ML020510571
| ML020510571 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/06/2002 |
| From: | Operator Licensing and Human Performance Branch |
| To: | |
| References | |
| 50-302/02301 | |
| Download: ML020510571 (121) | |
See also: IR 05000302/2002301
Text
Draft Submittal
(Pink Paper)
Reactor Operator Written Exam
CRYSTAL RIVER EXAM
50-302/2002-301
JAN. 28 - FEB. 6, 2002
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: I
1. 4-10 001 / 7//0170502001 / 017G2.2.34/ 2.8/ 3.2/33 [2/3]/ NI
Given the following plant conditions:
PZR off scale low
RCS pressure 1200 psig and decreasing slowly
Core Exit Thermocouples (CETs) reading 950'F and increasing slowly
NI-1/2 reading 5000 cps and increasing
Self Powered Neutron Detectors (SPNDs) current readings increasing
Which of the following would explain the excore detectors increasing value?
A. Boron precipitation in the core.
B. Fuel coefficients effects.
VC. Voiding in the downcomer.
D. Temperature effects on the excore detectors.
A. Boron would be decreasing the neutron population.
B. Fuel coefficients would have a negative affect on neutron population.
C. CORRECT: Given the conditions with the plant in region 3 of ICC would have downcomer
voiding which will increase leakage for the excore detectors.
D. Temperature will not cause the indication to increase in the detectors.
NEW 2002 NRC exam KEH 10/3/01
KEY WORDS:
K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla Task Numbe 3 2/3 NI
I *3170502001 17G2.2.34 .8 .2
17
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Z Scramble Choices
Points IW]ID1A BDABcD Scramble Range: A- W
2K2RO.BNK Page: 2
Friday, January 18, 2002 @ 06:52 AM
2. 4-11 001 / 3//0830102005/ G2.1.19/ 3.0/3.0/ 33-[1]/ COMPUTER
none of the 52 Core
Which of the following control room indications is available to verify that
Exit Thermocouples have failed low?
,/A. Plant computer core map diagram.
B. Flashing incore temperature on the SPDS screens.
C. Flashing indication on the extended range core exit thermocouple display.
D. Incore recorder displays 000 for any of the 52 CETs failed low.
Reasons:
A. Correct, the plant computer has a CET display that includes the temperature
of each of the CET location and any bad readings are identified.
B. SPDS has several flashing alarms for parameters out of range; incore
is not one of those alarms.
flashing
C. The extended range core exit thermocouple displays do not have a
function.
D. Recorder only looks at 16 selected CETs, not all 52.
New question written for Sept 2000 RO and SRO exam. (3-9-2000 mg)
length. CMC
Modified 8-10-00 to add new distractor (D) and reorder answers according to
REPEAT
KEY WORDS:
K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla Task Numbe 1303-[1 ICOMPUTER
3 ý
1830102005 G2o119
ANSWERS: Version Answers: I7 Sramble Choices
0 1 2 3 4 5 6 9b S rm
Points=
IAIB ýýIII~c=AB Scramble Range: A- Wd
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: 3
3. 4-11 002/2/1/0170502001/ 017A1.01/3.7/3.9/33 [1/ SPDS
Which of the following explain the SPDS core exit thermocouple (CET) input(s) for display of
Inadequate Core Cooling (ICC)?
A. SPDS directly selects the highest from all 52 CETs.
B. SPDS directly selects the average of the 16 (EQ) CETs.
VC. SPDS is provided the highest of the 8 (EQ) CETs from its respective Chessel
recorder.
D. SPDS is provided the average of the 8 (EQ) CETs from its respective Chessel
recorder.
A. SPDS does not directly select from the core CETs for its input.
B. SPDS does not directly select CETs.
C. CORRECT: The SPDS is fed from its respective Chessel the high select CET.
D. The Chessel provides the CET input but SPDS does not use the average.
NEW 2002 NRC exam KEH 10/3/01
KEY WORDS:
Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla
12 1 0170502001 17A1.01 .7 .9 3 1 SPDS
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 [ScrambleChoices
[Pingl Points=i ICDID1A1BICID1A1BICID Scramble Range: A- W
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: 4
4. 4-13 001/ 5/ / 0130502001/ 013A2.06/ 3.7/4.0/33/ ESAS
Given the following plant conditions:
- RCS Pressure 2155 psig.
- RCS Temperature 5790 F.
- RB l for "B" Train is tripped in accordance with OP-507.
Which of the following correctly identifies the ES system response to a low failure (0 psig) of
RC-3A-PT4 (channel 2 ES)?
A. HPI, LPI, and RBIC would actuate on both trains.
B. HPI and LPI would actuate on both trains.
C. HPI and LPI would actuate on "A" train.
YD. HPI and LPI would actuate on "B" train.
A- Only the "B" channel has two channels actuated
B- Only one train (B) is affected
C- Only the (B) train is affected
D- Correct RB 1 on the (B) train and the #2 channel would actuated the (B) Train
See OP-507 Limit and Precaution
BANK QUESTION 2002 NRC EXAM 5/10/2001 KEH (RO ONLY)
BANK
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Imrport Initial/Re System
JESAS
15 1 10130502001 013A2.06 k.7 4.0 h3
ANSWERS: Version Answers:
Points [-'-I D=AB o l , Z Scramble Choices
0123456789
Scramble Range: A - wd
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: 5
5. 4-14 002/3/1/ 0410102007/ G2.2.2/ 3.5/3.5/ 33-[2/3]/
The following plant conditions exist:
- Plant is operating >> 20% power
- Both Main Feedwater Loop Master Hand/Auto stations are in HAND
- SUCV position >> 95% open.
- LLCV position >> 5% open
I&C technicians have requested that the "B" train SUCV and LLCV hand/auto stations be taken
to hand in order to record some data on the proportional/integral module suppling the input to
these stations. Permission is received and these stations are placed in manual.
Which of the following describes the minimum required actions to return the FW control valve
stations to automatic?
A. Place the SUCV in auto first, then place the LLCV in auto.
,/B. Place the LLCV in auto first, then place the SUCV in auto.
C. Place the "B" Loop Master Hand/Auto station into auto first, place the SUCV to
auto second and the LLCV to auto third.
D. Place both Loop Master Hand/Auto stations into auto first, place the LLCV to auto
second and the SUCV to auto third.
Reasons:
A. The LLBV must be open at this point. The SUCV cannot be placed in
automatic first if the LLBV is open.
B. CORRECT
C. The position of the Loop Hand/Auto stations is not a factor in placing the
control valves back to automatic. The SUCV cannot be placed in automatic
first if the LLBV is open.
D. The position of the Loop Hand/Auto stations is not a factor in placing the
control valves back to automatic.
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: 6
5. 4-14 002/3//0410102007/ G2.2.2/ 3.5/ 3.5/33-[2/31/
Unmodified repeat question from LOI 99-01 program; NRCN
Modified 8-2-00 CMC
BANK; modified sentence structure with comma per LM (NRC) 7/27/01
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
13 1 10410102007 0G2.2.2 ý.5 6.5 h3-[2/3
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points = IBIC IDlA IOIAIBE
B13c Scramble Range: A- R
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: 7
6. 4-14 003/3//0410102003/ 059K4.18/ 2.8/ 3.0/33 [1]/ ICS
Which of the following is a function of the Rapid Feedwater Reduction (RFR) feature of ICS?
A. Reduces both main feedwater loop master hand/auto stations demand to zero.
"/B. Inserts a negative error to the low load and startup control valves.
C. Inserts a rapid closure signal to both main feedwater block valves.
D. Selects main feedwater pumps to delta pressure control.
A. A zero demand is inserted downstream of the loop masters, however, the loop masters are
not driven to zero by RFR.
B. CORRECT: This negative error closes the valves and it will be released at 2.5" above low
level limits, however, this is what RFR does to reduce feedwater.
C. The closure speed of the main block valves is the same, there is no rapid closure capabilities.
D. Delta P control of the pumps is a function of the MBVs position.
NEW 2002 NRC exam KEH 10/4/01
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
13 k410102003 1059K4.18 1.I .o 3 1cs
ANSWERS: Version Answers:
01 23456789 [] Scramble Choices
Points[ 1
IB e ID1A B DABB Co Scramble Range: A -
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: 8
7. 4-25 001/ 4/ / 0720402003/ 072A3.01/ 2.9/3.1/33 [11/ RM
Given the following plant conditions:
100% power
RM-A5 sample pump trips
Rad monitor control panel indicates high flow alarm
Which of the following is the final control complex ventilation lineup?
A. The 17 fans trip; Control room dampers remain in their normal lineup.
B. The 17 fans trip; Control room dampers reposition to their recirculation lineup.
"/C. The 17 fans remain running; Control room dampers remain in their normal lineup.
D. The 17 fans remain running; Control room dampers reposition to their recirculation
lineup.
A. The high flow alarm is from the pump trip, RM-A5 did not actuate any actions.
B. The high flow alarm is from the pump trip, RM-A5 did not actuate any actions.
C. CORRECT: The high flow alarm is from the pump trip, RM-A5 did not actuate any actions.
A. The high flow alarm is from the pump trip, RM-A5 did not actuate any actions.
NEW 2002 NRC exam KEH 10/3/01
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
14 1 10720402003 172A3.01 1.9 .1 3 1 IRM
ANSWERS: Version Answers:
0123456789 E Scramble Choices
Points F--1 0 12D A45 78D
Scramble Range: A - W
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: 9
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 should open as long as RWP-3A, Decay Heat Raw Water Pump, is
running.
I/ "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.
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: 10
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 IRM
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points[II IIKEICIKABCDA Scramble Range: A -
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: II
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: Version Answers:
0 1 2 3 4 5 6 7 8 9 [Scramble Choices
=
Points
D Scramble Range: A - d
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: 12
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 Rod 7-3
does not agree with its Absolute Position Indication (API).
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
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 Import Initial/Re System
13 1 10010102009 1014A2.0 4 13.4 13.9 133"41] zcRo
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 El Scramble Choices
Points =
IDIAIB ICIDl lB IolAD Scramble Range: A- Wd
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. has an increased number of fuel assemblies.
B. ventilation has been secured.
C. 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: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points =
ID1AIB IDIAIB C D A Scramble Range: A - 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 Page: 15
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 2"-8" ramp rate is not in
effect.
D. Below Low Level Limits with RCPs in operation the 2"-8" ramp rate is not in
effect.
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
12 10190502002 135K4.01 3.6 h.8 b3-tz3] I
ANSWERS: Version Answers:
Scramble Choices
Points
SPoints[ i] Z~IKIZ
I IIIB cIAIABI
1B0123456789
Scramble Range: A - 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?
A. AFW pump discharge valve FWV-215.
B. AFW control valves FWV-216/217.
C. AFW isolation valves FWV-222/223.
v/D.
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: Version Answers:
0 1 2 3 4 5 6 7 8 9 [Scramble Choices
Points "- InIAB IlIAIBc
IIA Scramble Range: A - wd
A TT"A lrlk A lr*l lk TT*
Friday, January 18, 2002 @ 06:52 AM I2KKU.SINJX Page: 17
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 RCP-1B RCP-1C RCP-1D
2nd 3rd 2nd 3rd 2nd 3rd 2nd 3rd
Time Stage Stage Stage Stage Stage Stage Stage Stage
0100 1300 700 1400 800 1550 900 1425 725
0400 1325 725 1375 825 1575 925 1425 775
0700 1300 700 1400 800 1550 950 1400 775
1000 1325 725 1400 800 1575 1035 1450 800
1300 1350 725 1400 800 1575 1125 1450 800
Dumpster 3 2 3 2
clicks per
minute at
1300.
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.
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: Version Answers:
0123456789 M Scramble Choices
Points=* PCoinUBtIs ID AIB ICIID Scramble Range: A- N
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
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. Manually depress the alarm acknowledge pushbutton.
B. Automatically will reset once the ultrasonic monitor needle drops back below the
red portion of the meter.
C. Automatically will reset once tailpipe temperature decreases below 150'F.
"/D. Manually reset in Tsat cabinet in the "B" ES 4160V switchgear room.
A. The alarm is locked in until reset in the 4160V SWGR room.
B. No auto reset from ultrasonic, the slide bar alarm setpoint will reflash the alarm.
C. No auto reset from tailpipe temperatures.
D. 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 RO Import. SRO Import Initial/Re System
0 POav
13,4,8 1020302001 Io 02.c .8 3.0o3
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points [4 IDIAIZ Is IAIB IBCA Scramble Range: A - w
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: 20
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, the "A" Waste
Gas Decay Tank.
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
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
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: Version Answers:
0 1 2 3 4 5 6 7 8 9 [Scramble Choices
Points IC I DIAI DI Scramble Range: A - W
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 - T4 & T4A; ROTs N -
T4B & T4BA
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
ANSWERS: Version Answers:
0123456789 M Scramble Choices
Points =* IP nCIDI1AIBICF lW Scramble Range: A- [
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 K/A RO Import. SRO Import Initial/Re System
19 11190302001 JECG2.2.25 12.5 .7 133 [1 ITS
ANSWERS: Version Answers:
0123456 789 E Scramble Choices
Points
Scramble Range: A - 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. Unidentified RCS leakage of 0.4 gpm.
B. Identified RCS leakage of 4.0 gpm.
C. RCP Controlled Bleed off flow of 8.0 gpm.
"vD. Primary to Secondary leakage of 1.4 gpm.
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 E Scramble Choices
Scramble Range: A -
Points[= IDPointsIDAIB CDICIA
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: 25
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?
A. TBP-3 Turbine-generator bearing oil pump.
B. VBIT- 1E Inverter.
C. 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:
0 1 2 3 4 5 6 7 8 9 ED Scramble Choices
Points = ID IA 1B [C ID JA 1B IC ID JA Scramble Range: A- R
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: 26
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:
0123456789 0 Scramble Choices
Points= Pn[IIAIIP DIB Ic IDI
o Scramble Range: A - E
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)?
A. 1. Long cycle clean-up is completed with the Feedwater Booster Pumps.
2. Main Feedwater Pumps are placed on turning gear.
3. The Start-up Feedwater Block Valves are opened.
4. One Main Feedwater Pump is started.
B. 1. Long cycle clean-up is completed with the Feedwater Booster Pumps.
2. Main Feedwater Pumps are placed on turning gear.
3. One Main Feedwater Pump is started.
4. The Start-up Feedwater Block Valves are opened.
C. 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.
,'D. 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.
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: 28
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 Import Initial/Re System
19 1150102004 JG2.1.23 b.g k.o k3-[2/31
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 [ZScrambleChoices
Points= iIDA lB Ic ID IAlB IC ID IA Scramble Range: A - DI
- *r - n a-'
Friday, January 18, 2002 @ 06:52 AM IIKU. ,BNK Page: 29
23. 5-14 001/ 51/1190402001/ 022K3.01/ 2.9/ 3.2/ 33-(1]I Al-505
Given the following plant conditions:
A Large break LOCA has occurred.
RCS temperature is 287 0 F.
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?
A. IEEE-279
"C. Reg Guide 1.97
D. ANSI 3.1
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: Version Answers:
01234567 8 9 E] Scramble Choices
Points[ 1
Ic DIAIB II I
I i Scramble Range: A - W
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: 30
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?
A. Remotely at the electrical switchgear.
B. Locally at the component.
"VC. Remotely at the EFIC cabinets.
D. 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 LE Scramble Choices
Points= ID IALBI
PoitsIC B ICIDI~lk~ Scramble Range: A-
DJ wý
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 Page: 32
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) Import Initial/Re System
I1 15-501 10340402001 1034A4.02 b.5 13.9 111-[2/31 IFH
ANSWERS: Version Answers:
01 23456789 [ Scramble Choices
Points= 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: Version Answers:
0123456 7 8 9 E Scramble Choices
- -ini II
e Points
1BICIDIJA1ICID A1BCIC Scramble Range: A - W
Friday, January 18, 2002 @ 06:52 AM 2K2RO.BNK Page: 34
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 180 0 F.
- 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:
0 1 2 3 4 5 6 7 8 9 FýScrambleChoices
Points = I IAIBI1C ID]A Scramble Range: A- W
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:
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 Import. SRO Import Initial/Re System
16 450402001 39A4.01 ý.9 3 [11 EOP-02
ANSWERS: Version Answers:
456789
ID Scramble Choices
Points= 0D 2I
IC ]IElIZIEIElo Scramble 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 be K/A RO Import. SRO Import Initial/Re System
13 1115050200)6 1074G2.4.21 13.7 7.3
h3 [1] IEOP
ANSWERS: Version Answers:
0123456 78 9 [ Scramble Choices
IBClDIIcl
PointsF71
Scramble Range: A -
w
[A
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 1
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?
A. Effects remain the same over core life.
B. Beginning of core life.
C. 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:
Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective
115 1150402016 035K5.01 .4 3.9 3-[1
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Ivj Scramble G,,uhei
Points= IDIA1BIC ID [B IA DA= Scramble Range: A- d
2kcom.jbnk 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:
Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective 3 33 23 IRX S/U
7 105002001 032AA2.02 .6
ANSWERS: Version Answers: Ti .
0 1 2 3 4 5 6 7 8 9 "jScrambler ,ouwces
1e
Points 1BIcIDAI1B Ic IDABCI Scramble Range: A - wd
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 3
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.
B. 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.
C. Remove the lead shielding; reposition the valve; leave the lead shielding for the
Health Physics technician to replace.
vD. 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 33-1 I29
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points= IDIAIB iclIAIB Scramble Range: A- [
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 4
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. 5240F.
540 0 F.
C. 555 0 F.
D. 5650 F.
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:
0 1 2 3 4 5 6 7 8 9 LX]JScrambleUChoices
Points = IB Ic ID* IB
BCIC Scramble Range: A- Ed
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 5
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:
0 1 2 3 4 5 6 7 8 9 E Scramble Choices
PointsF--* D AB D Scramble Range: A- w
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 6
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?
A. Decrease RCS pressurizer level.
B. Decrease RCS hot leg flow.
",-C. Increase RCS loop pressure.
D. 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:
Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective
13 1
,50502002
( EO3EK3.1 1.8
- .2 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
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 7
7. 4-07 001 / 4//0860402001 / 086A1.01/ 2.9/3.3/33 [2/3]/ FIRE
Given the following plant conditions:
"Afire is in progress on the startup transformer
"ALoss 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 RO Import. SRO Import Initial/Re System
14 10860402001 1086A1.O ,1 .9 3.3 33 [2/3 IFIRE
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 E] Scramble Choices
Points= IB ICIDIAIBIc IDIAIBc Scramble Range: A- [
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 8
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 LABEL INITIAL FINAL
PZR Level RCI-LT1 220 208
RCS Tcold (NR) RC5A-TE I 555 557
PZR Temp RC2-TE1 648 665
RCS Press (NR) RC3A-PT1 2155 2135
Instrument signal failure rates are rapid from the inital value to the final value.
Which instrument would the Smart Auto Signal Selector (SASS) module perform an automatic
TRANSFER?
,/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: Version Answers:
01 23456789 [] Scramble Choices
Points[ffi IBCDA B Scramble Range: A - D
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 9
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 when the
pressure transmitter failed high.
- 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
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 10
9. 4-09 002/ 3,4,7//0160102003/ 027AA1.01 / 4.0/3.9/33-[2/31/01 CYC2
ANSWERS: Version Answers:
W Scramble Choices
P~i÷* * D A B C AD B C D A
on
0123456789
Scramble Range: A - W
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: I I
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. NI-5
"/B. NI-6
C. NI-7
D. 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
Points= Poins A Is Ic IOIA I CI
[I Scramble Range: A - [
2k2com.bnk Page: 12
Friday, January 18, 2002 @ 06:51 AM
11. 4-10 002/3//1150402016/ 002K5.10/ 3.6/ 4.1/33-[2/31/
The initial power escalation following a refueling outage is being performed. The reactor
power level is stabilized to perform testing. The following indications are available to the
operator at the control board:
NI-5 26.0%
NI-6 29.0%
NI-7 26.0%
NI-S 29.0%
T-hot Loop A 588.50 F
T-hot Loop B 588.00 F
T-cold Loop. A 570.00 F
T-cold Loop IB 569.50 F
Tave 579.00 F
Which of the following is an accurate estimate of the thermal power level of the reactor at this
point?
A. 372 MWt
B. 661 MWt
C. 738 MWt
,D. 1070 MWt
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 13
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 RO Import. SRO Import Initial/Re System
1002K5.1 S 13.6 4.1 3- 2/3
13 11150402016
Version Answers:
ANSWERS:
0 1 2 3 4 5 6 7 8 9 [Scramble Choices
1ge Points= ID1AB B ICIDI1A Scramble Range: A - W
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 14
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%.
-A.
NI-3 will indicate less than 10-10amps and power is restricted to less than 5%.
B.
NI-3 will indicate greater than 10-10amps and power is restricted to less than% x
C.
10-9amps
D. NI-3 will indicate less than 10-10amps and power is restricted to less than 1 x
10-9 amps
Reasons:
A. 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
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 15
12. 4-10 003/5,6/5-01/1150402016/ 033AK3.01 / 3.2/3.6/ 33-[2/31/
KEY WORDS:
Lesson Pla Task Numbe K/A RO Impc rt. SRO Import Initial/Re System
Objective
15,6 5-01 1150402016 033AK3.01 13.2 13.6 b3-[2/3] II
ANSWERS: Version Answeirs:
Sige ]Points[
Pt W]IAIBICIDEI
I012345 6 7 8 9 [ Scramble Choices
]I-IZlI Scramble Range: A - W
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk 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 Task Numbe K/A RO Import. SRO Import Initial/Re System
k.1 4.4 r3
[11 IRPS
14 010502002 54AK3.01
ANSWERS: Version Answers:
I 1 Scramble Choices
0123456789
S1ge Points 7]I[Zlll~eIPDIAIB le 5crSo
amble Range: A - Ed
Friday, January 18, 2002 @ 06:51 AM 2keom.bnk Page: 17
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?
A. Takes both channels out of "MANUAL BYPASS" when the second RPS channel is
place in "MANUAL BYPASS".
B. The first RPS channel in "MANUAL BYPASS" will trip the second RPS channels
Reactor Trip Module, if that channel is placed in "MANUAL BYPASS".
",/C. The first RPS channel in "MANUAL BYPASS" prevents placing any additional
channels in "MANUAL BYPASS".
D. 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[= Pointsl l ID B
A IC ID Scramble Range: A- [A
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 18
15. 4-12 004/4//0120402007/045K1.18/3.6/3.7/33 [2/31/ RPS
The following plant conditions exist:
PARAMETER DATA
Rx power 75%
Linear amp power range top 35% bottom 40%
5970
RCS Thot
RCS pressure 2155#
RCS flow 9 x 107 lbm/hr
RB pressure +0.5 psig
RCP monitor A 8,300 kw
B 7,100 kw
C 9,500 kw
D 0 kw
Turbine auto-stop oil 99 psig
Both MFW control oil 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)
A. RB pressure 3.5 psig
B. RCS pressure 1911 psig
C. RCP monitor B 2152 kw
,/D. Turbine auto-stop oil 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.
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 19
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: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points i
DAB Scramble Range: A - W1
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 20
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?
V'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:
Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective 13.4 h.6 133 2/31 AMSAC
4,5 0450402001 04AK3.2
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ,LXJcrambleG oces P
IAIBCICD [AIl I Scramble Range: A -
Points
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 21
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- 1C 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:
0 1 2 3 4 5 6 7 8 9 wI'ScrarnbleChoices
Points = 1BIIILC ID AB C Scramble Range: A - Wj
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 22
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:
A. HPI initiates on low RCS pressure due to the RCS leak.
The HPI "BISTABLE TRIPPED" lights are BLUE.
C. LPI initiates on low RCS presssure due to the RCS leak.
D. 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:
01 23456789 E Scramble Choices
Points =
[3 IC1131A 1B ICIDIA
I IC
IB Scramble Range: A - d
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 23
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:
0 1 2 3 4 5 6 7 8 9 LjScrambleChoices
Points = IDAI B IC IDIJA Scramble Range: A- Wd
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?
A. green -- off -- amber
B. green -- white -- amber
'/C. amber -- off -- green
D. 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 oi30502001 1006A3.0 '3 14.1 14. b3-[l1
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points Iii
S]
ICIDAIBIC ID11IB ICIDI Scramble Range: A - D
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk 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 K/A RO Import. SRO Import Initial/Re System
13 1 0410402001 1003AK1.13 .2 13.6 3 2/3 ICS
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 W1 Scramble Choices
Points E*]
IDLIIIDABCDA Scramble Range: A - 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, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 27
22. 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 Initial/Re System
b.2 2
33-[231
13,5 0410402013 059K1.07 b.2
ANSWERS: Version Answers:
bZqo ]Points[ II IAIBC oAB
0123456789
AC lII Sc
Scramble Choices
ramble Range: A - Wd
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 28
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- 1D 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.
"vC. 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:
0 1 2 3 4 5 6 7 8 9 VLflcrambleunoices
Points=I] tICDAI ICIlDABI Scramble Range: A- Wd
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 29
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?
A. Must be started locally.
B. Must be started at the Remote Shutdown Panel.
C. Should have started when the transfer switches transferred control to the Remote
Shutdown Panel.
"vO. 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:
0 1 2 3 4 5 6 7 8 9 WScramble Choices
1e
Points=E 1D1A1BIC D lA IC IDA Scramble Range: A - d
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 30
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 K/A RO Import. SRO Import Initial/Re System
12 11150502002
IE03EK1 .2 13.8 k.0 h3 [2/3] SPFDS
ANSWERS: Version Answers:
Scramble Choices
0 1 2 3 4 5 6 7 8 9
Points[ I 1AIB cIC1)IAIB cIC1)IAI1B I Scr amble Range: A - W
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 31
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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; RM-L I,
letdown monitor, is in warning.
C. Power decreased rapidly 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 IRM
ANSWES. Version Answers:
0 1 2 3 4 5 6 7 8 9 E Scramble Choices
1e
Points FB c DIoAIB lCIDIAl1le Scramble Range: A- d
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 32
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 IRM
AhNSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 EN Scramble Choices
PointsF _5]
IB CIDIAJIBIcDIABIC I Scramble Range: A- R
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 33
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]
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 34
28. 4-25 003/3//0070402004/ 068K6.10/2.5/2.9/ 33-[2/3]/
ANSWERS: Version An swers:
4 5 6 7 8 9 E Scramble Choices
Points ID0123
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 1K Page: 36
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 0 Import. SRO Import Initial/Re System
101CYC2
14 11190101031 060AA1. .02 2.9 b.1 133-[1]
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
PointsF 1 IC Scramble Range: A - w
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 37
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- 1A/l B (RB purge exhaust dampers)
,/D. AHV- IA/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- IA/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 E Scramble Choices
ige Points[=
I1IA1B ICDIAIBICInlAI Scramble Range: A - Wý
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 38
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?
A. Service water flow switch in parallel with both CRD breakers closing coils.
"/B. Service water flow switch in series with each CRD breakers closing coil.
C. Service water pump(s) breaker contact(s) in parallel with both CRD breakers closing
coils.
D. 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 o
I001K1.09 .8 13.1 3 [2/3] ORD
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 LlScramble Choices
Points = IB DIA IDIAIB IC I Scramble Range: A- [
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 TI"
ask Numbe K/A RO Import. SRO Import Initial/Re System
ICRD
14 0450402001 1007EK2.02 13.5 F.5 133 [2/31
ANSWERS: Version Answers:
01 23456 7 89 N Scramble Choices
ine Points [ 1
1B CID1A1ICD 1AI I I
Scramble Range: A - wý
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 40
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 not moving.
D. CORRECT: the zone reference would show all the other rods at the 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 LM Scramble Choices
Points= IA1B ICMD
Pont IAlB ICIDJA I Scramble Range: A -
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 Page: 42
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 Task Numbe K/A RO Import. SRO Import Initial/Re System
151 10010402019 100G2.1.32 13.4 h.8 -h3-[2/31 I
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points 1IDIE JIIoIIIABcDA Scramble Range: A- Wd
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 43
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
Points=[ Ic 1
DAIB I ID A I1
IC ID I Scramble Range: A - FD]
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 44
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. Only "A" side BWST suction valve (MUV-73) will receive an open signal.
B. Only "B" side BWST suction valve (MUV-58) will receive an open signal.
C. Both "A" and "B" side BWST suction valves (MUV-73/58) will receive an open
signal.
D. 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
ANSWERS: Version Answers:
0123456789 Z Scramble Choices
Points=E* Pn B ICDA B Scramble Range: A - W
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 K/A RO Import. SRO Import Initial/Re System
13,4,7 1 11150402016 157AA1.05 1.2 13.4 h3-[l IMUP
ANSWERS: Version Answers:
0123456 789 [ Scramble Choices
inge JPoints =
A IScramble Range: A - Wd
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 46
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 [008K1.02 3.3/3.4]
ROTs 0 - T8 & T8S; LOIL-T8AR/T8AS
KEY WORDS:
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
Points= Pn AABCD A Scramble Range: A - w
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 47
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- 1A and SWP- IB auto start and SWP- 1C 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:
01 23456789 [E Scramble Choices
Points IFICDTATC II DI [D Jk Scramble Range: A - W
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 48
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 start and
the flume water level is almost empty.
Which of the following actions, and applicable reasons for these actions, should be performed?
A. No action required, RWP-1 and RWP-2B are not affected.
B. Trip the reactor and initiate EFIC due to the loss of CW cooling to the condenser.
C. 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
PointsF-1] ID1A113eICID A1B IC
Pn l LDJAI
Scramble Range: A - d
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
KEY WORDS:
Obje4ctive Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
4,5,7 1 11150402011 059AK2".01 12.7 k.8 k3 [2/3]
IRWL
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points LIII IIAiIDA1 A Scramble Range: A - d
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 50
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:
0 1 2 3 4 5 6 7 8 9 LE Scramble Choices
Points =
IDA1BICIDIAICIDIJAI Scramble Range: A - d
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.
D. The temperature of the RB atmosphere.
Reasons:
A. This parameter is limited to reduce the amount of post-LOCA hydrogen
and does not affect iodine in the RB atmosphere.
B. 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 bjective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
13 ý-30 10260502004 0272.1.28 .2 13.3 133- [1 I
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points IC Scramble Range: A - Wd
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 52
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- 1A 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
Points= PA 1tiBC ID IA13 1 Scramble Range: A- d
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 53
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: Version Answers:
0123456789 E] Scramble Choices
Points= Points ID JA Scramble Range: A - d
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 64 0 F
- 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 65 0F
- 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 0 F 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 Page: 55
46. 4-63 003/ 5,7/ / 0880102014/ G2.3.9/2.5/3.4/ 33-[2/3]/
Reasons:
A. 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.
B. 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.
C. 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.
D. 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
15,7
Lesson Pla
1
Task Numbe
10880102014
K/A
0G2.3.9
RO Import.
.5
SRO Import
13.4
Initial/Re
33-[2/3]
w
System
ANSWERS: Version Answers:
7 8C 9
0C 1D1 2 3s* 4 I5 6AF Scn Scramble Choices
SPoints=* Scr,
amble Range: A - W
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 56
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:
0123456789 N Scramble Choices
Points
IAlB ICIDiJA JAJjB Scramble Range: A- N
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?
A. A signal that compares existing CD pump speed with FW flow and hotwell level.
B. A signal that compares existing CD pump speed with FW flow and deaerator level.
C. A signal that compares existing CD flow with FW flow and hotwell level.
,D. A signal that compares existing CD flow with FW flow and deaerator level.
Reasons:
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 tern
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 - d
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 58
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.
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
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 H Scramble Choices
Points [D IB IDJIA cDA C Scramble Range: A - d
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 59
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?
A. EDG-lA is operating at 61 Hz and 4200 volts.
B. EDG-lB is running with its output breaker (3210) closed.
"/C. The under-voltage relays are tripped and the normal feeder breaker is still closed.
D. 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 E Scramble Choices
Points= ICI l 1B ICIDAoIA IcC DI Scramble Range: A -
Friday, January 18, 2002 @ 06:51 AM om.bnk
eK2C Page: 60
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. ESE,-L DU A
EPUSF I t.R
0
Startup 3203 3204
FtECK CL OsYN3
BEST 3205 3206 SCTLA TIED 31tE 0
Unit Aux 3207 3208
0
EDG 3209 3210
OPT 3211 3212
A.CT1J ATED :Y*5
0
EtECPC CL Ol5[N'D
ACTUA TED 32L7] a
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.
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 61
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
Points[= IcID1I BCIDIoIA 113
Pn DII Scramble Range: A - W
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 62
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:
0123456789 [I Scramble Choices
Points IDIA I I IA
SICBI C1B I Scramble Range: A- d
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 63
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?
A. AP-58 1, Loss of NNI-X, should be entered.
B. AP-582, Loss of NNI-Y, should be entered.
AP-430, Loss of Control Room Alarms, should be entered.
D. 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
Points [= PnIDABC D Scramble Range: A- Wd
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 64
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
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 65
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 1mport. SRO Import Initial/Re System
14, 7, 9 780402006 1055K3.01 ý.5 12.7 133-[2/3] I
ANSWERS: Version Ansswers:
01 23' 4 5 6 7 8 9 [ Scramble Choices
Points= ]I IPIDins1 BC Scramble Range: A - d
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 66
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. If reactor power was less than 30% then this would be the correct action
to take, based on vacuum only.
B. 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 main
turbine to be tripped immediately.
D. 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
Friday, January 18, 2002 @ 06:51 AM 2kWcom.bnk Page: 67
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 10450402005 1051AA2.02 3.9 4' Ii'1-[1
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points L IC1fA1IIDAI Scramble Range: A - 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 RO Import. SRO Import Initial/Re System
16,8 I550402001 .4.48 13.5 13.8 111
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 WScramble Choices
Points
IC EIIA1B ICI1 IAIB IID Scramble Range: A- [
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 69
57. 5-01 001/ 4/ / 1190302001 / 076AA2.02/ 2.8/ 3.4/11 [2/3]/ RCS ACT
Given the following plant conditions:
0600 Plant at 100% power
0700 Plant at 80% power
1030 Chemistry sampled the RCS
1230 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?
A. Reduce RCS activity to less than the Tech Spec limit immediately or be in MODE 3
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
B. Reduce RCS activity to less than the Tech Spec limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in MODE
3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Reduce RCS activity to less than the Tech Spec limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in
MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
D. 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is allowed
C. CORRECT; See T.S. 3.4.15 condition A and B 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or MODE 3 W/I 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
D. 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: Version Answers:
01 23456 7 8 9 E Scramble Choices
Points IC 1D 1A 1B IC 11 1ATBC Scramble Range: A - d
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 70
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 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: Version Answers:
[Sn1e 0123456789 E Scramble Choices
Points [= J IDA15 ICID1A
IPIAiB IC Scramble Range: A - N
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 71
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 579 0 F
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
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 E Scramble Choices
Points rD AIBIcID J nA
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 1150502003
1 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 2kcom.bnk Page: 73
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. The RCS cooldown rate would be > 50°F/hr.
D. 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
1e
Points=[ Point
IDJ1AACJABC Scramble Range: A- R
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 74
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 E Scramble Choices
Points=[ [ IA11 ICIDJA
PoitsIIIDV lB ICIDJA I Scramble Range: A - W
,"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: Version Answers:
0123456 7 8 9 M Scramble Choices
Points[*]
[ [ BC D Scramble Range: A- Wd
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 76
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?
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 Page: 77
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 Task Numbe K/A RO Import. SRO Import Initial/Re System
17 I-56 10080402012 t26AA2.01 ý.9 13.5 b3-[2/3] I
ANSWERS: Version Answers:
[Snge ] 0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points DB A BC Scramble Range: A- d
Friday, January 18, 2002 @ 06:51 AM ZK2com.bnK Page: 78
65. 5-69 001/6/ / 1150402010/ EPP2.4.25/ 2.9/3.4/33 [1]/ FIRE
Given the following plant conditions:
A fire in the Intermediate Building
Step 3.3 of AP-880 States "Ensure fans in affected areas are secured."
The operator secures AHF-29 A/B and AHF-24 A/B
Which of the following is the reason for this action?
A. Prevent the spread of fire to radiological areas.
B. Prevent the spread of fire to the turbine building.
C. Ensure sprinkler system work effectively.
vD. Ensure fire dampers operate properly.
A. These area are identified in AP-880 but it is not the reason for securing the fans.
B. The fans will not prevent the spread to the turbine building.
C. The sprinkler systems will not be affected by the fans.
D. CORRECT: NOTE in AP-880 states securing the fans is to ensure proper operation of fire
NEW 2002 NRC exam KEH 10/2/01
KEY WORDS:
bjective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
16 1 11150402010 JEPP2.4.25 .9 13.4 133 [] IFIRE
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Z Scramble Choices
Points= DAB Scramble Range: A - Id
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 79
66. 5-84 001 / 6/ / 1150402012/ 065AK3.08/ 3.7/3.9/33 [2/31/IA
Given the following plant conditions:
RCS is at 140'F.
"A" DHR loop is in service.
A total loss of Instrument Air occurs.
Which of the following will be the flow capabilities (position) of the DHR cooler valves?
DCV-17 (A DH COOLER BYPASS CONTROL)
DCV- 177 (A DH COOLER OUTLET CONTROL)
A. DCV-17 full flow.
DCV-177 minimum flow.
B. DCV-17 full flow.
DCV-177 full flow.
C. DCV-17 minimum flow.
DCV-177 minimum flow.
- /D. DCV-17 minimum flow.
DCV-177 full flow.
A/B/C. The valve will fail to the ES position of no air for control, which is with the bypass
closed and the outlet open for maximum cooling.
D. CORRECT: The bypass flow limited, and the outlet full flow for max cooling.
These valves have throttle positions, therefore they are NOT just closed or open.
NEW 2002 NRC KEH 8/9/01 No references.
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
16 1 11150402012 1065AK3.08 13.7 13.9 k3 [2/3] IIA
ANSWERS: Version Answers:
0123456789 MJ Scramble Choices
Points=* IDIABICDIAI I ID]AI Scramble Range: A - R
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 80
67. 5-95 001/5/1/ 0040502007/ 011 EK2.02/ 2.6/ 2.7/ 33 [2/3]/ EOP-8
In EOP-8, when is HPI flow terminated if LPI flow is > 1400 gpm in any line per follow-up
step 3.6 (large break path) ?
A. When ECCS suction is transferred to the RB sump.
B. When CR1 isolation valves are closed.
C. When RB spray is secured.
vD. When TSC provides direction.
A. This is based on adequate suction to ECCS pumps.
B. This isolation is to prevent excessive N2 in RCS.
C. This stops RB spray based on RB conditions.
D. CORRECT: Large break requires flow until direction from TSC step 3.114.
M113: NRC exam 2002 KEH 9/25/01
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
151 0040502007 1011 EK2.02 .6 .7 33 2/3
IEoP-8
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points DABI DA Scramble Range: A- U
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 81
68. 5-95 002/3// 1150502007/ E082.1.28/ 3.2/3.3/ 33-1 ]/
A LOCA cooldown is being accomplished in accordance with the guidance of EOP-08, LOCA
Cooldown.
- The leak rate is approximately 300 gpm
- Normal cooldown rates are being used.
- All 4 RCPs are running.
The crew reaches a step in EOP-8 which states "IF 4 RCPs are running, THEN stop RCP- ID".
Which of the following statements describes the reason RCP- ID is specified in this step?
A. RCP-1D is specified to reduce RCS leakage if the leak is located on the Make-up
and Purification system letdown line which taps off of "D"cold leg.
B. RCP-1D is specified because it produces the greatest flow of the 4 RCPs. Stopping
this pump provides the maximum margin for core lift concerns.
VC. RCP-1D is specified because it is in the opposite loop from RCP-IB, which
provides pressurizer spray. Later guidance will reduce RCPs to a 2/0 combination.
D. RCP-lD is specified because it provides the greatest heat input to the RCS.
Stopping this pump will provide maximum heat reduction while maintaining 3
pumps in operation.
Reasons:
A. Letdown does tap off of the D cold leg but this was not the reason for
selecting RCP-lD to be shutdown.
B. The reason for reducing to 3 RCPs is core lift concerns but the selection
of RCP-1D was not random. A pump in the loop opposite RCP-lB is
selected to ensure maximum spray capability is maintained during RCP
operation. Spray is required to avoid delays in RCS depressurization
and cooldown.
C. Correct Answer. A pump in the loop opposite RCP- lB is selected to
ensure maximum spray capability is maintained during RCP operation.
Spray is required to avoid delays in RCS depressurization and cooldown.
D. The heat input from RCP-lD is not markedly different from the other
RCPs. This was not the basis of choosing RCP- I D.
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 82
68. 5-95 002/3//1150502007/ E082.1.28/ 3.2/ 3.3/33-[1]/
New question written for Sept. 2000 RO and SRO exam. (2-27-00 CMC)
REPEAT
KEY WORDS:
0 bjective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
13 1 11150502007 IE082.1.28 13.2 13.3 133-[1 1
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points C IDA* 1B C IDIA lB I IDI Scramble Range: A - d
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 83
69. 5-96 001/ 6//0120402006/ 029EK1.03/ 3.6/3.8/33 [2/31/ EOP-2
Given the following plant conditions:
An ATWAS has occurred.
Performing EOP-2 Immediate Actions.
NI's DO NOT indicate the Reactor Shutdown.
EOP-2 contingency actions ensure which of the following:
A. Core cooling is maintained.
,/B. Addition of negative reactivity.
C. Main steam to the turbine is terminated.
D. Reactivity worth of the inserted rods is maximized.
A. This requires emergency boration, the core is cooled.
B. CORRECT: Emergency boration is directed and that ensure negative reactivity to shutdown
the reactor and this is a hold step until it is accomplished.
C. Steam will not be secured until the reactor is shutdown.
D. The rods that have inserted are not going to be any more effective, more negative reactivity
is necessary to shutdown the reactor.
NEW NRC 2002 KEH 9/25/01
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
16 1 10120402006 1029EK1.03 13.6 13.8 133 2/31 IEOP-2
ANSWERS: Version Answers:
0123456789 SScramble Choices
Points=[ PBkC IA BICI IAlB Ic I Scramble Range: A - N
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 84
70. GT-001 001/17/ GET-001/ N/A/067AK1.01/2.9/3.9/33 [1]/ FIRE
Which of the following areas contain material which would be limited to a Class "B" fire?
A. Document control storage vault.
B. "A" ES 4160V switch gear room.
"C. 95'TB at lube oil purifier skid.
D. I&C calibration lab in maintenance facility.
A. Paper Class "A".
B. Electical equipment Class "C".
C. CORRECT: Oil Class "B"
D. No fire hazard for Class "B"
NEW NRC exam 2002 KEH 9/25/01
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
117 GET-O0 IN/A 07AK.O1 .9 b.9 b3[1 IFIRE
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 E Scramble Choices
Points =I
ID Scramble Range: A- D
aosimetry.
B. Dose rate is less than 5 mr/hr at 30 cm.
C. Dose rate is less than 100 mr/hr at 30 cm.
D. Dose rate is less than 1000 mr/hr at 30 cm.