ML020510576
| ML020510576 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/06/2002 |
| From: | Operator Licensing and Human Performance Branch |
| To: | |
| References | |
| 50-302/02301 | |
| Download: ML020510576 (126) | |
See also: IR 05000302/2002301
Text
Draft Submittal
(Pink Paper)
Senior Reactor Operator Written Exam
CRYSTAL RIVER EXAM
50-302/2002-301
JAN. 28 - FEB. 6, 2002
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: I
1. 3-03 001/10//1150401013/ 061K5.01/136/3.9/33 []/ NC
Given the following plant conditions:
Reactor trip has occurred.
Natural Circulation cooldown in progress with Emergency Feedwater.
During the cooldown, a transition is made from EFW to MFW.
Which of the following identifies the resulting core delta T (Thot minus Tcold) following this
transition?
A. Decreases because OTSG saturation temperature decreases.
B. Decreases because natural circulation flow in the RCS decreases due to a higher
thermal center with MFW.
"VC. Increases because natural circulation flow in the RCS decreases due to a lower
thermal center with MFW.
D. Remains the same because of the hotter water and lower thermal center with MFW
A. This only affects the OTSG Tcold.
B. The thermal center is lower with MFW.
C. CORRECT: Lower thermal center less driving head lower flow therefore higher delta T
D. With lower flow and lower center delta T has to change.
NEW 2002 NRC EXAM KEH (INPO BANK) 8/28/01
KEY WORDS:
Objective Lesson Pla TaskNumbe K/A RO Import. SRO Import Initial/Re System
110 1 1150401013 061K5.01 b.6 .9 3 1 INC
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points =* Points II IDABCD Scramble Range: A -
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 2
2. 3-24 001/ 3/ /1150401013/ 038EA2.01/ 4.1/ 4.7/ 33 11/ SGTR
Which of the following identify when the Tube Rupture Alternate Control Criteria (TRACC)
limits apply?
A. Emergency cooldown limits cannot reduce or maintain OTSG levels.
B. An uncontrolled release via a MSSV is in progress.
C. Limits identified in 10 CFR 100 for unrestricted areas are exceeded.
vD. Unable to fill the RB sump with adequate inventory for recirculation.
A, Emergency C/D limits are not allowed to maintain levels.
B. A stuck MSSV is not a critieria for TRACC
C. Dose limits for even the design basis transient should not even reach the I0 CFR 100 limits.
D. CORRECT: This requires enough inventory in the BWST to have recirc cooling for the
RCS,
NEW 2002 NRC EXAM KEH 8/28/01
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
13 1150401013 138EA2.01 4.1 h.7 b3 1)
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 S Scramble Choices
Points=
I] 1BI D A Scramble Range: A- Wd
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 3
3. 4-12 001/ 5//0120402004/ 029EA2.07/ 4.2/ 4,3/44-[2/3J/ ATWAS
Given the following plant conditions:
100% power
The following events occur:
Both MFW pumps trip
The following alarms are actuated:
EFW actuated H-6-3
DSS channel trip J-l-I
Main turbine trip 0-3-1
AMSAC trip 0-5-1
Control rod groups 5, 6, and 7 rods indicate fully inserted.
NO OPERATOR ACTIONS HAVE OCCURRED!
Which of the following describes the status of the CRD Diamond panel trip confirm light, and
the breaker trip lights on the RPS cabinets?
A. Trip confirm : LIT
Breaker trip lights : DIM
B. Trip confirm: OFF
Breaker trip lights : BRIGHT
C. Trip confirm : LIT
Breaker trip lights : BRIGHT
vD. Trip confirm: OFF
Breaker trip lights : DIM
A. RPS failed, no trip confirm because CRD breakers did not open, DSS tripped the groups
5,6,7 rods. NO operator actions means no manual trip
B. RPS failed, no trip confirm because CRD breakers did not open, DSS tripped the groups
5,6,7 rods. NO operator actions means no manual trip
C. RPS failed, no trip confirm because CRD breakers did not open, DSS tripped the groups
5,6,7 rods. NO operator actions means no manual trip
D. CORRECT: RPS failed therefore no breakers tripped and no trip confirm, DSS tripped the
rods however, the reactor did not trip from RPS.
2K2SRO.BNK Page: 4
Friday, January 18, 2002 @ 06:52 AM
3. 4-12 001 / 5//0120402004/ 029EA2.07/ 4.2/4.3/44-[2/31/ ATWAS
NEW NRC 2002 exam KEH 10/16/01
KEY WORDS: System
K/A RO Import. SRO Import Initial/Re
Objective Lesson Pla Task Numbe
I .2 .3 4-2/3 TWAS
15 10120402004 029EA2.07
Version Answers:
ANSWERS: Scramble Choices
0 1 2 3 4 5 6 7 8 9
[DABc l Scramble Range: A -
Points=
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 5
4. 4-13 001/21/1 150401013/ 013A2.05/ 3.7/ 4.2/ 44-[1]/ ES
Given the following plant conditions:
MUP-IB/C are ES selected
ES has actuated both HPI pumps are running
MUP- 1C has no DC control power
Which of the following describes the MUP indicating lights on the main control board for these
conditions?
A. ES selection light "ON"
Green breaker light "ON"
Red breaker light "ON"
B. ES selection light "ON"
Green breaker light "ON"
Red breaker light "OFF"
Green breaker light "OFF"
Red breaker light "OFF"
D. ES selection light "OFF"
Green breaker light "OFF"
Red breaker light "OFF"
A. No control power the breaker lights are both OFF.
B. No control power the breaker lights are both OFF.
C. CORRECT: the ES light remains lit and with no control power the breaker lights are both
OFF.
D. The ES selection light remains lit, it is supplied from the ES DC power, no control power
the breaker lights are both OFF.
The ES light is fed from VBDP-4 (24V AC); The breaker control power is from DPDP-5B
(125V DC). See electrical drawing B-208-041 MU-04.
NEW 2002 NRC exam KEH 11/06/01
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 6
4. 4-13 001/ 2/ / 1150401013/ 013A2.05/ 3.7/4.2/44-[11/ ES
KEY WORDS:
K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla Task Numbe
11150401013 j1:3A2.05 .7
hES 1
42 -14i
12
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Sin Points c I IAB CDABcD Scramble Range: A- W
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 7
5. 4-29 001/ 6//1150402016/ 033A2.03/ 3.1/ 3.5/ 44-[1]/ SF
Which of the following design features of the Spent Fuel Cooling system minimizes the
probability of uncovering spent fuel?
A. Auto makeup from demain water system.
vB. Spent fuel cooling piping arrangement.
C. Spent fuel cooling auto isolation on ITS low level alarm.
D. Auto makeup from BWST.
A. Make up capability exist but it is not automatic for loss of level.
B. CORRECT: The piping arrangement is where the suction is 4 feet from the top of the pool,
so any leaks in the system will not uncover the spent fuel.
C. The low level alarm does not isolate the SFP cooling system.
D. No automatic makeup capabilities from the BWST.
NEW 2002 NRC exam KEH 10/16/01
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
16 1150402016 33A2.03 .1 .5 1 SF
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Ej Scramble Choices
Points=
c lABI IScramble Range: A-
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 8
6. 4-54 001/ 5// 0050102006/ COCG2.1.32/ 3.4/3.8/44-[2/3]/ DH/MUP
Given the following plant conditions:
MODE 5,
T *lncore is 142 'F
PZR level is 100" with a N2 bubble
RCS pressure is 45#
DHP- 1A is running with a flow rate of 3000 gpm
DHHE- lA outlet temperature is 141 F
OTSG "A" level is 590" full range with a N2 blanket
OTSG "B" level is 590" full range and on recirculation for today
All MUJ/HPI pumps are RED tagged
All HPI injection valves are CAUTION tagged with power OFF on the MCB
Purification flow exists via 1 demin and 2 post filters with a flow rate of 220 gpm
Which of the following basis, identifies a limit and precaution that is being exceeded given the
situation above?
A. Low Temperature Overpressure Protection.
B. Prevent exceeding the maximum design of components.
"/C. Protect anion resin from thermal degradation.
D. Prevent lifting the MU system relief valves.
A. LTOP is not a concern with the HPI pumps tagged out.
B. MUP demins and filters are within their design, the max is 225.
C. CORRECT, the Decay Heat Cooler outlet is above the high temperature limit for the demin
of 135 0 F.
D. The RCS pressure is below 105# at 45#.
OP-404 L&P 3.2.8 outlet temp of 135°F.
BANK 2002 NRC exam KEH 10/20/01
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
15 1 10050102006 GIOCG2.1.32 3.4 ,4-[2/3] IDH/MUP
- W T All * lr*b *. lrlb i Tlr T
Friday, January 18, 2002 @ 06:52 AM 2K,2SJU.BI1N Page: 9
6. 4-54001/5//0050102006/COCG2.1.32/ 3.4/3.8/44-[2/3]/DH/MUP
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points[I IDIAIIIDJBCD Scramble Range: A- w
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 10
7. 4-59 001/5,6,9/ / 1190101019/ RACG2.3.6/ 2.1/3.1/ 44-[1]/ LIQ REL
The SSO/CRS must sign all radioactive liquid release permits prior to the initiation of the
release.
What is the purpose of the SSO/CRS signature?
V'A. It serves to acknowledge and confirm the approval to complete the release.
B. It serves to acknowledge and confirm the appropriate liquid radiation monitor is
operating properly.
C. It acknowledges and confirms the estimated volume of fluid to be released.
D. It acknowledges and confirms the estimated amount of radioactivity to be released
to the environment.
Reasons:
A. CORRECT: This documents management approval for the release.
B. This is done after the signature.
C. Volume of the release is determined by the size of the tank.
D. The signature acknowledges only the completion of the chemistry portion of the
permit not the amount of reactivity release.
OPSA1.BNK 2002 NRC exam KEH 10/13/01
OP-407A Section 4.3; 1-11
BANK; ROT 5-48 #18; NRC 6-97; ROTs M - 5B; NRCM
KEY WORDS:
Objec tive Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
I 11190101019 IRACG2.3.6 .i
Version Answers:
.1
ANSWERS:
0 1 2 3 4 5 6 7 8 9 <Scramble Choices
Points =l ID1AIBs
BIA1BIC Scramble Range: A- w
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: I11
8. 4-60 001/ 3//0020402013/ 01 0K4.03/ 3.8/4.1/ 33 [1]/ PORV
Which of the following indications identify the PORV open in response to a valid RCS
pressure indication?
A. 2475 psig; Pressurizer level lowering.
,-B. 2465 psig; Ultrasonic needle in red area of meter.
C. 2475 psig; Red indication light on panel lit.
D. 2465 psig; Tail pipe temperature of 110°F.
A. PZR level lowering does not prove the PORV is open.
B. CORRECT: The Ultrasonic meter identifies flow from the PORV.
C. The light can be lit and the PORV not open.
D. Tail pipe temperature would be much higher than 110°F.
NEW 2002 NRC exam KEH 10/3/01
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
3 020402013 010K4.03 3.8 k.1 h3 [11 IPORV
ANSWERS: Version Answers:
0123456789 W Scramble Choices
PointsF-1 PBoitD IAIB c D IA1B ICI Scramble Range: A - [
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 12
9. 4-61 001 / 9//1190101020/G2.3.8/2.3/3.2/55-[2/3]/
The following conditions exist:
- Preparations are underway to release WDT-lB, "B" Waste Gas Decay Tank
- RM-A 11 has failed low.
- All other radiation monitors are functional.
Under what conditions may the release take place?
"vA. Two independent samples of WDT-1B are analyzed and two qualified persons
independently verify the release rate calculations and discharge valve lineup.
B. A continuous sample of WDT-1B is analyzed and two qualified persons
independently verify the release rate calculations and suction valve lineup.
C. At least two grab samples of WDT-1B are analyzed and two qualified persons
independently verify the release rate calculations and suction valve lineup.
D. Samples are taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed while WDT-1B is being released and
two qualified persons independently verify the release rate calculations and
discharge valve lineup.
Reasons:
A. Correct, the release may be initiated, if RM-A2 is operable (stem) and at least
two independent samples of the tank's contents are analyzed; two qualified
persons independently verify the release rate calculations, and two qualified
persons independently verify the discharge valve lineup.
B. and C. The tank contents must have at least two independent samples
analyzed and two qualified persons independently verify the discharge valve
lineup.
D. The tank contents must have at least two independent samples analyzed.
Provide ODCM; New question written for Sept 2000 SRO exam. (4-6-2000 mg)
REPEAT
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
19 1 11190101020 G2.3.8 k.3 13.2 155-[2/31 1
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 13
9. 4-61 001/ 9//1190101020/ G2.3.8/ 2.3/3.2/ 55-[2/3]/
ANSWERS: Version Answe rs:
012345
0 6 7 8 9 Z Scramble Choices
PointsL j IA B IC ID IAI rScramble Range: A- W
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 14
10. 4-64 001/ 7,9/1 0630402001/ 058AA2.03/ 3.5/ 3.9/ 44-[2/31/ DC DIST
Given the following plant conditions:
100% power
DC control power is lost to the 6900V Reactor Auxiliary Bus 3A.
One minute later a loss of offsite power occurs.
Which of the following describes the response of the RCPs if AC power is restored to the
6900V Reactor Auxiliary Bus 3A prior to the restoration of its DC control power?
"/A. RCPs "A" and "C" will start because the RCP breakers are closed.
B. RCPs "A" and "C" will remain off because the RCP breakers will trip on a loss of
DC control power.
C. RCPs "A" and "B" will start because the RCP breakers are closed.
D. RCPs "A" and "B" will remain off because the RCP breakers will trip on a loss of
DC control power.
"A"
A. CORRECT: THe Breakers will remain closed and will re-energize with the bus for the
& "C" RCPs (Bus 3A pumps)
B. The breaker do not trip with no control power.
C. Wrong combination of pumps
D. Wrong combination of pumps, breakers don't trip.
OPSA1.BNK 2002 NRC exam KEH 10/13/01
NRC 5-93; ROT-4-64 F6; CP FPC final; ROTs M - TI; ROTs N - T3 & 3A; ROTs
0 - T3;
LOIl-T7AR; LOII-T7AS; LOIL-T7BR/T7BS
KEY WORDS:
Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla
0630402001 058AA2.03 b.5 h.9 -V4- 2/3] ]DC DIST
17,9
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
IsIPoints= ] 1A 1B IC 11)IA 1B] IlDIA 1B I Scramble Range: A- Ed
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 15
11. 4-90 002/4/5-30 1/ 1150401001 / 055EA2.03/ 3.9/4.7/ 44-[2/3]/
The following plant conditions exist:
- A Station Blackout has occurred.
- The Offsite Transformer is available.
- The "B" Emergency Diesel Generator is tagged out for maintenance
- Annunciator Q-02-03, Diesel Generator "A" Breaker Closed, is in alarm but
Breaker 3209, "A" EDG 4160V ES Bus Supply Breaker has reopened.
- Electricians have reported that there is no fault on the "A" 4160V ES bus.
Which of the following actions by itself is sufficient to allow closure of Breaker 3211, "A"
Offsite Transformer 4160V ES Bus Supply Breaker, and energize the "A" ES 4160V ES Bus?
-'A. Defeat the "A" 4160 V ES Bus lockout.
B. Depress the "4160V ESA UV Reset" pushbutton.
C. De-energize the undervoltage relay for the "A" 4160V ES Bus.
D. De-energize the DC control circuit for Breaker 3209.
Reasons:
A. Correct, the bus lockout has to be reset to energize the bus from one of the
normal supply breakers.
B. This action is only a portion of what is needed to permit closure of an offsite
power supply breaker. Unless the undervoltage relay for the "A" ES 4160V
Bus is de-energized, the action will have no effect on permitting breaker
closure.
C. De-energizing the undervoltage relay will permit resetting of the 4160V ES
Bus lockout but this action alone will not allow closure of the offsite breaker.
D. De-energizing the DC control circuit for Breaker 3209 will only prevent
remote operation of that breaker.
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 16
11. 4-90002/4/5-30 1/1150401001/055EA2.03/3.9/4.7/44-[2/3]/
New question written for Sept 2000 SRO exam. (2-14-2000 mg)
Stem modified 8-10-00 CMC
REPEAT
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
4 15-301 11150401001 1055EA2.03 k.9 k4.7 k4-[2/3] I
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points [= IA IID 1AD1B Scramble Range: A - Id
Friday, January 18, 2002 @ 06:52 AM
2K2SRO.BNK Page: 17
12. 5-01 004/5/ / 1190201002/ G2.2.22/ 3.4/4.1/ 55-[2/3]/
The following conditions exist:
- The plant is in Mode 5 following a refueling outage.
- SP-370, Quarterly Cycling of Valves, is being conducted.
- The operators testing CAV-2, Pressurizer and Letdown combined sample
containment isolation, report that it has not met the requirements specified on
its engineering data sheet.
What action(s), if any, should be taken prior to entry into Mode 4?
A. No action is required prior to entry into Mode 4.
B. Ascension into Mode 4 is prohibited until CAV-2 is repaired.
C. Close CAV-2 and de-energize within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of entering Mode 4.
"/D. Isolate the penetration associated with CAV-2 prior to entering Mode 4.
Reasons:
A. Containment isolation valves are required to be operable in Modes 1-4, an
action is required.
B. Mode ascension can be performed if LCO 3.0.4 is complied with.
C. Containment isolation valves are required to be operable in Modes 1-4, an
action is required. These actions do not comply with LCO 3.0.4.
D. Correct, these actions comply with LCO 3.0.4 and 3.6.3 condition A. Mode
ascension is allowed.
Unmodified bank question (5-01 #60) for Sept 2000 SRO exam. (4-5-2000 mg)
Provide TS
3.0.4 and 3.6.3
BANK
KEY WORDS:
Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective
15 1 1190201002 G2.2.22 .4 .1 55- 2/3
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 18
"12.5-01 004/5/1/1190201002/ G2.2.22/ 3.4/4.1/ 55-[2/3]/
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Ej Scramble Choices
I *e IPoints[
1 IDIAIB ICID 1A ICIlDIA I Scramble Range: A-
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 19
13. 5-01 005/10/ / 1150401001/ COCG2.1.4/ 2.3/ 3.4/ 33 [11/ ITS
While on watch a reactor operator must leave due to illness.
The Control Room Supervisor (CRS) has called for a relief operator to correct the situation,
which of the following conditions describes the maximum time the shift crew may remain
below minimum staffing requirements?
A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, at all RCS temperatures.
0
B. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, provided that RCS temperature is greater than 200 F.
'VC. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, at all RCS temperatures.
0
D. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, provided that RCS temperature is greater than 200 F.
A. Does not disallow the situation, but incorrectly states the time restriction.
B. Incorrectly restricted by RCS temperature.
C. CORRECT; T.S. section 5.2.2 identifies for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and no RCS temp limitation.
D. Incorrectly restricted by RCS temperature.
NEW 2002 KEH (7/12/01) Provide ITS section 5.2.2
KEY WORDS: A .
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
10 11150401001 1COCG2.1.4 2.3 .4 :31 ITS
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points ]icD11 I IB IC IDJA IB1C ID I Scramble Range: A -
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 20
14. 5-01 006/ 5//1190201006/ 005G2.1.12/ 2.9/4.0/33 [11/ ITS
Given the following plant conditions:
- Mode 6; preparing for refueling operations.
- Refueling Water Canal level is < 154 feet.
- BWST level is 12 feet.
- RCS temperature is 90'F.
- "A" DHR loop is in service.
- Eddy current testing is in progress on both OTSGs.
Which of the following statements describes the Technical Specification requirements for the
DHR system during these conditions?
A. One DHR loop shall be in operation.
B. One DHR loop shall be in operation. The required DHR loop may be removed from
operation for < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
"C. Two DHR loops shall be operable and at least one DHR loop shall be in operation.
D. Two DHR loops shall be operable. The DHR loops may be removed from operation
for < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
A. Level is <156, this spec does not apply.
B. Level is <156, this spec does not apply.
C. Both DHR loops are required to be operable, with one in service.
D. Both DHR loops are required to be operable, there is no note for removal.
NEW 2002 KEH (7/12/01) Provide ITS 3.9.4 and 3.9.5
KEY WORDS:
0 'bjective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
15 1 11190201006 1005G2.1.12 .9 ko 33 1 1iTS
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points[* IC Scramble Range: A - E
2K2SRO.BNK Page: 21
Friday, January 18, 2002 @ 06:52 AM
15. 5-01 007/5//1190201006/ COCG2.1.33/ 3.4/4.0/33 [2/3]/ ITS-CRD
Given the following plant conditions:
- Reactor power is 70%.
- 3 RCP operation for the last 48 days. stator, but
- Control rod Group 5 Rod 8 has been determined to be inoperable due to a failed
the rod will TRIP. postion.
- Control rod Group 5 Rod 8 is positioned 10 inches from the Group 5 average
Which of the following describes the required action?
A. Calculate SDM within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
"/B. Reduce power to 44% within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
C. Place the reactor in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D. Align Group 5 rods to within 6 inches of rod (5-8) within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
A. The SDM calculation is required W/T 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. (Condition A. Action A.2. 1.1.)
B. CORRECT; Reduce power to < 60% of the allowable thermal power W/T 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
(Condition A. Action A.2.2) (75 x .6 = 45%)
C. IF unable to perform required actions then W/I 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> be in mode 3. (Condition B. Action
B.1.)
be
D. The rods should be realigned W/I 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if that action is appropriate. Also the rods would
W/I 6.5% not 6 inches.
NEW 2002 KEH (7/13/01) Provide ITS 3.1.4
KEY WORDS:
Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla
1190201006 CoCG2.133 i 3 21
320 ITS-CRD
15
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 El Scramble Choices
Points= 1111 IDIIIAIcDABJ C Scramble Range: A- W
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 22
16. 5-01 008/8/ OPS 5-01/ 1190201006/ COCG2.1.12/ 2.9/4.0/ 55-[2/3]/ ITS
Given the following plant conditions:
100% power.
At 0815 on October 23, the results of performing SR 3.8.6.1 were as follows:
3A 1 Pilot cell Parameters: 3A2 Pilot cell Parameters:
2.22 VDC 2.18 VDC
Level between high and low marks Level between high and low marks
Specific Gravity = 1.212 Specific Gravity = 1.205
3B1 Pilot cell Parameters: 3B2 Pilot cell Parameters:
2.20 VDC 2.05 VDC
Level between high and low marks Level between high and low marks
Specific Gravity = 1.2 10 Specific Gravity = 1.198
Which of the following describes the required ITS actions?
-A. Restore only the Train B battery cell parameters to within limits by 1015 on October
23.
B. Immediately enter LCO 3.0.3 and initiate a plant shutdown by 0915 on
October 23.
C. Restore only the Train A battery cell parameters to within limits by 1015 on
November 23.
D. Restore the Train A and B battery cell parameters to within limits by 1015 on
November 23.
2K2SRO.BNK Page: 23
Friday, January 18, 2002 @ 06:52 AM
16. 5-01 008/8/ OPS 5-01/ 1190201006/ COCG2.1.12/ 2.9/4.0/ 55-[2/31/ITS
A. CORRECT: At 0815 on October 23, the Train B battery is declared
inoperable since 3B2 battery cell parameters are outside the Category C
limits of Table 3.8.6-1. TS 3.8.6 Condition B requires immediately declaring
the associated battery inoperable. Per LCO 3.0.6, this Required Action
results in entering Condition A of TS 3.8.4.
B. LCO 3.0.3 would be entered if a battery in both trains were inoperable.
However, only the 3B2 battery is inoperable for the above conditions.
C. Train A battery parameters are within Category A limits of Table 3.8.6-1.
D. Only Train B DC electrical power subsystem is inoperable. Train A battery parameters are
within Category A limits of Table 3.8.6-1.
Ref:
ITS 3.8.6 and 3.8.4
BANK 2002 NRC exam KEH 10/20/01
KEY WORDS:
Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective
11190201006 IcOcG2.112 19.0 55-535 ITs
18 I0Ps5-01
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ]Scramble Choices
Points[
inle 1A1B IcIDIA IBCAB Scramble Range: A-
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 24
17. 5-01 009/7/ / 1190201006/ EQC2.2.25/ 2.5/3.7/ 44-[2/3]/ ITS
Given the following plant conditions:
The "B" RPS channel was scheduled for SR 3.3.1.5 Channel Calibration on 3 Jan 2002. This is
a 92 day frequency surveillance, and it was NOT performed.
Which of the following dates identifies when the "B" RPS channel must be declared
A. If the surveillance is not completed by 4 Jan 2002.
,,B. If the surveillance is not completed by 26 Jan 2002.
C. If the surveillance is not completed by 3 Feb 2002.
D. If the surveillance is not completed by 17 Feb 2002.
A. This is within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1 day, SR 3.0.2 allows 1.25 times the frequency for completion of a
surveillance. (92 X .25 = 23 days)
B. CORRECT: SR 3.0.2 allows 1.25 times the frequency for completion of a surveillance. (92
X .25 = 23 days) This is 23 days later.
C. This is 31 days later which is the frequency for some of the RPS surveillances.
D. This is 45 days later which is the frequency for some of the RPS surveillances.
Modified BANK 2002 NRC exam KEH 11/8/01
KEY WORDS:
Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla
11190201006 EQC2.2.25 =5 7---2/3 J ITS
17
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points1 ICIEIDAABIBCCIDJAý Scramble Range: A- W
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 25
18. 5-01 010 (HARDLIN K 178-29072 001)/ 5//1190201006/ 017G2.1.12/ 2.9/4.0/ 55-[2/31/ I/C
Given the following plant conditions:
Power 100%
SP-338 has been performed
Evaluate the data sheet (See Attached; Enclosure 1, page 5)
Which of the following identifies the required actions in accordance with ITS 3.3.17?
A. Restore required channel(s) to operable status immediately.
B. Restore required channel(s) to operable status within 7 days.
C. Restore required channel(s) to operable status within 30 days.
,/D. No action required.
A. Have not exceeded the time or action taken lAW Condtion A, ALL channels are operable.
B. ALL channels are operable.
C. ALL channels are operable.
D. All channels are operable, have a reading that may or may not be out by 42 degrees but only
one for each quadrant and between different channels. The channels are the chessel recorders
"A" & "B" as designated in ITS 3.3.17 (page B 3.3-125B)
NEW 2002 NRC exam KEH 11/12/01 (PROVIDE ITS 3.3.17 and BASES)
KEY WORDS:
Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla
15 -T1190201006 117G2.1.12 2.9 k.0 155-[2/31 II/C
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Z Scramble Choices
Points= ID1A B IC 1A ID Scramble Range: A-
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 26
19. 5-113 001/6//1150502013/ 024AA2.05/ 3.3/ 3.9/ 44-[1]/ AP-490
AP-490 has you verify that you have > 10 gpm boration flow rate.
Which of the following will provide adequate SDM based on the ITS assumptions (BOC,
BAST @ 11,600 ppm) with this flow rate.
A. 30 minutes
B. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
'/C. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
D. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
A. ITS uses BAST at 11,600 ppm, with 10 gpm at BOC would give a 1% delta K/K in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
B. ITS uses BAST at 11,600 ppm, with 10 gpm at BOC would give a 1% delta K/K in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
C. CORRECT: ITS uses BAST at 11,600 ppm, with 10 gpm at BOC would give a 1% delta
K/K in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
D. ITS uses BAST at 11,600 ppm, with 10 gpm at BOC would give a 1% delta K/K in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
ITS bases for 3.1.1
NEW 2002 NRC exam KEH 10/16/01
KEY WORDS:
Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective
16 X
11510502013 024AA2.05 .9 -
4.3 P-490
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points ICIDIAIBICI IIABcD Scramble Range: A - W
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 27
20. 5-116001/2//1150502012/ E14EA.2.2/ 4.0/4.0/ 33-[1]I EOP-02
Enclosure 1 of EOP-14, SPO Post Trip Actions, states:
"Isolate the drains from the 5A and 5B FWHE's (Feedwater Heaters) to the DFT (Deaerator)."
Which of the following is the reason for this action following a Reactor Trip?
A. This prevents oxygen intrusion into the DFT.
B. This prevents damage to the 5A and 5B FWHE's from reverse flow of DFT steam
and water.
",/C. This prevents water hammer in the DIFT due to exposure to vacuum.
D. This prevents possible FWHE tube leaks due to formation of excessive differential
pressures.
A. This is true for the DFP vents, NOT the drains.
B. This is for the DFT protection, not the FWHE.
The
C. CORRECT: This separates the DFP from the condenser, therfore exposure to vacuum.
flow path would cause water hammer.
D. This is for the DFT protection, not the FWHE.
OPSA1.BNK 2002 NRC exam KEH 10 13/01
ROTs J - TlOA; ROTs M - T6A; ROTs N - T4B & T4BA
KEY WORDS:
Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla
I 11150502012 TE4EA.2.2 I.0I.0 I3-1 IEOP-02
12
ANSWERS: Version Answers:
7 8 9 Scrambte Choices
0 1 2 3 4 5 6
Points Z IDI1I IlDABIl
IC Scramble Range: A- W
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 28
21. 5-14 001/ 6//1190402001 / 009G2.4.22/ 3.0/ 4.0/ 44-[1]/Al-505
In accordance with Al-505, which of the following is an allowable exception to performing
symptom response in the EOPs?
A. Any loss of SCM during HPI/PORV cooling does not require branching to EOP-3
for 2 minutes.
B. During a Loss of Off-site Power, EOP-2 Immediate Actions do not need to be
performed unless the EDGs fail to power the ES busses.
C. During an OTSG Tube Rupture the reactor is tripped because pressurizer level drops
below 100", EOP-2 does not need to be entered since EOP-6 contains all necessary
guidance.
"vD. SCM is lost during restart of an RCP, EOP-3 does not have to be entered unless
SCM is not restored within 1.5 minutes.
A. If a pressure decrease occurs during EOP-4 that results in an ISCM then must enter EOP-3
B. If the EDG had not started than this is a Station Blackout and EOP-12 applies.
C. If the reactor was tripped due to pressurizer level by the operator than you must go to
D. CORRECT: You can wait 1.5 minutes to recover SCM before transition to EOP-3.
This is from Al-505 section 4.1.2.5.a page 10 of 35
OPSA1.BNK 2002 NRC exam KEH 10/13/01
KEY WORDS:
Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective
16 1 11190402001 1009G2.4.22 .0.0 10 1:1 1 kl-505
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points 1 ID1A 1 BBcIDIAI Scramble Range: A- W
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 29
22. 5-31 001 / 4,7//1150401001/ 067G2.4.27/3.0/3.5/ 33-[1j/ FIRE
Given the following plant conditions:
- A "Control Complex Fire Alert" alarm has been received.
- A Halon bank has actuated in the cable spreading room.
- Multiple plant components/equipment are cycling erratically causing a loss of
plant control.
Which of the following describes the action(s) that should be initiated?
A. Enter AP-880, Fire Protection, and concurrently perform AP-5 10, Rapid Power
Reduction.
B. Enter AP-880, Fire Protection, only and perform required actions.
"/C. Enter AP-990, Shutdown from Outside the Control Room, only and perform
required actions.
D. Enter AP-990, Shutdown from Outside the Control Room, and concurrently perform
AP-880, Fire Protection.
Reasons: REWORD T' DISTRACTOR. COULD BE ARGUED AS CORRECT ALSO.
8-16-00 Modified "D" to have concurrently perform AP-880 which is not correct when
entering AP-990. KEH 10/13/01
A. AP-990 should be entered due to the loss of plant control. Per note at
begining of AP-990, no other procdure to be used unless directed by
AP-990.
B. AP-990 should be entered due to the loss of plant control. Per note at
begining of AP-990, no other procdure to be used unless directed by
AP-990.
C. CORRECT: AP-990 should be entered due to the fire and loss of plant
control. Per note at begining of AP-990, no other procdure to be used unless
directed by AP-990.
D. AP-990 should be entered due to the loss of plant control. Per note at
begining of AP-990, no other procdure to be used unless directed by
AP-990.
OPSA1.BNK 2002 NRC exam KEH 10/13/01
NRCM; ROTs O- T13 K/A# 067AA2.13 3.3/4.4
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 30
22. 5-31 001/4,7//1150401001/ 067G2.4.27/3.0/3.5/33-[1]/ FIRE
KEY WORDS:
Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective
4,7 11150401001 067G2,4.27 3.0 h.5 33-[1] IFRE
Version Answers:
ANSWERS:
0 1 2 3 4 5 6 7 8 9 mFj Scramble Choices
l U
Points
71 ID 1AI1 IC B B
ID[A Scramble Range: A-
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 31
23. 5-31 002/7// 1190402001/ 068G2.4.35/ 3.3/ 3.5/ 44-[1]/ AP-990
Given the following plant conditions:
Fire in the cable spreading room
AP-990 has been implemented and transfer is complete
Step 3.50 states; "Notify PPO to ensure selected MUP lube oil pumps are running."
Step 3.51 states; " WHEN MUP lube oil pumps are running, THEN notify RO to start selected
MUP.
Which of the following identifies the location for the completion for each of the two steps
above?
,/A. Lube oil pumps are started locally, and the MUP is started from the switchgear.
B. Lube oil pumps are started from the switchgear, and the MUP is started from the
remote shutdown panel.
C. Lube oil pumps are started from the switchgear, and the MUP is started from the
switchgear.
D. Lube oil pumps are started locally, and the MUP is started from the remote
shutdown panel.
the
A. CORRECT: LO pumps are started in the MUP cubicles, and the pumps are started from
4160V ES switchgear.
B. LO pumps are started in the MUP cubicles, and no controls on the RSD panel for the MUPs
C. LO pumps are started in the MUP cubicles.
D. No controls on the RSD panel for the MUPs.
NEW 2002 NRC exam KEH 10/13/01
KEY WORDS:
Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla
71190402001 68G2 .4.35 .3 3.5 1 P-990
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points=LII! 1AIBCIocl]AIBElII Scramble Range: A-
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 32
24. 5-42 001 / 18/ /1190101035/ G2.4.30/ 2.2/3.6/ 55-[2/3]/
Which of the following will require a notification to the NRC within a maximum of four (4)
hours?
A. Axial power imbalance is -61% at 92% power.
"/B. State of Florida notification following the death of a turtle on the bar racks.
C. Apprehension by security of 2 persons selling cocaine in the Ready Warehouse.
D. The hospitalization of two employees following a crane accident in the Turbine
Building.
Reasons:
A. -61% imbalance at 92% power violates safety limit 2.1. 1.1 and by safety limit
violation 2.2.4 the NRC must be notified within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
B Correct, the NRC must be notified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of notifying other
government agencies. (CP-151 Encl. 2 pg 12 of 23, pg 2 of 23 #4.)
C. The NRC requires 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification for the sale, use, or possession of illegal
drugs within the protected area.
D. A report to OSHA is made for a fatality or hospitalization of three or more
employees within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. As only 2 employees are injured in this
circumstance, OSHA notification will be through normal channels.
Provide CP-151, TS 2.1, TS 2.2 and the COLR. New question written for Sept 2000 SRO
exam. (3-7-2000 mg)
REPEAT
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
IG2.4.30 .2 3.6 155- 2/3
118 X1190101035
Version Answers:
ANSWERS:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points = IIC AIBC
IBIC IDlAIBII Scramble Range: A- W
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 33
25. 5-50 001/1//1150101004/ EQCG2.2.28/2.6/3.5/44-[1]/ FP-601A
Which of the following statements is correct concerning operating a fuel handling bridge with
interlock functions bypassed?
A. Operation of the bridge with interlocks bypassed is not administratively controlled if
done by an SRO qualified person.
"-B. Manual operation should not be routinely discounted as a possible alternative to
bypassing.
C. The bridges are never to be operated if it requires an interlock to be bypassed.
D. Operation with interlocks bypassed requires permission from the CR-3 Safety
specialist and the Man-on-Call.
A. SRO permission is required to bypass, it is controlled.
B. CORRECT: L&P in FP-601A that manual is an option, because it is slower and more
controlled.
C. Interlock have to be bypassed sometimes, never is not an option.
D. Refueling SRO or SSO but not safety man and man on call.
OPSA1.BNK 2002 NRC exam KEH 10/13/01
ROTs J - TIOB
KEY WORDS:
Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla
I1 1150101004 EQCG2.2.28 .6 4.5-1 FP-G01A
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points IB ICIZ 11cDA11 Scramble Range: A - Wd
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 34
26. 5-69 001 / 6//1150501001/ EPPG2.4.27/ 3.0/3.5/ 44-[1]/ FIRE
Given the following plant conditions:
A fire has been burning in the Auxiliary building
The fire team leader has just reported the fire is OUT.
Which of the following is your required action as control room supervisor with respect to
AP-880?
A. Restore control complex ventilation.
B. Restore FSP-2A/B, Diesel Fire Service Pumps, to standby.
C. Notify the SSO to assess plant conditions.
"vD. Establish a fire watch.
A. Step 18 plant ventilation once fire out step 13 has fire watch established.
fire
B. This is step 15 states fire protection system not specific pumps once fire out step 13 has
watch established.
C. This is step 16 for fire damage, once fire out step 13 has fire watch established.
D. CORRECT: Once fire out step 13 has fire watch established.
NEW 2002 NRC exam KEH 10/13/01
KEY WORDS:
Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla
EPPG2.4.27 ý.0 b.5 k4-[11 IFIRE
16 1150501001
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Z Scramble Choices
Points 1 ID1A BT TD[AI= Scramble Range: A - W
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 35
27. 5-85 001/ 5// 1150502007/011 G2.4.5/ 3.0/ 4.0/ 55-[2/3]/ EOP-03
Given the following plant conditions:
- A LOCA with a Loss of SCM.
- RCS pressure is 1100 psig.
- High pressure injection (HPI) and reactor building isolation and cooling
(RBIC) have actuated.
- Emergency feedwater initiation and control (EFIC) has actuated.
- Steam generator levels are progressing toward their required setpoint.
- OTSGs pressure is 500 psig and decreasing.
- RCS temperature begins to increase up the saturation line.
Which of the following procedures should be entered?
A. EOP-2, Vital System Status Verification.
"/B. EOP-4, Inadequate Heat Transfer.
C. EOP-7, Inadequate Core Cooling.
Reasons:
A. Adequate SCM does not exist to go to EOP-2 per step 3.20.
B. CORRECT: Step 3.17 sends you to EOP-4 for inadequate primary to secondary heat
transfer, (feeding OTSGs and still the RCS is heating up) based on entry conditions.
C. The system is saturated therefore, entry conditions for EOP-7 are not met.
D. Since LPI flow does not exist the branch point to EOP-8 should not be taken per step 3.11.
OPSA1.BNK (Modified) 2002 NRC exam KEH 10/13/01
NEED COPY EOP-03
NRC 6-97; ROTs N - FPCF K/A# 009EA2.01 4.2/4.8 TSK# 3440403001(STA?)
KEY WORDS:
Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective
I5 L 1150502007 I011G2.4.5 .4.0 55-2/3 EOP-03
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 36
27. 5-85 001/ 5// 11505020071011G2.4.5/3.014.0/ 55-[2/3]/ EOP-03
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
SinPoints= *LEl WIIZZI LDABC Scramble Range: A- W
2K2SRO.BNK Page: 37
Friday, January 18, 2002 @ 06:52 AM
28. 5-97 001/ 4// 1150501001/ 074G2.4.21/ 3.7/4.3/33 [2/3]/ EOP
Plant conditions are as follows:
In EOP-7 Inadequate Core Cooling (ICC) with the RCS in region 3.
MUP-LB is running, with ONLY MUV-24 open.
RCPs- 1B/D are running.
will be re-energized and
MUP-IC will be started within the next minute, and MUVs-25 and 26
available.
Which of the following actions are applicable for this scenario?
A. When MUP-1C is started, revert to the begining of EOP-7, step 3.1.
-t
B. Open high point vents until the cooldown is complete.
C. Secure the RCPs to prevent tube failure in the OTSGs.
D. Throttle HPI to control cooldown rate.
prior to step 3.21
A- DO NOT REVERT to the begining if conditions change. NOTE
to remove non-condensable
B- CORRECT; Until cooldown is complete these should be open
gases.
C- The pumps continue to run until in the severe accident region.
that cooldown may
D- HPI will not be throttled until SCM is re-established, NOTE identifies
be excessive due to HPI flow.
NEW 2002 SRO KEH 7/11/2001 Provide EOP-7
KEY WORDS:
RO Import. SRO Import Initial/Re System
Objective Lesson Pla Task Numbe K/A
074G2.4.21 47 .3 F3312/3 EOP
14 1150501001
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ScrambleRange:s
Points =
FB lc I AIBl D[AI Scramble Range: A - Wý
Page: 38
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK
29. 5-97 002/5/ OPS 5-97/0170502001 / COCG2.1.20/ 4.3/4.2/11-[2/31/ EOP-7
Given the following plant conditions:
- All feedwater has been lost.
- No High Pressure Injection (HPI) pump is operating due to multiple
mechanical failures.
- Reactor Coolant (RCS) pressure is 1285 psig.
- SPDS indicates superheat conditions.
(SPDS) indicate 1250'F.
Twenty minutes later (at the same pressure) the incore thermocouples
steps to attempt to
What actions would the operators be following after initially completing
restore HPI and Emergency Feedwater (EFW)?
"-'A. Operators will exit the EOPs and be under the control of the TSC and the Severe
Accident Mitigation Guidelines.
B. Reduce OTSG pressures, open all high point vents, then open the PORV.
greater than
C. Attempt to restore HPI and EFW, reduce RCS pressure to 100 psi
OTSG pressure if > 2400 psi and reduce OTSG pressure.
of HPI
D. Transition to EOP-8, LOCA Cooldown, only after successful restoration
and/or EFW.
Reasons:
A. Correct, conditions are in the severe accident region.
are in the severe
B. These are actions for region 3, and the plant conditions
accident region. are in the severe
C. These are actions for region 2, and the plant conditions
accident region. are in the severe
D. These are actions for region 1, and the plant conditions
accident region.
BANK 2002 NRC exam KEH 10/20/01
Provide EOP-07 and steam tables; New question written for LOI-99-01
exam. (8-1-2000 mf) Modified 10/27 per G.C./M.V.
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 39
29. 5-97 002/5/ OPS 5-97/ 0170502001/ COCG2.1.20/ 4.3/4.2/11 -[2/3]/ EOP-7
KEY WORDS:
SRO Import Initial/Re System
Objective Lesson Pla
bPS 5-97
Task Numbe
0170502001
K/A
IcOCG2.1.20 4.3
RO Import.
4.2 1--/g
IEoP-7 I
15
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points=
1A 1BicIDZIAI1B CIDAB Scramble Range: A - wý
Friday, January 18, 2002 @ 06:52 AM 2K2SRO.BNK Page: 40
SP-338 001 (HARDLINK 178-29072 002) ENCLOSURE 1
(Page 5 of 11)
POST ACCIDENT MONITORING CHANNEL CHECK (Continued)
CONTROL ROOM
(Unless otherwise noted)
All Channels
Agree Within 42F
DEVICE UNIT READING
RC-171-TR, Core Exit Temperature
IM-5G-TE Channel 1 Quadrant WX OF 610
IM-9E-TE Channel 6 Quadrant XY OF 608
IM-9H-TE Channel 5 Quadrant YZ OF 611
IM-3L-TE Channel 2 Quadrant ZW OF 663
IM-6C-TE Channel 3 Quadrant WX OF 642
IM-1 3G-TE Channel 8 Quadrant XY OF 609
IM-100-TE Channel 7 Quadrant YZ OF 610
IM-60-TE Channel 4 Quadrant ZW OF 611
RC-172-TR, Core Exit Temperature
IM-7F-TE Channel 9 Quadrant WX OF 608
IM-1OC-TE Channel 16 Quadrant XY OF 608
IM-1OM-TE Channel 13 Quadrant YZ OF 650
IM-4N-TE Channel 12 Quadrant ZW OF 610
IM-2G-TE Channel 10 Quadrant WX OF 612
IM-11G-TE Channel 15 Quadrant XY OF 636
IM-13L-TE Channel 14 Quadrant YZ OF 613
IM-6L-TE Channel 11 Quadrant ZW OF 608
To meet all of the requirements of operability for Core Exit Temperature
(Thermocouple), each quadrant requires at least two OPERABLE detectors, one from
each channel. Operability of only one detector for any quadrant constitutes entry into
Condition A of LCO 3.3.17. Any quadrant with no operable detector constitutes entry
into Condition C of LCO 3.3.17. Separate Condition entry is allowed for each
quadrant.
D,.. 1
Friday, January 18, 2002 @ 06:51 AM 2k*.un. ae.:
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.
"vD. End of core life.
Reasons:
A steam line break results in a
As the core ages MTC becomes increasingly more negative.
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:
Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla
1150402016 10351501 S1 14-tl33
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 I!' ScramubledUuA.U
Points=1
ID1A 1B 1c IDJA B C Scramble Range: A - d
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 2
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
"vB. 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-210.
KEY WORDS:
Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective 13.6 h.9 133 2/3 RXS/U
17 0150102001 032AA2.02
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 "JScrambleUhrIiJW s
Points 1 IDI IAIBI CABc Scramble Range: A- d
Friday, January 18, 2002 @ 06:51 AM 2k2com.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.
'D. 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
112 JGT-001R24 11190102008 JG2.3.2 .5 12.9 133-[1] I
ANSWERS: Version Answers:
01 234566 7 8 9 []Scramble Choices
Sin Points[Z Z ID
DAIBICIDIA
lflAI Scramble Range: A - N
Friday, January 18, 2002 @ 06:51 AM
2k2com.bnk Page: 4
4. 2-34 001/ 8// 150502005/ 037AK1.01 / 2.9/3.3/11 [2/31/ 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
pressure equal to 950 psig?
(All temperatures are rounded to the nearest whole number)
A. 524 0 F.
"-B. 5400 F.
C. 555 0 F.
D. 565 0 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:
K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla Task Numbe
9 b.3 11 2/31 ISGTL
FB 150502005 037AK1.01
Version Answers: 7 Sr-rcrmhle Choices
ANSWERS:
Points = WIB lZ DAlllC Scramble Range: A - D
2k2com.bnk Page: 5
Friday, January 18, 2002 @ 06:51 AM
5. 2-34 002/5, 15//0020402013/008AK3.02/3.6/4.1/33 - [11/
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:
K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla Task Numbe
10020402013 1008AK3.02 .6 .1 3- 1
15,15
ANSWERS: 0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points[=]
IJ IlIEIABGI Scramble Range: A- J
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 6
6. 3-20 001/ 3/ / 1150502002/ E03EK3.1/ 3.2/ 3.8/33 [2/31/ 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:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
13 1150502002 IEO3EK3.1 b.2 8 3 2/31 EOP-3
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZJ Scramble Choices
Points = IC IDlA1B ICIDIAIBIC IDI Scramble Range: A - wý
2k2com.bnk Page: 7
Friday, January 18, 2002 @ 06:51 AM
7. 4-07 001 / 4//0860402001/ 086A1.01/2.9/3.3/33 [2/31/FIRE
Given the following plant conditions:
"A fire 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-2AIB, 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.
chargers
B. CORRECT: The LOOP will de-energize ACDP-7, loss of power to the battery
not been reached
would start these pumps, with pressure at 100 psig the pressure setpoints have
for starting.
C. The LOOP will de-energize ACDP-7, no power.
fire header
D. The surge tank is for damping system surge pressure, not adequate to supply
pressure during actuation of fire system.
NEW 2002 NRC exam KEH 10/2/01
KEY WORDS: System
Task Numbe K/A RO Import. SRO Import Initial/Re
Objective Lesson Pla 33 t27/3 FIRE
4 0600 086A1.01 .9 13.3
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Eg Scramble Choices
Points= 1BZICI1DAATBAC Scramble Range: A - Wd
Friday, January 18, 2002 @ 06:51 AM 2kcom.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 RC1-LT1 220 208
RCS Tcold (NR) RC5A-TE1 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 2' .
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 160402005 016G2.1.311 .2 9 [2/31 ISASS
ANSWERS. Version Answers:
0 1 2 3 4 5 6 7 8 9 IvAl cramble, Choices
Points= IA C B IC Scramble Range: A - [A
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-PT 1, 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, 0101K4.03 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; LOI1-T5
BANK
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
13,4,7 1 b160102003 1027AA1.01 .0 13.9 b33-[2/31 101CYC2
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-[2/3]/ 01 CYC2
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 [Scramble Choices
Points[--* I IA sICIDAIsICIDIAI Scramble Range: A - W
Friday, January 18, 2002 @ 06:51 AM 2k2com.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
-1B. 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 1 10150102003 7015A4.01 ý.6 k.6 h3 2/31 IN'
ANSWERS: Version Answers:
0123456 7 8 9 E Scramble Choices
Points= ID IAIB
P tIBC I FZEI Scramble Range: A - W
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 12
11. 4-10 002/3/ / 1150402016/ 002K5.10/3.6/4.1/ 33-[2/3]/
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-8 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 B 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
"vD. 1070 MWt
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 13
11. 4-10 002/3/ / 1150402016/ 002K5.10/ 3.6/4.1/ 33-[2/3]/
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. 18.5' / 44' dT = .42 x 2544 = 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:
w
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
3 11150402016 1002K5.1 0 .61 133-[213
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points = IDIA1B IC ID Scramble Range: A - W
Friday, January 18, 2002 @ 06:51 AM 2kcom.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?
,'A. NI-3 will indicate greater than 1O- 1 0 amps and power is restricted to less than 5%.
B. NI-3 will indicate less than 10-10amps and power is restricted to less than 5%.
C. NI-3 will indicate greater than 10 amps and power is restricted to less than 1 x
10-9amps
D. NI-3 will indicate less than 10-amps 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-[2/3]/
KEY WORDS:
Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective
15,6 5-01 1150402016 1033AK3.01 .2 3. 132/3
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Isingl Points i 1AIBICID IAIIBICIDIAAB 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 [11/ 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).
"C. 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.
sink.
C. CORRECT; based on limiting the pressure spike on the loss of heat
D. These are based on RCS flow, temperature, and flux.
NEW 2002 KEH (8/7/01)
KEY WORDS:
K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla Task Numbe
054AK3.01 k.1 k.4 1h3tll laPS
14 10010502002
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 El Scramble Choices
Points ICKIDIA lDIABD Scramble Range: A- W
Friday, January 18, 2002 @ 06:51 AM LKLCOm.DnK Page: 17
14. 4-12 003/ 4//0120102010/ 012K6.04/ 3.3/3.6/33 [2/3]/ 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 112K6.04 .3 .6 3 2/31 IRPS
ANSWERl:- Version Answers:
0 1 2 3 4 5 6 7 8 9 E Scramble Choices
Points Ic IDA lBIC IDIAIB cD Scramble Range: A- Wý
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 18
15. 4-12 004/4/ / 0120402007/ 045K1.18/3.6/3.7/33 [2/3]/ 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 [2/31/ RPS
TS Table 3.3.1-1; COLR; EOP-2 Step 1.0; OPS 5-01; KA #'s E02EK2.1 3.8/4.0, 003K3.04
3.9/4.2
LOI 1-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 1120402007 1045K1.18 .6 .7 3 2/3] IRPS
ANSWERS: Version Answers:
01 23456 7 8 9 E Scramble Choices
Points = ID A1B IDl1A1B ICMDA Scramble Range: A - Wd
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 [2/3]/ AMSAC
Given the following plant conditions:
52% power
AMSAC channel "B" is in TEST/CAL
"A" main feedwater flow instrument fails to 0%
Which of the following identifies the plant conditions?
"/A. AMSAC does not actuate.
B. AMSAC actuates the "A" channel of EFIC.
C. AMSAC actuates and trips the turbine, the reactor will not trip.
D. AMSAC actuates and trips the turbine, which trips the reactor.
A. CORRECT: With a channel in TEST the other channel is blocked, no trip or actuation will
occur.
B. The channel signal to EFIC is blocked and it will not actuate.
C. The channel is blocked no turbine trip will occur.
D. The channel is blocked no turbine trip will occur or reactor.
NEW 2002 NRC exam KEH 10/2/01
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
14,5 1 10450402001 A04AK3.2 .4 13.6 133 [2/31 IAMSAC
ANSWERS: Version Answers:
0123456 Z Scramble Choices
789
IAB~ClIIc
Points 1
Scramble Range: A - W
2kcom.bnk Page: 21
Friday, January 18, 2002 @ 06:51 AM
17. 4-12 006/ 4//0020102009/ 015AA1.03/3.7/3.8/ [2/3]/
The following conditions exist:
The plant is operating at 85% power.
One RCPPM channel test switch (SS6) is placed in "TEST" for RCP-ID.
Which of the following indicates the plant response should RCP- IC 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-LC trips; RPS will see a loss of two RCPs and each
RPS pump monitor will trip their respective RPS channel.
channels will be1tripped
B-CORRECT With each RPS pump monitor tripping their respective cnannel men aii KRP
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:
Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective
14 1 0020102009 15AA1.03 7
22/3 38
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 I/J Scramble ,Uoce
Points = 13IC IDII IcDIDABI IC Scramble Range: A - M
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 22
18. 4-13 001/ 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.
/B. 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 .3 14.5 13 [2/31 IES
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Sge Points=
1IDIAIBJIcDTAIC Scramble Range: A- d
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 23
19. 4-13 002/5/ / 0130102006/ 013K2.01 / 3.6/3.8/ 33-[2/3]/
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 1 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.
"/D. Both channels I 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 1 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 Io3K2.0t 13.6 13.8 3-2/3
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Z scramble Choices
Points =* IDIAB IZIABc
I DDA Scramble Range: A - D
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 24
20. 4-13 003/2//0130502001/ 006A3.03/4.1/4.1/ 33-[l]/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
"VC. 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
k..i 133-[11
JES
12 013050201 I06A3.C 13
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points = 1)ABC D Scramble Range: A - w
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 25
21. 4-14 001/ 3// 0410402001/ 003AK1.1 3 3.2/3.6/33 [2/3] ICS
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 10410402001 1003AK1.13 .2 13.6 133 [2/3]
ICos
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 WScramble Choices
Points = ID Scramble Range: A - R
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 instmment) 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.
2k2com.bnk Page: 27
Friday, January 18, 2002 @ 06:51 AM
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: Initial/Re
Lesson Pla Task Numbe K/A RO Import. SRO Import System
Objective
13.2 .2 -F3-[2/31
13,5 1 0410402013 59K1.07
ANSWERS: Version Answers: Scramble Choices
S i[nn1e n [
] Points j IAIB~CIIA
0123456789 IID II Scr
amble Range: A -
d
Friday, January 18, 2002 @06:51 AM 2kcom.bnk Page: 28
"23.4-14 003/3/1/ 0410402001/ 003K3.05/ 3.6/3.7/ [2/3V!
Given the following plant conditions:
Plant is at 85% power
All ICS stations are in AUTOMATIC
RCP-ID 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.
'/C. The Integrated Master will decrease demand at a rate sufficent to block the
calibrating integral.
D. The Unit Load Demand will decrease demand to the low load limit setpoint.
Reasons
A- the total feedwater flow control will not control any feedwater flow until one OTSG is on
low level limits, and the RCP trip (RCP flow circuit) will re-ratio feedwater
B- Track is actuated by a cross limit that would not be actuated based on the conditions during
the runback.
C- Correct. The runback will be at 50%/min which is faster than the 2%/min rate that blocks
the calibrating integral.
D- The ULD will decrease its demand but based on the runback to 75%, NOT the low load
limit of 129 MWe
NEW NRC 2002 KEH 5/2/01
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
13 1 141040200, 1003K3.05 b.6 13.7 /3I
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 L0lScrambleChoices
Points *] [JAICZI D Scramble Range: A - W
2kcom.bnk Page: 29
Friday, January 18, 2002 @ 06:51 AM
"24.4-16 001/3/ / 1010402004/ 068AK2.07/ 3.3/3.4/33 [2/3]/ RSP
Given the following plant conditions:
to the
Fire in the cable spreading room, the Control Room has been evacuated and transfer
Remote Shutdown Panel has been completed.
Following the transfer, RCS pressure decreased to 1400# and initiated Engineering Safeguards.
for
Which of the following identifies the starting status of the Emergency Diesel Generators
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.
"*D. 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
that ES will still
D. CORRECT, ES actuates on low RCS pressure, AND this is the one circuit
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:
K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla Task Numbe
1068AK2.07 .3 3.4 3 2/3 RSP
F3 I 11010402004
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
I I Points= ID1A1BIDIAIB ClI Scramble Range: A-
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 30
25. 4-21 001/ 2// 1150502002/ EO3EK1.2/ 3.8/4.0/33 [2/3]/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 IEO3EK1.2 b.8 k.0 3 [2/3 POS
ANSWERS: Version Answers:
01 23456 789 [A Scramble Choices
Points =-" 1A1B CIDlAIBIC Scramble Range: A - w
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 31
26. 4-25 001/ 7//0720402013/ 061AA1.01 / 3.6/3.6/3312/31/ 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-LI,
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
L7 _ 10720402013 1061AA1.01 13.6 13312/3] IRM
ANSWERS: Version Answers:
[Snge ] 0123456 7 8 9 E Scramble Choices
Points= 1B Ic ID IA I IC ID IA 1B IC I Scramble Range: A - wj
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.
"vB. 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 10720102001 1072A4.03 .1 b3.[ IRM
AKICUIC* . Version Answers:
0 1 2 3 4 5 6 7 8 9 E Scramble Choices
Points = 1B ICIDA ICIAIsIC I Scramble Range: A-
B11 r1
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.
"vB. 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; LOII-T5
BANK
KEY WORDS:
Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective
13 0070402004
!068K6.10 F25 129 13
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 Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points[ 1 IBKIDIAIBEDAIKFCA Scramble Range: A- W
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- 11A, Auxiliary Building Supply Fan is off.
- AHF- l1B, 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.
"VC. 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-1 1A 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 lA, AHF-1 lB, AHF-30, and AHF-34A.
D. RM-A2 in high alarm automatically trips AHF-9A, AHF-9B,
AHF-10, AHF-1I A, AHF-1 IB, 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 2k2com.bnk Page: 36
29. 4-25 004/4//1190101031/ 060AA1.02/ 2.9/ 3.1/ 33-[1]/ 01CYC2
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
14 1 11190101031 1060AA1.02 I.9 h.1 133-[1]
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 NScramble Choices
Points 1I BCD Scramble Range: A- N
2k2com.bnk Page: 37
Friday, January 18, 2002 @ 06:51 AM
30. 4-25 005/4/ / 0720402002/ 029K1.01/ 3.4/3.7/ 33-[1j/
Given the following plant conditions:
- Mode 5
- RB purge in progress
high alarm actuates
- RMA-1 (RB purge exhaust duct radiation monitor) gas
or close) in this condition?
Which of the following components are interlocked (stop
A. AHF-6A/6B (RB purge supply fans)
B. AHF-7A/7B (RB purge exhaust fans)
C. AHFL- IA/1B (RB purge exhaust dampers)
"vD. AHV-1A/IB/IC/LD (RB purge supply/exhaust valves)
Reasons:
A/B Per AP-250 the fans must be tripped manually
interlocked with RMA- 1
C- these dampers are to the charcoal filters and are not
D- CORRECT RMA-1 is interlocked to close AHV-IA/B/C/D
Other K/A 069AA1.01 3.5/3.7/ 029K4.03 3.2/3.5
MODIFIED BANK
KEY WORDS: Initial/Re System
Task Numbe K/A RO Import. SRO Import
Objective Lesson Pla
3.4 3 33-1I
= F0720402002 029Cc1.01
4 .... Answers:.. on rScramble Choices
ANSWRS: Version
ANSWERS:
0A1 2 4 Scramble R A..
- g1e ]Points=1 FDAI-V =IIBclIA Scramble Range: A-
2k2com.bnk Page: 38
Friday, January 18, 2002 @ 06:51 AM
31. 4-28 001/4//0080402011/ 001 K1.09/2.8/3.1/33 [2/31/ CRD
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.
I 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:
I oeonn PIo Toc*k Nilmhn K/A RO Import. SRO Import Initial/Re System
jec ve Lesso n Pla Task Numbe K/A RO Import. SRO Import Initial/Re
2.8 133 1213] IGRD
14 I 10080402011 I001K1.0
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points[ 4 IBIcIDIAIB C I Scramble Range: A- U
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 39
32. 4-28 002/4// 0450402001/ 007EK2.02/ 3.5/3.6/33 [2/31/ 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.
,/B. 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 LhO
B. CORRECT; Redundant trip confirm will actuate the Rx Trip [/O to trip the turbine.
C. RTM does not interface with the Turbine [/O relays
D. Redundant trip confirm does not interface with the Turbine trip L/O 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 Task Numbe K/A RO Import. SRO Import Initial/Re System
14 10450402001 007EK2.02 .5 13.6 3 2/31 c
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
ICIDl 1A IB CID1AIB ICI Scramble Range: A-
SPoints13
Friday, January 18, 2002 @ 06:51 AM 2k2com.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.
"/D. 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; LOII-TI
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
13,4 1 I0010402004 1014K4.04 12.6 12.9 3 1 CRD
ANSWERS: Version Answers:
01 234567 8 9 E Scramble Choices
Points Pn 1A 1
B Ic I 1
A BC ID JA Scramble Range: A - Wd
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 41
34. 4-28 004/5// 0010402019/ 001G2.1.32/3.4/3.8/ 33-[2/3]/
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- 1 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.
-1D. 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//0010402019/001G2.l.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:
Task Numbe K/A RO Import. SRO Import Initial/Re System
Lesson Pla
Objective
15 - F010402019 01G2.1.32 b.4 b.8 ý3-12/3 I
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points= IDAI. r A
DWIAIKBCIDj Scramble Range: A- W
Pica'A*
Friday, January 18, 2002 @ 06:51 AM £it m'bI.II
' Pa e:....
35. 4-28 005/3/ /1150502001/ 014A2.01 / 2.8/3.3/ 33-[1]/
that Control Rod groups 1
Following a loss of off site power, what are the indications, if any,
through 7 are fully inserted?
1 through
A. The CRD panel is de-energized, there are no indications that CRD groups
7 are fully inserted.
control panel are
B. All in-limit lights on the position indication panel and the diamond
on.
"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 battery
A. Following a plant modification made in 1999 (MAR 96-07-17-03)
in-limit
backup power supply was added that powers the position indication
on the position
lights following a loss of off-site power. The in-limit lights
indication panel would be on.
on the position
B. The CRD system is de-energized, only the in-limit lights
indication panel would be on.
only the in-limit lights
C. Correct, because of the installation of MAR 96-07-17-03
on the position panel would be on.
de-energized.
D. The in-limit lights on the diamond control panel will be
mg)
New question written for Sept 2000 RO and SRO exam. (3-22-2000
REPEAT
KEY WORDS: System
K/A RO Import. SRO Import Initial/Re
Objective Lesson Pla Task Numbe
14A2.01 .8 .3 3
3 1150502001
Version Answers:
ANSWERS: 0 92 4
A 6 7 8 9 Scramble Choices
Points 1 IIAIB2cl ýDScramble Range: A- R
2k2com.bnk Page: 44
Friday, January 18, 2002 @ 06:51 AM
36. 4-52 001/ 3,4// 0040402006/ 004G2.1.30/ 3.9/3.4/ 33-[1]/ MUP
Given the following plant conditions:
- 100% full power.
- "B" MUP is in operation.
- Channel "B" (LT-2) is selected for MUT indication.
Channel "A"
Which of the following describes the response of the makeup system if the
(LT-1), MUT level transmitter fails low?
V
-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.
open
C. Both "A" and "B" side BWST suction valves (MUV-73/58) will receive an
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 - T 13; LOI 1-T9AR/T9AS
KEY WORDS:
K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla Task Numbe
10040402006 04G2.1.30 .934 13-1 MUP
[3,4
Version Answers: Sc
Cr aromhle C-hoice s
ANSW ERS:
0 1 2 3 4 5 6 7 8 9S eR
Points=1
FANEL II2IJoIOIIM Scramble Range: A-
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-[1]/ 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?
",/A. 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.
OPSA1.BNK 2002 NRC exam KEH 10/12/01
ROTs K - T2; ROTs M - T6B
KEY WORDS:
Objec tive Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
13,4,7 j057AA1.05 b3.2 13.4 1-[1 ]MUP
V1150402016
Version Answers:
ANSWERS:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points=II
IA1BIC ID AIB Scramble Range: A - Wý
Friday, January 18, 2002 @ 06:51 AM 2k2com.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-1B) is tagged out for
maintenance.
Which of the following safety related equipment will be without cooling water?
A. MUP- IC, RWP-2B and BSP-1B are without cooling water.
B. MUP-I B, RWP-3B and BSP-1B are without cooling water.
C. MUP-I B, RWP-2B and BSP-1B are without cooling water.
vD. MUP-1C, RWP-3B and BSP-1B are without cooling water.
A. RWP-2B is cooled from SW
B. MUP-IB is cooled from SW
C. MUP-IB 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 10070402005 1026A1.06 1.7 13.0 h3-[2/3 IDHcc
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 [Scramble Choices
Points[ 1]
ID Scramble Range: A- U
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 47
39. 4-56 001/ 4// 0080402006/ 008K4.09/ 2.7/2.9/33-[1]/ SW
Given the following plant conditions:
- The "C" Nuclear Services Closed Cycle Cooling Water Pump (SWP-I C) 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-LC trips. SWP-lA remains in standby.
,B. SWP-1B auto starts first; then SWP-IA auto starts and SWP-1C trips.
C. SWP-IA auto starts first; then SWP-lB auto starts and SWP-1C trips.
D. Both SWP-IA and SWP-IB auto start and SWP-1C continues to run.
Reasons:
A. SWP-lA auto starts 8 seconds later.
B. CORRECT: SWP-IB starts first, the loss of suction low pressure would require SWP-IA.
The first Emergency SWP that starts, will then tripSWP-IC 15 seconds later
C. SWP-1B auto starts first.
D. SWP-lC trips 15 seconds after SWP-1A 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
F4 10080402006 1008K4.09 .7 .9 33-[11 ISw
AMNWERS. Version Answers:
MI !*4,7 VV *l1*I
0123456789 N Scramble Choices
Points=E ! IBiItDIA IBIICI ABC Scramble Range: A- d
Friday, January 18, 2002 @ 06:51 AM 2kcomn.bnk Page; 48
40. 4-57 001 / 7// 0760402003/ 075K1.01 / 2.5/2.5/ 33-[2/3]/ 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.
OPSAL.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 1 b760402003 I075K1.01 ý.5 ý.5 b3-[2/3] IRW
ANSWERS: Version Answers:
0123456789 F] Scramble Choices
Points= IDIAInICIDIA1B ICIPn I A Scramble Range: A - W
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
high
During a liquid release, the control board operator receives an RM-L2 trip on a valid
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.
'D. 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:
K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla Task Numbe
059AK2.01 7 V8 133 2/31 IRWL
145,7 1150402011
Version Answers:
ANSWERS: mScramble Choices
0 1 2 3 4 5 6 7 8 9
Points FATAIDIAIBIA BICIDA Scramble Range: A- W
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 1004K3.04 3.7 .9 133 [2/31 IRCP
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 E Scramble Choices
Points
Points1l IC lB
ID ICIDJA Saen
Scramble Range: A -
2k2comr.bnk Page: 51
Friday, January 18, 2002 @ 06:51 AM
43. 4-62 001/3/2-30/ 0260502004/ 027G2.1.28/ 3.2/3.3/ 33-[11/
the amount of iodine in the RB
Which one of the following parameters is controlled to limit
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
and does not affect iodine in the RB atmosphere.
B. This parameter is limited to reduce the amount of post-LOCA
and does not affect iodine in the RB atmosphere.
the pH of the
C. Correct Answer. TSP baskets inside containment adjust
pH creates non-volatle
RB sump to between 7.0 and 11.0. This range of
iodine and limits the amount of iodine in the RB atmosphere.
into the steam
D. RB spray limits containment pressure by spraying liquid
byproduct of this
atmosphere but any reduction of RB temperature is a
pressure reduction and not intended to limit iodine in the
atmosphere.
(3-6-00 CMC)
New Question written for Sept. 2000 RO and SRO exam.
Additional Task numbers; 1150502007, 1150402016
REPEAT
KEY WORDS: SRO Import Initial/Re System
Objective
39 -30 Pa
Lesson Task Numbe
I0260502004 K/A
2702.128 .2 Import.
RO 33"l1
Version Answers:
ANSWERS: EScramble Choices
0 1 2 3 4 5 6 7 8 9
uII
DABI Scramble Range: A -
Points=l
Friday, January 18, 2002 @ 06:51 AM 2kcom.bnk Page: 52
44. 4-63 001/4/ / 1030402002/ 103A1.01 / 3.7/4.1/33 [2/3]/ RB VENT
Given the following plant conditions:
Small RCS leak.
Containment temperature 150'F.
AHF-1A is running in slow speed (AHF-1A/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-IB starts in slow speed.
D. AHF-1A trips, AHF-1A starts in slow speed.
A. CORRECT: AHF- 1A will continue to run in slow speed.
B. AHF-1B will not start even though it is ES selected.
C. AHF-IA will not trip, nor will AHF-1B start.
D. AHF-1A 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 11030402002 1103A101 7 1 b3 2/31 IRB VENT
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 LjpGScramble -,hoices
Points = 1
ATICII CIDB1AIB Scramble Range: A - D
2k2com.bnk Page: 53
Friday, January 18, 2002 @ 06:51 AM
45. 4-63 002/3//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 IC (AHF-IC)
B. Nuclear Services Raw Water Pump 1C (RWP- 1C)
C. Inverter IC (VBIT-1C)
D. Make-up Pump IC Main Lube Oil Pump (MUP-2C)
Reasons:
A. Correct Answer: AHF-LC is powered from ES MCC 3AB and would be
lost if this component is de-energized.
B. RWP-1C 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 10620402007 22K2"0 b.o h.1 133-[1]
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 LSJ Scram[le Chloice
Points -- IAIBIc IDIAIB Scramble Range: A - W
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-[2/3]/
Given the following plant conditions:
- Plant in MODE 5
- Containment purge in operation
- Outside ambient air temperature is 64°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°F
- 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.
V/C. Suspend Rosemont transmitter calibration until RB Air Temperature is at or above
70'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 CF1 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:
Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla
15,7 1 10880102014 12.3.9!5 3.4 3-2/3
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points F 1 ICII D A1BAGIDI Scramble Range: A- W
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 56
47. 4-68 001/ 3,4// 0590102009/ 039A4.03/ 2.8/2.8/33 [1]/ MFW
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 1 b590102009 039A4.03 ..8.8 b3t[1 IMFN
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices
Points 1A1B IC ID IA I Scramble Range: A - [A
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 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.
R oD. 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 modifiy 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 modifly condensate demand.
Deaerator level is another part of the comparison.
This question also addressed K/A #'s 056K6.03 2.1/2.4, 059K 1.01 2.3/2.3; Unmodified repeat
question from LOI 99-01 program; NRCN
BANK
KEY WORDS:
Objective Lesson Pra Task Numbe K/A RO Import. SRO Import Initial/Re Sys tern
14 1590402001 1056K1.03 .6 12.6 b3-l1
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
PointsF 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]/ ELEC DIST
Given the following plant conditions:
Recovering from a station blackout condition.
No offsite 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.
v 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:
Task Numbe K/A RO Import. SRO Import Initial/Re System
Objective Lesson Pla
13,4,9 11,50 0201 O5EA1.06 .1 332/3 ELECST
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Sigl t Points[ F1IIýIB DAIBC Scramble Range: A- WD]
Friday, January 18, 2002 @ 06:51 AM 2k2com.bnk Page: 59
50. 4-90 002/3,4,7/ 0640402001/ 064K3.02/ 4.2/4.4/ 33-[1 I/ 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-IA automatic breaker (3209) closure?
A. EDG-IA is operating at 61 Hz and 4200 volts.
B. EDG-1B is running with its output breaker (3210) closed.
VC. 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 1640402001 1064K3.02 142 k.4 03-tlj1EDG
ANSWERS: Version Answers:
0123456789 E Scramble Choices
Points =*L [C ID[A 1B I IBIA IDI Scramble Range: A -
wd
-1--
ZKZC*om.bnk
-
Friday, January 18, 2002 @ 06:52 AM Page: 60
5 1. 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. DIESEL Det A
ERDQ5-Tr EN,.aRE 0
Startup 3203 3204
RICK CL O5[NG
BEST 3205 3206 ACTUATED CME 0
Unit Aux 3207 3208 3 .. LK CI I ((NG
AC TLJ,* lE11D 3201L 0
EDG 3209 3210
OPT 3211 3212
ELmCK CLOE(NG
AC ThI TED 3ECP 0
EtLXCKCL05[5NO
AC TUh TED 32LL 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.
,VC. 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 @ 06:52 AM 2k2com.bnk Page: 61
51. 4-90 003/ 4/ / 0640202001 / AO5AK2.1/ 4.0/ 3.8/ 33-[2/3]/
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 10640202001 k05AK2.1 k.0 h.8 b3-[2/3] 7
ANSWERS: Version Answers:
0123456 789 [] Scramble Choices
Points=* Po ints C DIILJZICAICDjScramble Range: A - D
Friday, January 18, 2002 @ 06:52 AM 2k2com.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 4.77you 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.
-/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 6
1020102001 1062A3.04 .7 .9 3 1 C DIST
ANSWERS: Version Answers:
I~n1e 0 1 2 3 4 5 6 7 8 9 Zj Scramble Choices
Points F 1 iB C ID IA B IC ID 1A 1B IC I Scramble Range: A - 1d
Friday, January 18, 2002 @ 06:52 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.
"C. 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 1 10620402017 057AK3.01 4.1 .4 h3-12/31
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 [Scramble Choices
Points= Points
D 1 A 1CD Scramble Range: A - rd
Friday, January 18, 2002 @ 06:52 AM 2kcom.bnk Page: 64
54. 4-93 001/ 4, 7, 9// 0780402006/ 055K3.01 / 2.5/2.7/ 33-[2/31/
The following plant conditions exist:
- The plant is at 50% power, 437 MWe.
- The "A" Condenser Air Removal pump, ARP-lA 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- 1A is running in the holding mode with the air ejector in service and the Main
Control Board low vacuum white lights are lit.
I/ 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- 1A 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-1A 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-IA 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
LKLcom..bnk
-uh --b
Friday, January 18, 2002 @ 06:52 AM Page: 65
54. 4-93 001/ 4, 7, 9//0780402006/ 055K3.01/ 2.5/2.7/ 33-[2/31/
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
10780402006 055K3.01 12.5 12.7 133-[2/31 1
14, 7,9
ANSWERS: Versi on Answers:
23456789 E Scramble Choices
0 1 2 3AIB 4 IC5
Scramble Range: A -
Points
Friday, January 18, 2002 @ 06:52 AM 2k2com.bnk Page: 66
55. 4-93 002/ 5,6,8/ / 0450402005/ 051AA2.02/ 3.9/4.1/ 1-[1 1/
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 258' 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 > 2500 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 @ 06:52 AM 2k2com.bnk Page: 67
55. 4-93 002/ 5,6,8// 0450402005/ 051AA2.02/ 3.9/4.1/ 11-[1]/
KEY WORDS:
Objective
15,6,8
Lesson Pla
1
Task Numbe
10450402005
K/A
1051AA2.02
RO Import.
b.9
SRO Import
4.1
Initial/Re
II1-[1 w
System
ANSWERS: Version Answers:
8 9 Z Scramble Choices
Fge ]Points iZ ZIZIIEIIDIAIBI
Sit _C 01234567A
LD Scramble Range: A -
Friday, January 18, 2002 @ 06:52 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 KEH
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
16,8 1 0550402001 k4.48 13.8 ]1 I
ANSWERS: Versi on Answers:
0 1 23456 7 8 9 [ Scramble Choices
Points= cI L Scramble Range: A- R
Friday, January 18, 2002 @ 06:52 AM 2kcom.bnk Page: 69
57. 5-01 001/ 4/ / 1190302001/ 076AA2.02/ 2.8/3.4/11 [2/3Y 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 />.
vC. 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 176AA2.02 .8 3.4 ill [2/3 IRCS ACT
ANSWERS: Version Answers:
0123456789 Z Scramble Choices
Points [*,] PnIDAI C D Scramble Range: A -
Friday, January 18, 2002 @ 06:52 AM 2kcom.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.
"/D. 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
15 1 1150502008 1056AK3.02 k.4 .7 133 [1] EOP-12
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices
Points= IABI D A Scramble Range: A -
R
Friday, January 18, 2002 @ 06:52 AM 2k2com.bnk Page: 71
59. 5-101 001/1// 1150502005/ EPP2.4.2/ 3.9/ 4.1/33 [2/3]/ EOP-06
Given the following plant conditions:
100% power
RCS pressure 2155 psig
RCS temperature 579°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-A 12, (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
11 1 11150502005 IEPP2.4.2 b.9 I.1 133 2/3] IEOP-06
ANSWERS: Version Answers:
0123456 789 M Scramble Choices
Points i
D Scramble Range: A- W
AI * I I
Friday, January 18, 2002 @ 06:52 AM LKMcom.bn Ik Page: 72
60. 5-102 001! 51/1150502003/ 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?
vA. 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 500 since the trip.
D. Running 4 RCPS just adds more heat to the RCS.
NEW 2002 KEH (7/12/01) Provide EOP-04.
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
15 1 11150502003 EO4EK2.1 .8 .2 i11 [2/3] IEOP-4
ANSWERS: Version Answers:
0123456 7 8 9 E Scramble Choices
Points= LL I
o CDA B Scramble Range: A - W1
Friday, January 18, 2002 @ 06:52 AM 2k2com.bnk Page: 73
61. 5-106 001/10//0050102012/ 005K5.02/3.4/3.5/33 [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.
vB. A steam bubble forms in the hot leg.
C. The RCS cooldown rate would be > 50 0 F/hr.
D. The RCS pressure drops so low that DHP-1A 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 FEO Import. SRO 1mport Initial/Re System
.4 b3.5
110 10050102012 005K5.02 b33 [231 IPZR
ANSWERS: Version Answers:
3456789 E Scramble Choices
Points 01B 2CID
ine 3 567C
Scramble Range: A - d
Friday, January 18, 2002 @ 06:52 AM 2kcom.bnk Page: 74
62. 5-14 001/11/4-564/ 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.
"VD. 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
i1 1-5664 1080402010 1076A2.01 13.5 13.7 I11-[2/3] 1
ANSWERS: Version Answers:
0123456789 E Scramble Choices
1e
Points=* Pit1ABCD A Scramble Range: A - II
Friday, January 18, 2002 @ 06:52 AM 2k2com.bnik Page: 75
63. 5-34 001/ a/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 IEPP2.4.12 b.4 13.9 3 [1] IE-PLAN
ANSWERS: Version Answers:
0123456 7 8 9 E Scramble Choices
Points= PontDAI C D Scramble Range: A- W
Friday, January 18, 2002 @C06:52 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.
"/B. 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 @ 06:52 AIDA 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 k-56 k080402012 126AA2.01 .9 b.5 133-[2/31 1
ANSWERS: Version Answers:
0123456789 E Scramble Choices
Points =' JP
IChIDAIDJA Scramble Range: A - w
Friday, January 18, 2002 @ 06:52 AM 2k2com.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.
,D. 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:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
16 1 11150402010 IEPP2.4.25 2.9 b.4 b3 [11 IFIRE
ANSWERS: Version Answers:
01 23456 7 89 E] Scramble Choices
Points
TIIofl Scramble Range: A - [
Friday, January 18, 2002 @ 06:52 AM 2k2com.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.
"vD. 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
I6 I 1150402012 I65AK3.08 b.7 13.9 33 2/3 IIA
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 [Scramble Choices
Points IDA 1 BICIDABCDA Scramble Range: A - W
Friday, January 18, 2002 @ 06:52 AM 2kcom.bnk Page: 80
67. 5-95 001/ 5/ /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 CFI1 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.
MIB : NRC exam 2002 KEH 9/25/01
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
15 1 1040502007 I1EK2.02 .6 V7 33] EOP-8
ANSWERS: Version Answers:
0123456 7 8 9 [E Scramble Choices
Points =* IDIA 1BIc IDIAIBIc IDJAI Scramble Range: A - Ij
Friday, January 18, 2002 @ 06:52 AM 2k2com.bnk Page: 81
68. 5-95 002/3/ / 1150502007/ E082.1.28/ 3.2/ 3.3/ 33-[11/
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-lD".
Which of the following statements describes the reason RCP- 1D 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- ID is specified because it produces the greatest flow of the 4 RCPs. Stopping
this pump provides the maximum margin for core lift concerns.
"/C. RCP-ID is specified because it is in the opposite loop from RCP-1B, which
provides pressurizer spray. Later guidance will reduce RCPs to a 2/0 combination.
D. RCP-ID 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- ID 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- I B 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-1D is not markedly different from the other
RCPs. This was not the basis of choosing RCP-ID.
Jl J I I
Friday, January 18, 2002 @ 06:52 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:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
b3-[lt]
13 1 11150502007 IE082.1.28 k.2 k.3 I
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 [ Scramble Choices
0 12 3 4 7 89__
I_
Points *L1 ICIDIABCDABCD Sc ramble Range: A - w
Friday, January 18, 2002 @ 06:52 AM 2k2com.bnk Page: 83
69. 5-96 001/ 6//0120402006/ 029EK1.03/ 3.6/3.8/33 [2/3]/ 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
JEOP-2
16 1 10120402006 1029EK1.03 13.6 13.8 133 2/3]
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 E] Scramble Choices
Points B IIDA BC Scramble Range: A- D
Friday, January 18, 2002 @ 06:52 AM 2kcom.bnk Page: 84
70. GT-001 001/17/ GET-00t/ N/N 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 ET-001 N/A 067AK1.o1 .9 h.9 3 1 IFIRE
ANSWERS: Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScrambleChoices
Points ci IDWKIBIIDA= Scramble Range: A
NEW NRC exam 2002 KEH 10/5/01
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
Friday, January 18, 2002 @ 06:52 AM 2kcom.bnk Page: 85
71. GT-001 002/ 53/ GET-001/ N/A/034A2.02/ 3.4/3.9/33 [1]/ FH
Given the following plant conditions:
Bringing new fuel storage cask into the spent fuel building.
While lifting the shipping cask off the truck, the rigging breaks, the cask drops onto the truck.
The first cask knocks another cask off the truck and both cask are laying on the ground. Both
cask are severely dented
Health Physics takes gamma radiation readings:
15 mrem/hr on contact with the dropped casks.
3 mrem/hr at 1 meter from each cask.
2 mrem/hr general background reading.
Which of the following would be the proper posting for this general area?
,A. Radiation Controlled Area.
B. Radiation Area.
D. Locked High Radiation Area.
A. CORRECT: General area for radiological protection for all workers, requires an RWP and
dosimetry.
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.
NEW NRC exam 2002 KEH 10/5/01
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Import. SRO Import Initial/Re System
153 LGET-O01 IN/A 134A2.02 b.4 1.9 b3 1] 1FH
ANSWERS: Version Answers:
01234567 8 9 LN Scramble Choices
IIB ClDI I4
5l
Points= ý Scramble Range: A- d