilation Exhaust Duct) is in alarm

RM-A12, (Condenser Vacuum Pump Off Gas Exhaust) is in alarm

Which of the following entry condtions has been met?

A.

A small break LOCA is in progress, enter EOP-02, Vital System Status Verification.

B.

A small break LOCA is in progress, enter EOP-03, Inadequate Subcooling Margin.

C.

A tube leak is in progress, enter EOP-02, Vital System Status Verification.

'D.

A tube leak is in progress, enter EOP-06, Steam Generator Tube Rupture.

A. The Rad Monitors make this a specific tube leak, and must enter EOP-06.

B. The Rad Monitors make this a specific tube leak, and must enter EOP-06.

C. The Rad Monitors make this a specific tube leak, and must enter EOP-06, this leak has not

caused a Rx trip.

D. CORRECT: The Rad Monitors make this a specific tube leak, and must enter EOP-06.

BANK 2002 NRC exam KEH 10/2/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

I1

1

1150502005

IEPP2.4.2

b.9

14.1

3 2/3]

IEOP-06

Version Answers:

ANSWERS:

Points

0 1 2 3 4 5 6 7 8 9

E Scramble Choices

rD AIBIcID

nA

J

C

Scramble Range: A-

N

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

Page: 72

60. 5-102 001/5/ / 1150502003/ EO4EK2.1/ 3.8/4.2/11 [2/31/ EOP-4

Given the following plant conditions:

- Time is 5 minutes after a reactor trip due to loss of both Main Feedwater

Pumps.

- No Emergency/Auxiliary Feedwater Pumps are operating.

- Tincore is 590'F and increasing.

- RCS pressure is 2325 psig and increasing.

- All 4 RCPs are running.

- "A" OTSG level is 30 inches.

- "A" OTSG pressure is 1010 psig and stable.

- "B" OTSG level is 0 inches.

- "B" OTSG pressure is 800 psig and decreasing.

- RCS heat up rate is +30'F / Hr.

Which of the following action(s) is required concerning operation of the RCPs?

"/A.

Stop 1 RCP per loop.

B.

Stop 3 RCPs.

C.

Stop all 4 RCPs.

D.

Continue to run all 4 RCPs.

A. CORRECT; Step 3.9 of EOP-4 reduces the running RCPs to 1 per loop.

B. Misconception that leave 1 RCP for spray flow.

C. Do not place plant in NC with no other heat removal sources (OTSG), also have not

increased T incore 50' since the trip.

D. Running 4 RCPS just adds more heat to the RCS.

NEW 2002 KEH (7/12/01) Provide EOP-04.

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

15

1

1150502003

JEO4EK2.1

13.8

14.2

Ill [2/31

1EOP-4

ANSWERS:

Version Answers:

o 1 2 3 4 5 6 7 8 9

ZScramble Choices

iIPoints[A1BCID

JA Inc

A

Scramble Range: A -

Friday, January 18, 2002 @ 06:51 AM

61. 5-106 001/10// 0050102012/ 005K5.02/ 3.413.5/33 [2/3]/ PZR

Given the following plant conditions:

- RCS pressure is 255 psig

- RCS temperature is 260'F

- PZR level is 180 inches

- DHP-1A is running for RCS cooldown

- DHV-91 (Auxiliary Spray Isolation Valve) is open

As the operator throttles Auxiliary Spray valve RCV-53 it fails open causing a rapid outsurge

from the PZR.

Which of the following is a probable outcome of this event?

A.

Shutdown margin decreases to less than 1% deltaK/K.

A steam bubble forms in the hot leg.

C.

D.

The RCS cooldown rate would be > 50°F/hr.

The RCS pressure drops so low that DHP- IA starts to cavitate.

A. RCS/PZR boron is to be within 20 ppm, therefore this would not change SDM to less than

1%.

B. CORRECT; the outsurge would be water at about 402'F which would create a steam bubble

in the hot leg. Saturation temperature for 260'F RCS is about 40psig.

C. The outsurge is hot water, no cooldown would be seen.

D. The pressure drop would not cavitate a DHP with a suction from the RCS at something less

than 255 psig.

NEW CR-3 (INPO BANK) KEH 2002 NRC 8/21/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

110

1

10050102012

1005K5.02

.4

3.5

33 2/3

PzR

ANSWERS.

Version Answers:

0123456

7 8 9

E Scramble Choices

R

Point

IDJ1AACJABC

Scramble Range: A-

1e

Page: 73

Points=[

2kcom.bnk

Friday, January 18, 2002 @ 06:51 AM

62. 5-14 001/ 11/4-56 4/0080402010/076A2.01/ 3.5/3.7/ 11-[2/31/

Given the following plant conditions:

-

The plant is at 86% power.

-

The Nuclear Services Closed Cycle Cooling surge tank (SWT- 1) level is 1.8

feet.

-

Temperatures for components cooled by SW are rising.

-

The Secondary Plant Operator (SPO) reports large amounts of sea grass at the

intake.

-

The Primary Plant Operator (PPO) reports a large SW leak on the SWP

suction header.

Which of the following actions should be taken immediately?

A.

Start a plant shutdown.

B.

Start filling SWT-l.

C.

Place the standby SW heat exchanger in service.

/D.

Trip the reactor.

Reasons:

A., B., and C. All these actions are good ideas and proceduralized in AP-330, but with SWT-1

at < 2.0 feet the reactor needs to be tripped.

D. Correct, AI-505 and AP-330 have the operator trip the reactor when SWT- 1 is

< 2.0 feet.

Provide AP-330; New question written for LOI-99-01 SRO and RO Audit exam (7-19-2000 js)

BANK

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

Ili

k-56 4

10080402010

1076A2.01

1.5

h.7

I11-t2/3I

ANSWERS:

Version Answers:

0123456789

PoitsIIIDV

IA11 IC ID

JA lB IC ID JA I

E Scramble Choices

Scramble Range: A -

W

Page: 74

Points=[

[

2kcom.bnk

,"1 _,"

.

..

L-I-

Friday, January 18, 2002 @ 06:51 AM

hKhlCOm.DnK

Page: /7

63. 5-34 001/ 8/ //1150402005/ EPP2.4.12/ 3.4/3.9/33 [1]/ E-PLAN

Given the following plant conditions:

100% power.

A tube rupture occurs that results in an ES actuation on low RCS pressure.

An ALERT is declared based on the Fission Product Barrier Matrix.

Which of the following identifies the notification requirements for the CR-3 NRC resident,

plant personnel, and State Warning Point Tallahassee (SWPT)?

A.

Notify the CR-3 NRC resident and plant personnel within 15 minutes; notify State

Warning Point Tallahassee as soon as possible.

B.

Notify the CR-3 NRC resident and plant personnel in less than one (1) hour; notify

State Warning Point Tallahassee within 15 minutes.

"C.

Notify the CR-3 NRC resident and plant personnel as soon as possible; notify State

Warning Point Tallahassee within 15 minutes.

D.

Notify the CR-3 NRC resident and plant personnel within 15 minutes; notify State

Warning Point Tallahassee in less than one (1) hour.

A. Personnel as soon as possible, SWPT w/i 15 minutes.

B. Personnel as soon as possible, SWPT w/i 15 minutes.

C. CORRECT: Personnel as soon as possible, SWPT w/i 15 minutes.

D. Personnel as soon as possible, SWPT w/i 15 minutes.

NEW 2002 NRC exam KEH 10/2/01

KEY WORDS:

Objective

Lesson Pla

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

System

18

1

11150402005

EPP2.4.12

b.4

k.9

133 1

IE-1LAN

ANSWERS:

Points[*]

Version Answers:

0123456

7 8 9

M Scramble Choices

[ [

D

Scramble Range: A-

Wd

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

64. 5-61 001 / 7/4-56/ 0080402012/ 026AA2.01/ 2.9/3.5/ 33-[2/3]/

The following plant conditions exist:

- The nuclear services surge tank level is slowly decreasing.

- SWV-277 (SW Surge Tank fill valve) is full open.

- The RO has estimated the SW leak rate to be in excess of 80 gpm.

- The reactor building and auxiliary building sump levels are not increasing.

- All nuclear services heat exchangers have been rotated into operation with no

change in conditions.

- RCS makeup, letdown and MUT level are steady.

- There are no reactor building system leak annunciators in alarm.

Where is the location of the SW leak?

Page: 76

A.

The reactor coolant drain tank.

vB.

The industrial cooling system.

C.

The primary sample cooler.

D.

The in-service reactor coolant pump seal return cooler.

Reasons:

A.

No leak annunciators in alarm will rule this tank out. SW Tank level

lowering with the fill valve open indicates a leak greater than the 50 gpm

differential required to cause the leak annunciators to be in alarm. The ROs

leak rate estimate confirms the leak rate is greater than 50 gpm.

B.

This system is the only location for this leak for these conditions.

C.

The SW would not leak out of this cooler; RCS will leak into the SW

System.

D.

MUT level would increase or the auxiliary building sump level would

increase.

Friday, January 18, 2002 @ 06:51 AM

2k2com.bnk

64. 5-61 001/ 7/4-56/0080402012/ 026AA2.01/2.9/3.5/ 33-[2/3]/

AP-330 Step 3.7; Stem modified (SWV-277 and RO leak estimate info added) to remove

multiple correct answers otherwise this is an unmodified repeat question from LOI 99-01

program; NRCN

BANK

KEY WORDS:

Objective

Lesson Pla

17

I-56

ANSWERS:

[Snge

]

Points

Task Numbe

K/A

RO Import.

SRO Import

Initial/Re

10080402012

t26AA2.01

ý.9

13.5

b3-[2/3]

Version Answers:

0 1 2 3 4 5 6 7 8 9

ZScramble Choices

DB A