ML072980405
| ML072980405 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/09/2007 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-327/07-301, 50-328/07-301 50-327/07-301, 50-328/07-301 | |
| Download: ML072980405 (100) | |
See also: IR 05000327/2007301
Text
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QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Emergency Procedures I Plan Knowledge of annunciators alarms and indications, and use of the respon se instructions. LOOP
KiA justification: applies since the applicant is required to discriminate between a loss of off-site power to the eSST-Start Buss-Unit
board actuating the common alarm (1-AR-M1-B, B-3) vs. lock-out actuation from a Unit Board fault (87- 1C relay actuation of the 86-1C
jock-out relay).
Question No.
Tier 1 Group 1
Importance Rating:
Technical Referen ce:
49
R03.3
AR-M1B, B-3
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPL271AOP-P.01, B.7
New
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
41.7
Comments: editorial change to stem on location of 86 relay
(
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
NEW
HIGHER
412007
1.00
Version:
Answer:
o I 234 5 6 7 8 9
ADA BDBABCA
Source If Bank:
Difficulty:
Plant:
Last 2 NRC?:
Scramble Range : A - D
SEQUOYAH
NO
Monday, May 07, 2007 3:2 3:06 PM
100
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QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
51. 057 AK3 .01001
Given the following plant conditions:
-
Unit 1 is at 100% RTP.
-
A loss of 120V AC Vital Instrument Power Board 1-IV occurs.
-
A reactor trip does NOT occur.
Which ONE (1) of the following describes the actions required and the reason for the
actions in accordance with AOP-P.03, Loss of Unit 1 Vital Instrument Power Board?
A:" Place rod control in MANUAL due to loss of Auctionee red Tavg input; Control #4
Feedwater Reg Valve manua lly due to loss of AUTO control.
B. Place rod control in MANUAL due to loss of Auctioneered Tavg input; Control #2
Feedwater Reg Valve manually due to loss of AUTO control.
C. Place rod control in MANUAL due to loss of Tref input; Control #4 Feedwater Reg
Valve manually due to loss of AUTO control.
D. Place rod control in MANUAL due to loss of Tref input; Control #2 Feedwater Reg
Valve manually due to loss of AUTO control.
A. Correct. Loss of Auctioneeered Tavg would cause rod motion, so rods are placed in
Manual. #4 FRV is also operated manually due to loss of control
B. Incorrect.
Wrong FRV
C. Incorrect. Tref comes from board 1-1. Would be cause to place rods in manual, but
Tref input is not lost. Correct FRV
D. Incorrect. Tref and #2 FRVare both incorrect for loss of board 1-IV
Monday, May 07, 20073:23:06 PM
101
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Know1edge of the reasons forthe following responses as theyapplyto theLoss of Vital AC Instrument Bus: Actions contained in EOP
forlossofvital ac electrical instrument bus
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Question No.
Tier 1 Group 1
Importance Rating:
Technical Reference :
50
R04.1
AOP P.03
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPL271AOP-P.03 & 04, B.3
New
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
41 .7
Comments: corrected typo in stem.
(
(
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
NEW
HIGHER
4/2007
1.00
Version:
Answer:
o I 2 3 4 5 6 7 8 9
A D DC B A B B B D
Source If Bank:
Difficulty:
Plant:
Last2 NRC?:
Scramble Range: A - D
SEQUOYAH
NO
Monday, May 07, 20073:23:06 PM
102
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
52. 058 AAl.Ol 001
(
Given the following plant conditions:
-
Unit 1 is steady-state at 100% power.
-
Unit 2 is in Mode 6 with vessel upper internals removal in progress.
-
125V DC Vital Battery IV Output Breaker tripped and can't be reclosed.
Which ONE (1) of the following describes the required action(s) in accordance with
AOP-P.02, Loss of 125V DC Vital Battery Board?
A. Align 125V DC Vital Battery Bank V and Charger 1-S (spare) to Vital Battery Board
IV.
B~ Align 125V DC Vital Battery Bank V and Charger 2-5 (spare) to Vital Battery Board
IV.
C. Suspend core alterations on Unit 2 until 125V DC Channel IV is returned to
OPERABLE status.
D. Restore 125V DC Channel IV to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or initiate a
shutdown of Unit 1.
A. Incorrect. Not capable of being aligned.
B. Correct. per 0-SO-250-1
C. Incorrect. No TS requirement.
D. Incorrect. Wrong time requirement per TS.
(
Monday, May 07, 2007 3:23:06 PM
103
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability to operate andl or monitorthefollO'Ning as theyapplyto the Loss of DC Power:Cross-tie of theaffected de bus with thealternate
supply
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Question No.
Tier 1 Group 1
Importance Rating:
Technical Reference:
51
RO 3.4
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPL271AOP-P.02, B.8.b
Bank
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
41.10
Comments: editorial change to D (one hour) based on NRC comment.
(
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
BANK
III GHER
4/2007
1.00
Version:
0 I 2 3 4 5 6 7 8 9
Answer:
B A CAB D D D A A
Scramble Range: A - D
Source If Bank:
SQN BANK
Difficulty:
Plant:
SEQUOYAll
Last 2 NRC?:
Monday, May 07. 20073:23:06 PM
104
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c.
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
53. 058 AAl.02 00 1
Given the following plant conditions:
- Unit 1 is in Mode 3.
- The following alarms are received in the control room:
- AR-M-01-C, B4, 125V DC VITAL CHGR II FAILURE OR VITAL BAT II
DISCHARGE.
- AR-M-01-C, B5, 125V DC VITAL BAT BD II ABNORMAL.
- Battery Board II Voltage indicates 119 VDC and lowering slowly.
- Battery Charger 11 DC Output Breaker is tripped open.
- Reports from the AUO are that Battery Board II appears normal with the exception
of the Charger Output Breaker trip
Which ONE (1) of the following describes the operability of the Battery Board, and the
action required?
A':" Declare Battery Board 11 INOPERABLE. Align the Spare Charger in accorda nce
with 0-SO-250-1, 125 Volt dc Vital Battery Boards.
B. Declare Battery Board II INOPERABLE. Reduce Battery loading as necessary in
accordance with 0-SO-250-1 , 125 Volt dc Vital Battery Boards.
C. Battery Board II remains OPERABLE. Align the Spare Charger in accordance with
0-SO-250-1 , 125 Volt dc Vital Battery Boards.
D. Battery Board 11 remains OPERABLE. Reduce Battery loading as necessary in
accordance with 0-SO-250-1 , 125 Volt dc Vital Battery Boards.
A is correct. Less than 125 VDC, Annunciator 84 and TS requires LCO entry
8 is incorrect because it is not inop due to charger disconnect.
C and 0 are incorrect because the battery is not operable. C contains correct action,
and 0 remains credible because the plant status and action taken do not eliminate
operability of the battery by themselves. If the battery is connected to the board, it may
be functioning, but it may not be operable (Low Volts)
Monday, May 07, 2007 3:23:07 PM
105
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVE N 5-7-07
Ability to determine and interpret the followingas theyapply to the Loss of DC Power: 125V de bus voltage, low/criticallow. alarm
(
Question No.
Tier 1 Group 1
Importance Rating:
Technical Reference:
81
SRO 3.6
AR-M-01C,
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPL271AOP-P.02, B.8.b & 9
New
l
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
43.5,43.2
Comments:
Time:
Points:
1.00
Version: o I 234 5 6 7 8 9
Answer: ADBCD AA CBB
Scramble Range: A - D
Source:
NEW
Source IfBank:
Cognitive Level:
IIlGHER
Difficulty:
Job Position:
Plant:
SEQUOYAH
Date:
4/2007
Last 2 NRC?:
NO
Monday, May 07.20073:23:07 PM
106
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
54. 059 AL07 001
Given the following plant conditions:
Unit 1 is at 100% power
-
All controls in automatic
-
All four main feedwater flows start increasing
-
All four steam generator levels trending upwards.
For information:
PT-1-33 is a Main steam header pressure transmitter
PT-3-1 is a Main feedwater header pressure transmitter
Which ONE (1) of the following identifies the two instrument failures that would cause
this transient? (consider each failure separately)
A.
B~
C.
D.
PT-1-33
failed LOW
failed HIGH
failed LOW
failed HIGH
PT-3-1
failed LOW.
failed LOW .
failed HIGH.
failed HIGH.
l
A.
PT-1-33 failing low would cause a high delta-P and the MFPT control
system would reduce MFPT speed causing low feed flow and
decreasing SG levels. The results of PT-3-1 failing low are described
in "B" below.
B.
Correct. Feedwater header pressure is normally higher than steam
header pressure by a programmed value of 80 psid at 0% totalized
steam flow and 195 psid at 100% totalized steam flow. PT-1-33 failing
high OR PT-3-1 failing low would indicate a lower than normal delta-P
between steam header pressure and FW header pressure. This
would cause the MFPT control system to increase speed in an attempt
to restore programmed delta-P. This increased delta-P would
increase FW flow and cause SG level to trend upward. The FW
regulating valves would be closing in an attempt to reduce SG level
back to programmed value.
C.
The results of PT-1-33 failing high are described in "B" above. PT-3-1
failing high would cause a high delta-P and the MFPT control system
would reduce MFPT speed causing low feed flow and decreasing SG
levels.
D.
PT-1-33 failing low would cause a high delta-P and the MFPT control system
would reduce MFPT speed causing low feed flow and decreasing SG levels.
PT-3-1 failing high would cause a high delta-P and the MFPT control system
would reduce MFPT speed causing low feed flow and decreasing SG levels.
Monday. May 07. 2007 3:23:07 PM
107
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability to predict and/or monitorchangesin parameters(to prevent exceeding design limits) associated with operatingtheMFW ccotrols
including: Feed Pump speed, including normal control speed for ICS.
(
Question No.
Tier 2 Group 1
Importance Rating:
Technical Reference:
18
R02.5
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPT200.MFW, 8.5
Question Source:
Bank
Question History:
SQN FW-B.5-1
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
41.7,41.4
Comments: editorial change to answers to put in two column format. combined second two
bullets into one statement.
SEQUOYAH
NO
(
(
Time:
Source:
Cognitive Level:
Job Position:
Dale:
Points:
BANK
HIGHER
412007
1.00
Version:
Answer:
o I 2 3 4 5 6 7 8 9
B DA B B C C D C C
Scramble Range: A - D
Source If Bank:
SEQUOYAH BANK
Difficuhy:
Plant:
Last 2 NRC'!:
Monday, May 07, 20073:23:07 PM
108
(
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
55. 059 AK 1.02 001
Given the following plant conditions:
-
An accidental spill of the Monitor Tank has occurred in the Aux Building.
Radiation levels in the area of the spill are 40 mRem per hour at 30 em.
Contamination levels on the floor around the tank are 1.2E4 DPM/100 cm2.
Which ONE (1) of the following describes how the area will be posted?
A'! Radiation Area AND Contamination Area
B. High Radiation Area AND Contamination Area
C. Radiation Area AND High Contamination Area
D. High Radiation Area AND High Contamination Area
A. Correct. This area should be posted as a radiation area >5 mrem and <100
mrem/hr) and a contamination area (>1000 dpm/100 cm2). RC/-15 Sects 6.7&
6.12.
B. Incorrect. Greater than 100 mrem/ hr is a high radiation area. RC/-15 Sect 6.8 &
6.12.
C. Incorrect. Greater than 50,000 dpm/100 cm2 is a high contamination area. RC/-15
Sects 6.7& 6.13.
D. Incorrect. Greater than 100 mrem/ hr is a high radiation area. Greater than 50,000
dpm/100 cm2 is a high contamination area. RC/-15 Sects 6.8 & 6.13.
Monday, May 07,20073:23:07 PM
109
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledge of theoperational implications of thefollo.vingconceptsas they apply toAccidental LiquidRa<twaste Release: Biological
effects on humans of various types of radiation, exposure levels that are acceptable for nuclearpower plant personnel, and the units
usedforradiation-intensitymeasurements and forradiation exposure levels
Question No.
Tier 1 Group 2
Importance Rating:
Technical Reference:
60
R02.6
SPP-5.1: RCI-15, Sects 6,7, 6.8, 6.12 & 6.13
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
RWT-010,
New
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
41.12
Comments: removed second part of each answer based on NRC comment
(
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
NEW
HIGHER
4/2007
1.00
Version:
Answer.
o I 2 3 4 5 6 7 8 9
ABD CDADC BC
Source If Bank:
Difficu lty:
Plant:
Last 2 NRC?:
Scramble Range: A - 0
SEQUOYAH
NO
Monday, May 07,20073:23:07 PM
110
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
56. 060 AKLOI 001
Which ONE (1) of the following describes a potential monitored location for airborne
effluents of gaseous waste and the correct unit of measurement for the effluent?
A.
B:'
C.
D.
Monitored Location
Turbine Building Vent
Service Building Vent
Turbine Building Vent
Service Building Vent
Unit of Measurement
counts per minute
counts per minute
mRem per hour
mRem per hour
(
A. Incorrect.
Turbine building ventilation exhaust path is a vent path but is not monitored
since there is little/no potential of rad release occcuring via this path.
B. Correct. Service Bldg el. 718 in mechanical equipment room. Scintillation type detector
with an 8 point sampling probe.
While the detector is primarily monitoring for Beta,
Gamma would also be detected. Possible sources of contaminants in the vent system are
exhaust from the radiochemical lab, titration room, counting room, and decontamination
rooms. Read-out is in 'CPM'.
C. Incorrect. Not a monitored vent path
D. Incorrect. Measured in CPM, but is a monitored vent path.
Monday. May 07, 2007 3:23:07 PM
111
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledgeof the operationalimplications of the followingconcepts as they apply to Accidental Gaseous Radwaste Release:Typesof
radiation, their units of intensity,and the location of sources of radiation ina nuclear power plant
(
Question No.
Tier 1 Group 2
Importance Rating:
Technical Reference :
61
R02.5
O-AR-M12-B, A-5/A-6; ODCM, Section 1.1.2 requirements; U1
PEDs- REP RM-Effluents pg; 1,2-47610-90-1A
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPT200.RM, Obj 4
Question Source:
Modified
Question History:
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
41 .13
Comments: modified question based on NRC comment.
(
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
MODIFIED
LOWER
4/2007
1.00
Version:
Answer:
o I 234 5 6 7 8 9
BAAADB CDAB
Source If Bank:
Difficulty:
Plant:
Last 2 NRC?:
Scramble Range: A- D
SEQUOYAH
NO
Monday, May 07, 2007 3:23:07 PM
112
(
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
57. 061 K6.02 001
Given the following plant conditions:
Unit 2 is in Mode 1.
-
The TDAFW Pump is tagged out of service.
-
A Loss of Feedwater causes a reactor trip.
-
Coincident with the trip, 2B-B Shutdown Board Bd Differential trip actuates.
Which ONE (1) of the following describes the Auxiliary Feedwater alignment and
approximate flow rates?
A':' 1 and 2 SGs being fed at 220 GPM each
B. 1 and 2 SGs being fed at 440 GPM each
C. ALL SGs being fed at 110 GPM each
D. ALL SGs being fed at 220 GPM each
A. Correct. Loss of 2B-B SO Board, Only A MDAFW Pump is available. Capacity is
440 GPM, and it is aligned to automatically feed 1 and 2 SGs. Distractors are for
TDAFW capacity and flow alignments
B. Incorrect. Capacity of TDAFW aligned to 2 SGs
C. Incorrect. MDAFW would be aligned to 2 SGs, not all 4 SGs
D. Incorrect. This would be the alignemnt if the TDAFW Pump was the only operating
pump
Monday, May 07, 2007 3:23:07 PM
113
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
KnO'N1edgeof theeffect of a loss or malfunction of the following will haveen theAFW components: Pumps
(
Question No.
Tier 2 Group 1
Importance Rating:
Technical Reference:
19
R02.6
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPT200.AFW, B.5.d
Question Source:
Bank
.Question History:
WTSI Bank
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
41 .7,41 .8
Comments: Modified question to add approximately to each answer.
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
BANK
HIGHER
4/2007
1.00
Version:
0 1 2 3 4 5 6 7 8 9
Answer:
A B B D C D C B C C
Scramble Range: A * D
Source If Bank:
WTSI
Difficulty:
Plant:
SEQUOYAl l
Last 2 NRC?:
Monday, May 07,20073:23:07 PM
114
l
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
58. 062 AK3.01 001
Given the following plant conditions:
Unit 1 is tripped.
-
The crew is performing actions of AOP-M.01 , Loss of Essential Raw Cooling
Water.
ERCW Supply Header 2B to the Aux Building and 0-FCV-67-152, CCS
OB1/0B2 Discharge Valve to header B, have been isolated to stop the leak.
-
A Safety Injection signal is subsequently received.
Which ONE (1) of the following describes the position of 0-FCV-67-152 for these
cond itions, and status of flow through the OB1/0B2 CCS Heat Exchanger?
A. The valve will open to its 35% open position. ERCW flow will be provided from
Header 1B.
B~ The valve will open to its 35% open position. NO ERCW flow will be provided .
C. The valve will open to its 50% open position. NO ERCW flow will be provided.
D. The valve will open to its 50% open position. ERCW flow will be provided from
Header 1B.
A. Incorrect. Since ERCW was manually isolated, no flow will be available
B. Correct. Valves open to Position A (35%)
C. Incorrect. The valves will not open to 50% position. Applicant may confuse with
actions in EA-67-1, ERCWoperation, which will manually align valve to 50%.
D. Incorrect. The valves will not open to 50% position. No flow will be provided under
given conditions.
Monday, May 07, 2007 3:23:07 PM
115
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledge of the reasons forthe following responses as theyapply totheLoss of NuclearService Water The conditions thatwill initiate
the automatic opening andclosingof the SWS isolationvalves to the nuclear service water coolers
(
Question No.
Tier 1 Group 1
Importance Rating:
Technical Reference:
52
R0 3.2
AOP-M.01 , section 2.4 step 8
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPL271AOP-M.01, B.8.c
New
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
41.8
Comments:
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
NEW
HIGHER
4/2007
1.00
Version:
Answer:
o I 23 4 5 6 7 8 9
B DAC BACA B D
Source If Bank:
Difficulty:
Plant:
Last 2 NRC?:
Scramble Range: A - D
SEQUOYAl I
NO
Monday, May 07, 2007 3:23:07 PM
116
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
59 . 062 0 2.1.10 001
Which ONE (1) of the following describes the MINIMUM Mode 5 requirements for
operability of the AC Distribution system for Unit 1?
A':" Vital Instrument Power Boards 1-1, 1-111operable.
B. Vital Instrument Power Boards 1-1, 2-1,1-111, 2-111 operable.
C. Vital Instrument Power Boards 1-1 , 1-IV operable.
D. Vital Instrument Power Boards 1-1, 1- 11,2-1, 2-11 operable.
A. Correct
B. Incorrect. would be correct for both units
C. Incorrect. Minimum but wrong train.
D. Incorrect. question asks for minimum
Conductof Operations: Knowledgeof conditions and limitations in thefacility license.
Question Number:
Tier 2 Group 1
Importance Rating:
Technical Reference:
20
2.7
Proposed references to be provided to applicants during examination:
None
Learning Objective:
10 CFR Part 55 Content:
43.2
Comments:
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
BANK
LOWER
4/2007
1.00
Version:
Answer:
o I 234 5 6 7 8 9
AC D BA DBDCB
Source If Bank:
Difficulty:
Plant:
Last 2 NRC?:
Scramble Range: A - D
SEQUOYAH
NO
Monday, May 07, 2007 3:23:08 PM
117
(
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
60. 063 G2.2.22 00 I
Given the following plant conditions:
-
Unit 2 is operating steady-state at 100% power
-
All systems are normally aligned
Which ONE (1) of the following would result in the unit being in the action of Tech
Spec LCO 3.8.2.3, DC Distribution, at the conclusion of the alignment?
A. Battery Bank V is aligned to replace Vital Battery II supply to Vital Battery Board II.
Bt Battery Charger V is aligned to replace Charger III supply to Vital Battery Board III.
C. The Spare Vital Battery Charger 1-S is aligned to 480V Shutdown Board 1B1-B
while supplying Vital Battery Board II.
D. The Spare Vital Battery Charger 2-S is aligned to 480V Shutdown Board 2A2-A
while supplying Vital Battery Board III.
A. Incorrect. Battery Bank Vmay be substituted for any other bank
B. Correct. Charger Vis not allowed in Tech Specs to replace the normal charger.
C. Incorrect. This is an acceptable TS configuration, does not violate any TS
requirements for alignment
D. Incorrect. This is an acceptable TS configuration, does not violate any TS
requirements for alignment
Monday, May 07, 2007 3:23:08 PM
118
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
EquipmentControl Knawledge of limiting conditions foroperations andsafetylimits..
(
Question No.
Tier 2 Group 1
Importance Rating:
Technical Reference:
21
RO 3.4
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPT200.DC, B.6
Bank
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
43.2
Comments: Modified B to align vitai charger V to the vital battery board which is not ailowed
by
SEQUOYAlI
NO
(
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points :
BANK
LOWER
4/2007
1.00
Version:
Answer:
o I 23 4 567 8 9
B B B DAD B A CA
Scramble Range: A - D
Source IfBank:
SQN BANK
Difficulty:
Plant:
Last 2 NRC?:
Monday. May 07, 2007 3:23:08 PM
119
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
61. 064 K4.01 DOl
Diesel Generator 1A-A has been started by the manual emergency start switch on the
M-1 panel.
Which ONE (1) of the following conditions I actions will stop Diesel Generator 1A-A?
A. Low lube oil pressure
B. High jacket water temperature
C. Actuation of the generator reverse power relay
D~ Actuation of the generator differential relay
a.
Incorrect because only the differential and overspeed protection is available
fol/owing manual emergency start from M-1 panels. Low lube Oil trip is disabled
b. Incorrect because only the differential and overspeed protection is available
following manual emergency start from M-1 panels. High Jacket Water temp trip
is disabled
c. Incorrect because only the differential and overspeed protection is available
fol/owing manual emergency start from M-1 panels. Reverse power trip is
disabled
d. Correct because only the differential and overspeed protection is available
following manual emergency start from M-1 panels.
Monday. May 07. 2007 3:23:08 PM
120
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledgeof ED/G systemdesign feature(s) and/or i n ter~lock(s) whichprovide for thefollO'Ning: Trips 'While loading the EDfG
(frequency, 'IOltage, speed).
(
Question No,
Tier 2 Group 1
Importance Rating:
Technical Reference:
22
R0 3.8
OPT200DG
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPL200DG Obj 4.i
Question Source:
Bank
Question History:
SQN Bank
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
41,7
Comments: Corrected typo in D
SEQUOYAH
NO
(
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
BANK
LOWER
4/2007
1.00
Version:
Answer:
o I 2 34 5 6 7 8 9
Scramble Range: A - D
Source If Bank:
SQN BANK
Difficulty:
Plant:
LasI 2 NRC?:
Monday, May 07, 2007 3:23:08 PM
121
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
62. 068 AA2.02 001
Given the following plant conditions:
Unit 1 is at 100%.
-
A fire is in prog ress in the Control Building Cable Spreading Room.
-
The Fire Brigade is on the scene and has requested backup assistance.
W hich ONE (1) of the following describes the correct procedure to be entered, and
how RCS boration will be monitored throughout the RCS cooldown after the reactor is
tripped?
A'! Enter AOP-N.01, Plant Fires.
Initiate and monitor boration to cold shutdown cond itions in accordance with
AOP-C.04, Shutdown From Auxiliary Control Room.
B. Enter AOP-N .08, Appendix R Fire Safe Shutdown.
Initiate and monitor boration to cold shutdown conditions in accordance with
AOP-C.04, Shutdown From Auxiliary Control Room.
C. Enter AOP-N.01 , Plant Fires.
Initiate and monitor boration in accordance with 0-GO-7, Plant Cooldown from Hot
Standby to Cold Shutdown.
D. Enter AOP-N.08, Appendix R Fire Safe Shutdown.
Initiate and monitor boration in accordance with 0-GO-7, Plant Cooldown from Hot
Standby to Cold Shutdown.
A. Correct.
AOP-N.01 will be entered for plant fires, and crew will transition to
AOP-C.04 at step 21.d since the fire is in the control building.
B. Incorrect. Initial procedure entry is incorrect. AOP C.04 will be entered
C. Incorrect. AOP C.04 will direct the trip. Boration will be done in accordance with the
AOP vs the GO. If conditions of the fire did not affect the unit and the
conditions required plant shutdown then the boration of the RCS would
be conducted in accordance with GO-7.
D. Incorrect. Initial procedure entry is incorrect and AOP C.04 will control boration
Monday, May 07, 2007 3:23:08 PM
122
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability todetermine andInterpretthefollowing as theyapply to theControl Room Evacuation: Local boric acidflow
(
Question No.
82
Tier 1 Group 2
Importance Rating:
SR04.2
Technical Reference :
AOPs N.01, N.08, C.04
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPL271AOP N.01 B.6
Question Source:
New
Question History:
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
43.5
Scramble Range: A- D
SEQUOYAH
NO
o 1 23 4 5 6 7 8 9
ADAAD BADAA
Source If Bank:
Difficulty:
Plant:
Last 2 NRC?:
Removed indication from Aux Control Room in A and
Version:
Answer:
1.00
Points:
NEW
IIIOIlER
4/2007
Source:
Cognitive Level:
Job Position:
Date:
Comments: corrected typo In C and D.
B.
Time:
(
Monday. May 07,20073:23:08 PM
123
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
63. 068 AK2.02 001
(
Given the following plant conditions:
-
Unit 1 is at 100% RTP when a fire occurs in the cable spreading room.
-
Due to the large amount of smoke in the main control room, it is decided by the
Shift Manager that the main control room must be abandoned.
Which ONE (1) of the following responses below describes the proper operating crew
actions for the given conditions?
A. Prior to evacuation, trip the reactor in the Main Control Room and perform post trip
actions in accordance with E-O, Reactor Trip or Safety Injection.
B~ Prior to evacuation, trip the reactor in the Main Control Room and dispatch
personnel to perform applicable sections of AOP-C.04, Shutdown From Auxiliary
Control Room, Appendix Z.
C. Evacuate the Main Control Room, then trip the reactor from the Auxiliary Control
Room after the Auxiliary Control Room is manned and perform perform post trip
actions in accordance with E-O, Reactor Trip or Safety Injection.
D. Evacuate the Main Control Room, then trip the reactor from the Auxiliary Control
Room after the Auxiliary Control Room is manned and dispatch personnel to
perform applicable sections of AOP-C.04, Shutdown From Auxiliary Control Room,
Appendi x Z.
'----
-:; ~--;---~:-=;;-:;;-;:-;-
-=------;:,.----,--,------;:-
-
-
;:,---------'
A. Incorrect. AOP-C.04 Sect. 2.1, Step 1 Note: "EOPs are NOT applicable when evacuating
the MCR." Therefore, carrying out E-O post trip actions is not the correct procedural action
path to expediously evacuate the MCR.
B. Correct. AOP-G.04, Section 2.1 steps 1&3- ENSURE the reactor is TRIPPED &
DISPA TCH CRO with ...Appendix Z...Ensure personnel dispatched...
C. Incorrect. See A; EOPs are not applicable when evacuating MeR
D. Incorrect. AOP-G.04 does not contain adequate instructions for initiating reactor trip from
outside the MCR nor does the ACR contain/provide adequate controls to perform this.
Dispatching personnel per Appendix Z is correct.
Monday, May 07, 2007 3:23:08 PM
124
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowtedgeof theInterrelations between the Control Room Evacuationandthe following: Reactor trip system
(
Question No.
Tier 1 Group 2
Importance Rating:
Technical Reference:
62
R03.7
AOP C.04
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPL271AOP-C.04, B.6
Question Source:
Bank
Question History:
SQN Bank
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
41.10
Comments : Editorial change to D wording to be similar to wording in the AOP.
SEQUOYAlI
NO
(
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
BANK
LOWER
412007
1.00
Version:
Answer:
o I 2 3 4 5 6 7 8 9
B B B A C AAA B D
Scramble Range: A - D
Source If Bank:
SQN BANK
Difficulty:
Plant:
Last 2 NRC? :
Monday, May 07,20073:23:08 PM
125
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
64 . 071 K3.04 00 1;-:c_.,----------;,--;--_~------------------~--,
(
Given the following plant conditions:
- A Gas Decay tank release is in progress with A- A ABGTS running for dilution
flow.
- A leak occurs on the waste gas compressor which results in a gas release to the
Auxiliary Building.
- 0-RE-90-101, Auxiliary Building Vent Monitor, is in alarm.
Which ONE (1) of the following indicates the effect this leak will have on the plant?
(Assume no operator actions)
A. Gas Decay Tank release will be terminated; ONLY A-A ABGTS will be running.
B. Gas Decay Tank release will be terminated; BOTH A-A and B-B ABGTS will be
running.
C. Gas Decay Tank release will continue; ONLY A-A ABGTS will be running.
D~ Gas Decay Tank release will continue; BOTH A-A and B-B ABGTS will be running.
A. Incorrect. Applicant may believe that Aux Bldg high radiation will terminate gas release,
but it would be terminated only by O-RE- 90-118 Rad Monitor in release discharge piping
to the Shield Bldg. Applicant may think that only the A-A ABGTS will receive a start signal
since the gas release is out the U-1 Shield Building and the A-A ABGTS is the U-1 fan.
B. Incorrect. Applicant may believe that Aux Bldg high radiation will terminate gas release,
but it would be terminated only by O-RE- 90-118 Rad Monitor in release discharge piping
to the Shield Bldg. Correct portion is that both ABGTS fans will start on an ABI.
C. Incorrect. Applicant should know the waste gas release will continue since it discharges
to the Shield Bldg vent via O-RE- 90-118 Rad Monitor in release discharge piping.
D. Correct - Waste gas release continues since RE-90-118 Rad Monitor would terminate
only if high radiation in release discharge piping to the Shield Bldg is detected. ABGTS
will continue to run- no interface from the AB area rad monitors.
Monday. May 07, 2007 3:23:08 PM
126
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knavvle::lge of theeffectthata loss ormalfunction of theWasteGas Disposal System will haveon the following: VenUlation system.
(
Question No.
Tier 2 Group 2
Importance Rating:
Technical Reference:
35
R02.7
0-50-77-15, Section 6.0 Step9 and NOTE; 47W611-77-4;
47W611 -30-6
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPT200.GRW, Obj. so, ge, 9h
Question Source:
Bank
Question History:
SQN Bank
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
41.7
Comments: editorial change to stem wording
(
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
BANK
LOWER
412007
1.00
Version:
0 I 2 3 4 5 6 7 8 9
Answer:
D A B C A A D D D B
Scramble Range: A - D
Source If Bank:
SQN BANK
Difficulty:
Plant:
SEQUOYAH
Last 2 NRC? :
NO
Monday, May 07, 2007 3:23:08 PM
127
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
65. 073 AZ.Ol 001
Given the following plant conditions:
-
Unit 1 is at 100% RTP.
-
Alarm "1-RA-120B/12 1B STM GEN BLDN L1Q SAMP MON INSTR MALFUNC"
annunciates.
Which ONE (1) of the following describes the cause of the alarm and the mitigating
actions that the crew should implement?
Cause
A. Loss of power to the
radiation monitor
B~ Loss of power to the
radiation monitor
C. High flow through the radiation
monitor
D. High flow through the
radiation monitor
Mitigating Action
Manually terminate S /G blowdown release.
(there is no automatic termination)
Verify automatic termination of
S/G blowdown release.
Verify automatic termination of
S/G blowdown release.
Manually terminate S /G blowdown release.
(there is no automatic termination)
(
A. Incorrect. S/G blowdown should automatically isolate. If it fails to isolate the
operator would manually isolate.
B. Correct. High radiation or instrument malfunction would auto isolate S/G blowdown.
C. Incorrect. A low flow would cause the alarm; not high flow. Applicant may confuse
with RM90-119 which does give a malfunction alarm on high flow.
D. Incorrect. A low flow would cause the alarm; not high flow. S/G blowdown should
automatically isolate. If it fails to isolate the operator would manually isolate.
Monday. May 07, 2007 3:23:09 PM
128
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability to (a) predict theimpacts of the following malfunctionsoroperations onthe PRM system: and(b) based onthose predictions, use
procedures to correct, control, or mitigatethe consequences of those matfunctions oroperations: Erraticor failedpower supply.
(
Question No.
Tier 2 Group 1
Importance Rating:
Technical Reference:
24
R0 2.5
O-AR-M12A
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPT200.RM, 8.5
Question Source:
Bank
Question History:
SQN Bank
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
41.11
Comments:
SEQUOYAH
NO
(
Time:
Source:
Cogni tive Level:
Job Position:
Date:
Points:
BANK
LOWER
4/2007
1.00
Version:
Answer:
o 1 23 4 5 678 9
B B D B A B C B B D
Scramble Range: A - D
Source If Bank:
SQN BANK
Difficulty:
Planl:
Last 2 NRC? :
Monday, May 07, 2007 3:23:09 PM
129
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
66. 073 K 5.01 001
Which ONE (1) of the following describes the type of radiation detector used by the
Condenser Vacuum Exhaust Radiation Monitor 1-RM-90-119, and whether condenser
vacuum exhaust stack backpressure affects sample flow for 1-RM-90-119?
A. Scintillation detector. Backpressure does not affect the sample flow.
B~ Scintillation detector. Backpressure does affect the sample flow.
C. Geiger-Mueller detector. Backpressure does not affect the sample flow.
D. Geiger-Mueller detector. Backpressure does affect the sample flow.
A.
Incorrect. Correct detector type. Plausible, applicant may believe that since RE-90-119
has its own sample pump, adequate sample flow to/from the rad monitor could be
independent of back pressure effects; see B below.
B. Correct. Process rad monitors use scintillation detector type; primarily monitors for Beta;
any Gamma would also be detected. O-AR-M12-A, C-2 Step 2 Note states that high
condenser backpressure in the CVP exhaust stack can cause low flow through monitor
resulting in 1-RM-90-119 instrument malfunction alarms.
C. Incorrect. Wrong detector type. Plausible, applicant may believe that since RE-90-119
has its own sample pump, adequate sample flow to/from the rad monitor could be
independent of condenser back pressure effects; see B below.
D. Incorrect. Wrong detector type; correct effect, see B above.
Radiation monitor indication is a function ofactivity level and sample flowrate past the detector
for process side-stream rad monitors. If flow is reduced and/or isolated, detector indication will
be low.
Area Rad monitors use G-M detectors
Monday, May 07, 2007 3:23:09 PM
130
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledge of the operational implications of the tollONing concepts as they apply to the PRM system: Radiation theory, including
sources. types. units. andeffects.
(
Question No.
Tier 2 Group 1
Importance Rating:
Technical Reference:
23
R0 2.5
0-AR-M12-A, C-2; OPT200.RM, Slide 69 /70
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPT200.RM, B.4
New, 2007 ILT NRC Exam
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
41.11
SEQUOYAH
NO
Scramble Range: A - D
(
Comments:
Time:
Source:
Cognit ive Level:
Job Position:
Date:
Points:
NEW
LOWER
4/2007
1.00
Version:
Answer:
a I 2 3 4 567 8 9 .
BADADDD D C A
Source If Bank:
Difficulty:
Plant:
Last 2 NRC?:
Monday, May 07,20073:23:09 PM
131
(
(
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
67. 074 EAl.08 001
Given the following plant conditions:
-
The crew is responding to a LOCA.
RCS pressure is 400 psig.
-
Containment pressure is 7.5 psig.
Due to equipment failures, the crew has entered FR-C.1, Response to
Inadequate Core Cooling.
Which ONE (1) of the following methods is the highest priority in restoring the Core
Cooling CSF?
A. Depressurize the RCS by venting to Containment.
B. Initiate RHR flow to provide maximum cooling flow.
C. Rapidly depressurize the secondary to facilitate RCS depressurization.
D~ Start available CCP and SI pumps and align ECCS valves as necessary.
A. Incorrect. Depressurizing the RCS to Cntmt is a last resort.
B. Incorrect. RHR flow would be established after significant depressurization has
occurred. This would not be the primary plan to establish core cooling
C. Incorrect. Would perform once it was determined that HPI is unavailable
D. Correct. Top priority is to establish HPI if possible, although HPI failure most likely
led to entry to this procedure
Monday, May 07, 20073:23:09 PM
132
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Abilityto operate and monitorthe follO'Ning as they apply to a Inadequate Core Cooling: HPI System
Question No.
Tier 1 Group 2
Importance Rating:
Technical Reference:
63
R04.2
FR-C.1
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPL271FR-C.1, B.3
Question Source:
Bank
Question History:
SQN Bank
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
41.10
Comments:
(
Time:
Source:
Cognitive Level:
Job Position:
Date;
Points:
BANK
LOWER
4/2007
1.00
Version:
0 I 2 3 4 5 6 7 8 9
Answer:
Scramble Range: A - D
Source If Bank:
SQN BANK
Difficulty:
Plant:
SEQUOYAH
Last 2 NRC'!:
NO
Monday, May 07, 2007 3:23:09 PM
133
(
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
68. 075 G2.J.23 001
Given the following plant conditions:
Unit 1 is in Mode 3.
Condenser vacuum is being established.
The crew is starting up the CCW system in accordance with 0-SO-27-1 ,
Condenser Circulating Water System.
Wh ich ONE (1) of the following describes the required sequence of actions to start the
FIRST CCW Pump in accordance with 0-SO-27-1?
A. 1-Verify Discharge valve 5% open
2-Place Control switch in START
3-Verify discharge valve travels full open
B~ 1-Verify discharge valve is closed
2-Place Control switch in START
3-STOP Discharge valve travel at 25% open
C. 1-Verify discharge valve is closed
2-Place Control switch in START
3-Verify Discharge valve travels full open
D. 1-Verify discharge valve is 5% open
2-Place Control switch in START
3-STOP Discharge valve travel at 25% open
A. Incorrect. Incorrect order; plausible because operators are taught to start centrifigual
pumps with some limited flow, other centrifugal pumps have a preset bypass/discharge
valve feature like this. Since the CCWPp motor is a synchronous motor started as an
induction motor with excitation being applied as the motor approaches rated speed,
excitation, therefore power factor, is adjusted to bring the CCW Motor to synchronous
rated speed. Discharge valve opening, is limited until this adjustment is completed.
B. Correct. 0-SO-27-1 Sect 5.4 Step 10.b. directs the operator to verify CCWPp discharge
valves closed; Step 10.c NOTE: CCW pump will start when discharge valve is
approximately 5% open; Step 10.c directs placing the appropriate pump handswitch to
'START'; Step 10.d directs the AUO at approximately 25% open, to stop CCWPp
discharge valve from further opening using the associated [local] pushbutton control.
C. Incorrect. Plausible because other centrifugal pumps have a preset bypass and automatic
discharge valve opening feature actuated by placing the pump handswitch to start position.
D. Incorrect. Discharge valve at 5% open is plausible because operators are taught to start
centrifigual pumps with some limited flow [lack of knowledge of the start circuit]. Pump
start/discharge valve operating sequence is correct.
Sequence is from 0-SO-27-1and ensures a lower starting current on the pump motor, protects
against dead-heading and prevents short-circuiting backflow through an idle pump .
Monday, May 07, 20073:23:09 PM
134
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Conductof Operations: Abilityto perform specific system and integratedplant procedures during ell modes of plantoperation..
(
Question No.
Tier 2 Group 2
Importance Rating:
Technical Reference:
37
RO 3.9
0-SO-27-1
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPT200.CCW, B.4.g
New
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
41.10
Comments: Modified answers B and C to read similar to A and D. Modified step 1 of D to
read same as A.
(
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
NEW
LOWER
4/2007
1.00
Ve rsion:
Answer:
o 1 2 3 4 5 6 7 8 9
Source If Bank:
Difficulty:
Plant:
Last 2 NRC?:
Scramble Range: A * D
SEQUOYAH
NO
Monday, May 07, 2007 3:23:09 PM
135
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
69. 076 KI.l6 00 1
(
Given the following plant conditions:
One ERCW pump is running off of each Shutdown Board.
A Safety Injection occurs on Unit 1.
After the SI, a loss of off-site power occurs.
Whi ch ONE (1) of the following describes the preferred alignment of the ERCW pump
selector switches per 0-SO-67-1, Essential Raw Cooling Water, and which pumps will
be running after loads have sequenced on following the blackout?
Selector Switch Position
ERCW Pumps
M
Selected to the running pump
Pumps running prior to the
blackout will be running
B.
Selected to the non-running pump
Pumps NOT running prior to
blackout will be running
C.
Selected to the running pump
Pumps NOT running prior to
blackout will be running
D.
Selected to the non-running pump
Pumps running prior to the
blackout will be running
A. Correct. Four pumps would be selected for auto start, and those that are selected
will start.
B. Incorrect. Credible because the the non-running pumps can be selected, but this is
not the preferred alignment per 0-SO-67-1. If this were the case then this would be a
correct answer.
C. Inorrect. Credible because the the running pumps are selected, but the running
pumps would be running vs the non-running. Credible because the applicant may
believe that loss of header presure would result in backup pumps starting. Have to
consider that the sequence for blackout will be controlling pumps.
D. Incorrect. Credible because the the non-running pumps can be selected, Credible if
applicant confuses this with the start from an SI which indepent of the blackout signal.
Have to consider that the sequence for blackout will be controlling pumps.
Monday, May07, 2007 3:23:09 PM
136
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledge of thephysicalconnections and/or cause- effect relationships betweenthe SWS andthefollowing systems: ESF.
(
Question No.
25
Tier 2 Group 1
Importance Rating:
R0 3.6
Technical Reference:
0-50-67-1, OPT200.ERCW, Slides 21 & 22, 47W611-67-6,
Proposed references to be provided to applicants during examination:
None
Learning Objective :
OPT200 .ERCW, B.4.g
Question Source:
Bank
Question History:
SQN Bank
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
41.8
SEQUOYAH
NO
BANK
HIGHER
4/2007
Source:
Cognitive Level:
Job Position:
Date:
Comments: need to look at procedure. Has different names for the selector switch.
Time:
I
Points:
1.00
Version:
0 I 2 3 4 5 6 7 8 9
Answer:
A C B B B A AB C B
Scramble Range: A - D
Source If Bank:
SQN BANK
Difficulty:
Plant:
Last 2 NRC?:
(
Monday, May 07, 2007 3:23:09 PM
137
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
70. 078 G2.4.6 001
(
Given the following plant conditions:
Unit 1 is in MODE 3 following a shutdown.
-
A loss of Auxiliary Air occurred.
-
Auxiliary Feedwater was aligned as directed by AOP-M.02, "Loss Of
Control Air" to support current plant operations.
EA-3-4, "Local Alignment of TO AFW LCV Backup Air Supply" has been
implemented.
Which ONE (1) of the following describes the actions necessary to RESTORE
Auxiliary Feedwater normal and meet design basis requirements following the
restoration of the plant air systems?
A~ Using EA-3-4, Local Alignment of TO AFW LCV Backup Air Supply; isolate the
backup air supply and maintain bottle pressure at a minimum of 800 psig.
B. Using EA-3-4, Local Alignment of TO AFW LeV Backup Air Supply; isolate the
backup air supply and mainta in bottle pressure at a minimum of 1500 psig.
C. Using M.02, Loss of Control Air, Section 2.1 for Loss of Auxiliary Air; isolate the
backup air supply and maintain bottle pressure at a minimum of 800 psig .
O. Using M.02, Loss of Control Air, Section 2.1 for Loss of Auxiliary Air; isolate the
backup air supply and maintain bottle pressure at a minimum of 1500 psig.
A
is correct; EA-3-4, "Local Alignment of TO AFW LCV Backup Air Supply" Section
4.3.
B
is incorrect; correct procedure, but air pressure must be maintained >800 psig per
EA-3-4, credible since 1500 psig is the air pressure at which a Work Order is written
to change the bottle.
C
is incorrect; Wrong procedure usage, AOP-M.02 directs the operator to use EA-3-4,
align backup air supply. Correct minimum bottle pressure.
D
is incorrect; Wrong procedure usage. Incorrect bottle pressure.
Monday, May 07, 20073:23:09 PM
138
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Emergency Procedures f Plan Knowledge symptom based EO? mitigation strategies.
(
KA Match justification: Actions for a loss of essential air are lncluded in AOPs vs. EOPs. The actions would be the same
Question No.
Tier 2 Group 1
Importance Rating:
Technical Reference:
90
SRO 4.0
M.02, EA 3-4, TIS LCO 3.7.1.2
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPL271 C424, Obj. B.4
Question Source:
Bank
Question History:
Sequoyah AOP-M.02B2
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
41.10
SEQUOYAH
NO
(
Comments:
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
lJANK
LOWER
4/2007
1.00
Version:
Answer:
o 1 23 4 5 6 7 8 9
Scramble Range: A - D
Source ff Bank:
SEQUOYAH BANK
Difficulty :
Plant:
Last 2 NRC'!:
Monday, May 07, 2007 3:23:10 PM
139
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
71. 078 Kl.04 001
Given the following plant conditions:
Both units at 100% RTP.
-
Aux Air Compressor "A" is running.
-
Annunciator pane/1-XA-55-15B window C6 "LS-32-63 AUX AIR COMPR A LOW
OIL LVL HI AIR TEMP" is in alarm.
-
Auxiliary Building AUO reports a red indicating light for high discharge air
temperature for Aux Air Compressor "A".
Which ONE (1) of the following is the correct crew response in accordance with
1-AR-M15B, C6?
A. Verify Aux Air Compressor "A" automatically trips.
B. Verify Aux Air Compressor "A" is running unloaded.
C~ Verify proper cooling valve alignment from ERCW supply header 1A to the
compressor.
D. Verify proper cooling valve alignment from ERCW supply header 1A and 1B
cross-tie to the compressor.
A. Incorrect. High temperature is not an automatic trip. ARP only requires this action
for low oil level which is an automatic trip.
B. Incorrect. This is not a requirement in the ARP.
C. Correct. Cooling of the Aux air compressors is trained.
D. Incorrect. This would be correct for the A, B, C, and 0 air compressors, not the Aux
Air compressors.
Monday, May 07, 2007 3:23:10 PM
140
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledge of the physical connections and/or cause-effect relationships between the lAS andthe followingsystems: Coolingwaterto
compressor.
(
Question No.
26
Tier 2 Group 1
Importance Rating:
R02.6
Techn ical Reference:
1AR-M15-B, window C-6
Proposed references to be provided to applicants during examination:
None
Learning Objective :
OPT200.CSA, Obj 9.d
Question Source :
Bank
Question History:
SQN Bank
Question Cognitive Level :
Higher
10 CFR Part 55 Content:
41.10
Revised B to ensure answer
SEQUOYAH
NO
o 1 2 34 5 6 7 8 9
C DC C D A AAAD
Scramble Range: A - D
Source If Bank:
SQN BANK
Difficulty:
Plant:
Last 2 NRC?:
Version:
Answer:
1.00
Points:
BANK
LOWER
4/2007
Comments: Editorial modification to A based on NRC comments.
is incorrect.
Time:
Source:
Cognitive Level:
Job Position:
Date:
(
Monday, May 07,2007 3:23:10 PM
141
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
72. 086 A2.01 001
Given the following plant conditions:
A fire has occurred on the Main Transformer.
The Fire Brigade has extinguished the fire .
The High Pressure Fire Protection System is being restore d to normal in
accordance with 0-SO-26-1 and 0-SO-26-2.
An AUO is dispatched to the Fire Pump House to shut down the Fire Pump.
System Header pressure is 100 psig when the order to shut down Fire Pump is
given.
Wh ich ONE (1) of the following describes the impact of the Fire Pump shutdown?
A. The fire pump will not restart. HPFP tie to Potable Water will maintain system
pressure at the normal standby value without Fire Pump operation.
B. The fire pump will not restart. Jockey Pumps will operate to maintain system
pressure at the normal standby value without Fire Pump operation.
C~ The fire pump will restart. Determine where system flow demand is coming from,
and once corrected, attempt to shut down the Fire Pump again.
D. The fire pump will restart. Ensure the HPFP header is repressurized to 105 psig
prior to attempting another shutdown of the pump.
A. Incorrect. System pressure normally maintained by a combination of Potable Water
and Jockey Pump operation. In this case, pressure is not high enough to prevent Fire
Pump restart
B. Incorrect. System pressure normally maintained by a combination of Potable Water
and Jockey Pump operation. In this case, pressure is not high enough to prevent Fire
Pump restart
C. Correct. If system pressure is not 110-112 psig, the Fire Pump will restart. Action is
to find out where system demand is coming from
D. Incorrect. Correct system response but incorrect HPFP pressure . Pump would
restart again ifpressure was 105 when it was secured
Monday. May 07. 20073:23:10 PM
142
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability to(a) predict theimpacts of the following malfunctions oroperations ontheFire Protection System; and (b) based on those
predictions, use procedures tocorrect. control, or mitigate the consequences of those malfunctions or operations: Manual shutdown of
the FPS.
Question No.
Tier 2 Group 2
Importance Rating:
Technical Reference:
38
R0 2.9
0-SO-26-1
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPT200.HPFP, 6.16.a
New
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
41.10
Comments: editorial change to D. Removed greater than to make it incorrect.
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
NEW
HIGHER
4/2007
1.00
Version;
Answer:
o I 234 5 67 8 9
C CA CA CD D B D
Source If Bank:
Difficulty.
Plant:
Last 2 NRC? :
Scramble Range: A - D
SEQUOYAH
NO
. Monday, May 07, 2007 3:23:10 PM
143
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
73. 103 Al.OI 001
Given the following plant conditions:
The plant is in Mode 5.
Containment Purge is in operation.
The Personnel Airlock and Equipment Hatch are closed .
The Containment Purge Exhaust Isolation valve is inadvertently closed.
NO other components reposition .
Which ONE (1) of the following describes the containment parameter immediately
affected by this failure and the design limit for that parameter?
A.
Bt
c.
D.
Param eter
Design Limit
Temperature
250°F
Pressure
12 psig
Temperature
125°F
Pressure
9.5 psig
(
A. Incorrect. Temperature will not be adversely affected, Purge system does not provide a
cooling function. Correct containment temperature design limit.
B. Correct. Purge exhaust flow loss will couse containment pressure to increase in the
specified conditions; 12 psig is the Tech Spec maximum allowable pressure during LOCA
conditions.
C. Incorrect. Temperature not affected. 125°F is plausible since it is the lower Comtainment
temperature Tech Spec upper limit.
A. Incorrect. Pressure is affected; 9.5 psig is plausible because it is the containment setpoint
for placing RHR Spray in service in FR-Z.1 and for running Cntmt Spray Pumps in
EGA-1.1.
Monday, May 07.2007 3:23:1 0 PM
144
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Abilityto predict and/ormonitor changesin parameters (toprevent exceedingdesign limits) associated withoperating thecontainment
system controls including: Containment pressure, temperature. andhumidity.
(
Question No.
Tier 2 Group 1
Importance Rating:
Technical Reference:
27
R03.7
Tech Spec 3.6.1.4, 3.6.1 .5 & bases; 47W61 0-30-1
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPT200.CONTPURGE, B.5.d
Question Source:
Bank
Question History:
Harris 2005 NRC Exam
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
41.5
Comments:
(
Time:
Source:
Cognitive Level:
Job Position:
Dale:
Points:
BANK
HIGHER
4/2007
1.00
Version:
0 1 2 3 4 5 6 7 8 9
Answer:
B C B B D A C D AD
Scramble Range: A - D
Source If Bank:
IlARRlS 2005 NRC
Difficuhy:
Plant:
SEQUOYAli
Last 2 NRC?:
NO
Monday, May 07, 2007 3:23:10 PM
145
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
74. 103 10.03 001
Given the following plant conditions:'
Unit 2 is in Mode 6.
Core off-load is in progress.
Which ONE (1) of the following situations requires immediate suspension of irradiated
fuel movement? (Consider each individually)
A. One Train of ABGTS is declared inoperable.
B. Both Lower Containment Airlock doors are open.
C¥' Equipment Hatch is closed with 2 bolts fastened .
D. Containment Purge Supply Fan is declared inoperable
A. Incorrect. One train ofABGTS is required operable if One Airlock door will be open.
Refueling does not have to stop ifABGTS inop
B. Incorrect. Both doors may be open as long as 1 is capable of being closed.
C.Correct. Equipment door is required to be fastened by 4 bolts.
D. Incorrect. Containment Purge inop does not require stopping refueling, only concern
is containment purge radiation monitors being operable for refueling
Monday, May 07, 2007 3:23:10 PM
146
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledgeof the effectthat a loss or malfunction ofthe containment system will have onthe following: Loss of containment integrity
under refueling operations.
(
Question No.
Tier 2 Group 1
Importance Rating:
Technical Reference:
28
R03.?
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPT200.CntmtStructure, B.6.c
New
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
41.10/43.2
Comments:
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
NEW
LOWER
4/2007
1.00
Version:
Answer:
o I 2 3 4 5 6 7 8 9
Source If Bank:
Difficulty:
Plant:
Last 2 NRC?:
Scramble Range: A - 0
SEQUOYAH
NO
Monday, May 07, 2007 3:23:10 PM
147
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
75. E02 EA I.3 001
Given the following plant conditions:
Initial conditions:
-
A steam break has occurred inside containment.
Reactor trip and containment high-high pressure have actuated.
-
The faulted S/G has completely blown down.
-
The crew has entered ES-1.1 , SI Termination.
-
One containment spray pump is in service.
Current conditions:
Containment pressure is 2.5 psig .
-
The crew has just transitioned from ES-1.1 to the appropriate plant procedure.
Which ONE (1) of the following correctly describes the status of the CCPs and
Conta inment Spray pump immediately upon transition from ES-1. 1?
Containment Spray Pump
A.
1 CCP injecting via CCPIT
B. 1 CCP injecting via CCPIT
C. 1 CCP injecting via seal injection
and normal charg ing
D~ 1 CCP injecting via seal injection
and normal charging
In Service
Stopped and placed in A-AUTO
Stopped and placed in A-AUTO
In Service
(
A. Incorrect. Meet SI termination criteria; therefore, second CCP removed from
service and normal charging established.
B. Incorrect. Meet SI termination criteria; therefore, second CCP removed from
service and normal charging established. Containment pressure is > 2 psid;
therefore, CS is not stopped.
C. Incorrect. Containment pressure is > 2 psid; therefore, CS is not stopped.
D. Correct. Meet SI termination criteria; therefore, second CCP removed from service
and normal charging established. Containment pressure is > 2 psid; therefore, CS
is not stopped.
Monday, May 07,20073:23:10 PM
148
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Abilityto operate and I or monitor thefollowingas theyapplyto the (5 1Termination) Desired operatingresults during abnormal and
emergency situations.
(
Question No.
Tier 1 Group 2
Importance Rating:
Technical Reference:
64
R03.8
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPL271ES-1.1 , Objective 6
OPL273C502C; Obj. a.i, a.j
Question Source :
Bank
Question History:
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
41.10
Comments:
Time:
Source:
Cognitive Level:
Job Position:
Dale:
Points:
BANK
HIGHER
4/2007
1.00
Version:
0 I 2 3 4 5 6 7 8 9
Answer:
D B DA D C C A C A
Scramble Range: A - D
Source If Bank:
SEQUOYAH BANK
Difficulty:
Plant:
SEQUOYAH
Lasl 2 NRC! :
NO
Monday, May 07,2007 3:23:10 PM
149
(
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
76. E04 G2.1.28 001
Given the following plant conditions:
Reacto r Trip and Safety Injection have occurred on Unit 2.
The crew has transi tioned to ECA-1.2, LOCA Outside Containment.
The leak location has NOT been identified and the crew is preparing to isolate
Cold Leg Injection.
Radcon reports increased radiation levels in the 690' Pipe Chase.
Which ONE (1) of the following describes how Cold Leg Injection is isolated, and how
to determine if the leak has been stopped in accordance with ECA-1.2?
A. Close FCV-63-93 and FCV-63-94, Cold Leg Injection Valves, simultaneously.
Verify isolation by observing pressurizer level.
B. Close FCV-63-93 and FCV-63-94, Cold Leg Injection Valves, simultaneously.
Verify isolation by observing RCS pressure.
C. Close FCV-63-93 and FCV-63-94, Cold Leg Injection Valves, one at a time. Verify
isolation by observing pressurizer level.
D~ Close FCV-63-93 and FCV-63-94, Cold Leg Injection Valves, one at a time. Verify
isolation by observing RCS pressure.
A. Incorrect. Valves are closed 1 at a time, not simulataneously. RCS pressure is
checked
B. Incorrect. Correct parameter but 1 valve closed at a time
C. Incorrect. PZR level is not the parameter checked, but actions are correct.
D. Correct.Valves are closed one at a time and pressure is checked prior to
determining whether to reopen or leave closed. RCS pressure is the parameter
checked
Monday, May 07, 2007 3:23:11 PM
150
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Conduct of Operations: Kncwledq e of the purpose andfunction of majorsystem components and contro ls.
(
Question No.
Tier 1 Group 1
Importance Rating:
Technical Reference:
53
R0 3.2
ECA-1.2
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPL271ECA-1.2 Objective 4
New
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
41 .10
Comments:
Time:
Source:
Cognitive Level:
Job Position:
Date:
Point s:
NEW
LOWER
4/2007
1.00
Version:'
Answer:
o 1 23 4 5 6 7 8 9
DB C A A A CBB C
Source IfBank:
Difficulty:
Plant:
Last 2 NRC?:
Scramble Range: A - D
SEQUOYAH
NO
- Monday. May 07. 2007 3:23:11 PM
151
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
77. E05 EA1.3 00 \\
Given the following plant conditions:
Unit 1 is responding to a Loss of Heat Sink per FR-H.1 , Response to Loss of
Secondary Heat Sink.
-
All Steam Generator Wide Range levels are Off-Scale low.
o
RCS temperature is approximately 588°F and rising slowly.
Which ONE (1) of the following describes the preferred method of initiating Auxiliary
Feed flow for these conditions?
A. Feed at the highest possible rate to one SIG to preclude initiation of RCS Bleed
and Feed.
B. Feed at the minimum required flow to prevent possible SG tube failures.
Cl' Feed at the highest possible rate to one SIG to reestablish SG inventory and
secondary heat sink.
D. Feed at the minimum required flow to establish a controllable cooldown rate and
prevent RCS pressure from reaching the PORV setpoint.
A. Incorrect. Ble ed and Feed would already be initiated under these condition s.
B. Incorrect.
Tube failures are the primary concern when initiating feed, but for these
conditions, restoration of 1 SG as soon as possible is the priority
C.Correct. If RCS temp is rising with no inventory, AFW flow should be directed to one
SG at the max rate in an attempt to recover heat sink.
This minimizes the chance for
multiple tube failures as well as the quickest way to recover at least 1 SG as heat sink.
At this point, bleed and feed should already be initiated.
D. Incorrect. On a loss of heat sink, cooldown rate is not the priority. The RCS has
already heated up. Loss of inventory is a concern due to potential tube failures, but
addressed by feeding only 1 SG
Monday. May 07, 2007 3:23:11 PM
152
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledgeof the reasons for the following responses as they apply to the(Loss of SecondaryHeat Sink) Desiredoperating results
during abnormal andemergency situations.
(
Question No.
Tier 1 Group 1
Importance Rating:
Technical Reference :
54
R0 3.8
FR-H.1 BD
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPL271FR-H.1 Objective 4
Question Source:
Bank
Question History:
WTSI Various previous NRC
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
41.10
Comments:
SEQUOYAlI
NO
(
Mes
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
BANK
IllGHER
412007
1.00
Version:
Answer:
o I 2 3 4 5 6 7 8 9
C A D B D B C B DA
Scramble Range: A - D
Source If Bank:
WTSI
Difficulty:
Plant:
Last 2 NRC?:
Monday, May 07,2007 3:23:11 PM
153
(
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
78. E07 EA2 .1 001
Given the following plant conditions:
-
A Steam Generator Tube Rupture has occurred on Unit 1.
Due to equipment failures, the crew is performing actions contained in ECA-3.2,
SGTR and LOCA - Saturated Recovery.
-
The STA informs you that all CSF Status Trees are GREEN with the exception
of the following:
-
Core Cooling - YELLOW path for FR-C.3, Saturated Core Cooling
Inventory - YELLOW path for FR-1.2, Voids in Reactor Vessel
Which ONE (1) of the following describes the required implementation of procedures
for this event, and the reason?
A. Transition from ECA-3.2 to FR-1.2 to restore the Inventory CSF to a green
condition.
B. Transition from ECA-3.2 to FR-C.3 to restore the Core Cooling CSF to a green
condition.
C. Remain in ECA-3.2. Implementation of Yellow Path procedures is not allowed in
the ECA procedures in accordance with EPM-4, User's Guide.
D!" Remain in ECA-3.2. The actions contained in FR-C.3 and FR-1.2 conflict with
ECA-3.2 actions.
A. Incorrect. The crew may treat the actions is this way, but FR-I. will return SRO to
procedure in effect is Reactor vessel head voids are expected. ECAs do not preclude
the use ofyellow path procedures
B. Incorrect. Normally this would be true, but a caution in ECA-3.2 reminds SRO that
upper head may void during depressurization and step 1 of FR-C.3 returns SRO to
ECA-3.2 if performance of that procedure is in affect.
C. Incorrect. Transition is not required, and although FR-C.3 is a higher priority, it
would not be performed due to the conflict with ECA-3.2
D. Correct. Both FRs will return SRO to ECA-3.2.
Monday, May 07. 2007 3:23:11 PM
154
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability to determine and interpret the following as they apply to the (Saturated CoreCooling) Facility condttionsand selection of
appropriate procedures during abnormal andemergency operations .
(
Question No.
Tier 1 Group 2
Importance Rating:
Technical Reference:
83
SRO 4.0
EOP User's Guide, FR-C.3 step 1
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPL271EPM-4, B.11.c
New
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
43.5
Comments: Editorial change to Band 0 wording based on NRC comment
Time:
Source :
Cognitive Level:
Job Position:
Dale:
Points:
NEW
HIGHER
4/2007
1.00
Version:
Answer:
o 1 2 3 4 5 6 7 8 9
D D A A C B CB A A
Source If Bauk:
Difficulty:
Plant:
Last 2 NRC?:
Scramble Range: A - D
SEQUOYAH
NO
Monday, May 07, 2007 3:23:11 PM
155
(
c.
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
79. E09 G2.2.22 001
Given the following plant conditions:
A reactor trip has occurred on Unit 1.
Off-Site power has been lost.
Plant Cool down to Mode 5 will be performed.
Which ONE (1) of the following describes the Technical Specification Shutdown
Margin requirements prior to, and after the cooldown, and the minimum action require d
if Shutdown Margin requirements are not met at any time during the cooldown?
A. 1.0% delta k/k prior to RCS Cooldown;
1.6% delta k/k upon completion of RCS Cooldown;
Perform boration in accordance with EA-68-4, Emergency Boration, to restore
B. 1.0% delta k/k prior to RCS Cooldown;
1.6% delta k/k upon completion of RCS Cooldown;
Perform boration in accordance with SO-62-7, Boron Concentration Control, to
restore Shutdown Margin.
C~ 1.6% delta k/k prior to RCS Cooldown;
1.0% delta k/k upon completion of RCS Cooldown;
Perform boration in accordance with EA-68-4, Emergency Boration, to restore
D. 1.6% delta k/k prior to RCS Cooldown;
1.0% delta k/k upon completion of RCS Cooldown;
Perform boration in accordance with SO-62-7, Boron Concentration Control, to
restore Shutdown Margin.
A. Incorrect. Correct boration procedure but required Shutdown Margins are reversed
from Tech Spec requirements.
B. Incorrect. required Shutdown Margins are reversed from Tech Spec requirements.
Incorrect boration procedure. Incorrect procedure per ES-O.1, this
procedure wouta be used if borating RCS per GO-7 Shutdown from HSB
to CSO.
C. Correct.
O. Incorrect. Correct SOM, but incorrect procedure.
Monday, May 07. 20073:23:11 PM
156
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
EquipmentControl Knowledge of limiting conditionsfor operationsandsafetylimits.
KA Match: the KA is matched sincethe
Question No.
Tier 1 Group 2
Importance Rating:
Technical Reference:
84
SRO 4.1
EA-68-4, TS 3.1.1.2
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPL271ES-O.2. 6.6.a
New
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
43.5
Comments:
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
NEW
HIGHER
4/2007
1.00
Version:
Answer:
o I 2 345 6 7 8 9
C B C BAA B C I3A
Source tf Bank:
Difficulty:
Plant:
Last 2 NRC?:
Scramble Range: A - D
SEQUOYAII
NO
Monday, May 07,20073:23:11 PM
157
c
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
80 . Ell EK3.2 001
Which ONE (1) of the following describes two objectives of procedure ECA-1.1, Loss
A. Ensure only one train of SI in service to prevent cavitation and initiate makeup to
the RWST to ensure RCS inventory can be maintained.
B. Reduce SI flow to delay depletion of the RWST and stabilize RCS temperature to
minimize RCS inventory requirements.
C. Perform necessary system alignments to restore emergency coolant recirculation
capability and stabilize RCS temperature to minimize RCS inventory requirements.
D~ Reduce SI flow to delay depletion of the RWST and perform necessary system
alignments to restore emergency coolant recirculation capability
A. Incorrect. SI is reduced to the minimum required for heat removal. Plausible
because core cooling requirements must be maintained.
B. Incorrect. Stabil izing RCS temperature is not an action or priori ty, but plausible
because cooling down would result in RCS shrinkage, and therefore, additional
makeup required
C. Incorrect. Stabilizing RCS temperature is not an action or priority, but cooling down
would result in RCS shrinkage , and therefore, additional makeup required
D. Correct. The procedure has 3 objectives: Minimizes depletion of RWST,
depressurize RCS to minimize break flow and cause accumulator injection, and
continue attempts to restore recirculation capability
Monday. May 07, 2007 3:23:11 PM
158
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledge of the reasons for thefollowing responses 85 theyapply tothe (Loss of Emergency CoolantRecirculation) Normal. abnormal
and emergencyoperating proceduresassociated with (LossofEmergency CoolantRecirculation).
(
Question No.
Tier 1 Group 1
Importance Rating:
Technical Reference:
55
R0 3.5
ECA-1.1 and basis
Proposed references to be provided to applicants during examination:
Learning Objective: OPL271ECA-1.1 Objective 4
None
Question Source:
Question History:
Bank
WTSI Last Exam VCS 06 Audit
Question Cognitive Level:
10 CFR Part 55 Content:
Lower
41.10
Comments:
Time:
Source:
Cog nitive Level:
Job Position:
Date:
Points:
BANK
LOWER
4/2007
1.00
Version:
Answer:
o I 23 4 5 6 78 9
D D BBA DDC DC
Source If Dank:
Difficulty:
Plant:
Last 2 NRC?:
Scramble Range: A - D
SEQUOYAH
NO
Monday, May 07,20073:23:11 PM
159
(
l
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
81. El2 G2.4 .31 DOl
Given the following plant conditions:
-
A steam line rupture has occurred in the Unit 1 West Valve Vault Room.
-
The crew was unable to isolate SGs.
ECA-2.1, Uncontrolled Dep ressurization of All Steam Generators, is in progress.
-
The crew has taken action to minimize the plant cooldown.
-
AFW flow to S/Gs 1, 2, 3 and 4 are currently at 25 gpm.
-
Thots are decreasing slowly.
-
The following alarms are received:
1-XA-M3-C3, STM GEN #1 LEVEL LOW
1-XA-M3-C4, STM GEN #2 LEVEL LOW
1-XA-M3-C5, STM GEN #3 LEVEL LOW
1-XA-M3-C6, STM GEN #4 LEVEL LOW
Which ONE (1) of the following actions is required in accordance with ECA-2.1?
A. Raise AFW flow to #1, #2, #3, and #4 SGs . The minimum NR level, per ECA-2.1, is
25%.
B. Raise AFW flow to #1, #2, #3, and #4 SGs. The minimum NR level , per ECA-2.1 , is
50%.
C~ Maintain AFW flow at its current value. If Thot starts to rise, raise AFW flow to
stabilize RCS temperature.
D. Maintain AFW flow at its current value. When 3 of 4 SGs are at the applicable
setpoint, transition to FR-H.1 , Response to Loss of Secondary Heat Sink.
A. Incorrect. After throttling to minimize RCS cooldown, even if levels are low, AFW
remains throttled until That begins to rise. At that point, AFW is throttled just enough to
stabilize temperature.
Credible because 10% is the lower limit that level is checked at
B. Incorrect. After throttling to minimize RCS cooldown, even if levels are low, AFW
remains throttled until That begins to rise. At that point, AFW is throttled just enough to
stabilize temperature.
Credible because 50% is the upper limit that level is checked at
C. Correct.
D. Incorrect. Since this an operator induced reduction ofAFW flow, FR-H. 1 actions
would not be performed
Monday, May 07,2007 3:23:11 PM
160
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Emergency ProceduresI PlanKnowledgeof annunciators alarms and indications. anduse of the response instructions
(
Question No.
Tier 1 Group 1
Importance Rating:
Technical Reference:
56
RO 3.3
ECA-2.1, AR M3
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPL271ECA-2.1, B.6.a
New
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
41.10
Comments:
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
NEW
HIGH ER
4/2007
1.00
Version:
Answer:
o I 2 3 4 5 6 7 8 9
C BA B CC B B A B
Source If Bank:
Difficulty:
Plan t:
Last 2 NRC?:
Scramble Range: A - D
SEQUOYAII
NO
Monday. May 07. 2007 3:23:12 PM
161
(
l
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
82. E13 EK2.1 001
Given the following plant conditions:
-
The crew entered FR-H.2, "Steam Generator Overpressure", due to an
overpressure condition on S/G #2.
-
SG #2 pressure is 1170 psig.
S /G #2 narrow range level is 72%.
Which ONE (1) of the following describes the appropriate actions, in sequence, to
mitigate this event in accordance with FR-H.2?
A. First Verify Feedwater Isolation and then initiate SG Slowdown.
S~ First Verify Feedwater Isolation and then attempt to dump steam from the affected
SG.
C. First Isolate AFW flow and then initiate SG Slowdown.
D. First Isolate AFW flow and then attempt to dump steam from the affected SG.
A.
Incorrect. First action is correct, but SG blowdown is an action that would be
performed in FR-H.3. Applicant may confuse these actions since the indicated
level in the SG is 72% and think this is the cause of the high pressure.
B. Correct.
C. Incorrect. AFW is isolated later ifpressure cannot be brought under control by
dumping steam. Additionally, SG blowdown is a later action
D. Incorrect. AFW is isolated later; attempting to dump steam is correct.
Monday, May 07,20073:23:12 PM
162
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
KnO'Nledge of the jnteereaucoebetween the(SteamGenerator Overpressure) andthe foilOVo1ing: Ccmponents,and functions ofcontrol
andsafetysystems, Including jnstrornertauoo. signals. interlocks. failure modes, and autcmatic andmanual features
(
Question No.
Tier 1 Group 2
Importance Rating:
Technical Reference:
65
R0 3.0
FR-H.2
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPL271 FR-H.2, Obj. 5
Question Source:
Bank
Question History:
New
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
41.10
Comments:
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
NEW
HIGHER
412007
1.00
Version:
Answer:
o I 2 3 4 5 6 7 8 9
Source If Bank:
Difficulty:
Plant:
Last 2 NRC? :
Scramble Range: A - D
SEQ UOYAH
NO
Monday, May 07, 2007 3:23:12 PM
163
(
l
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
83 . E IS G2.1.32 00 1
Given the following plant conditions:
A LOCA has occurred and the following containment conditions exist after transition
to E-1, Loss of Reactor or Secondary Coolant:
Pressure is 2.5 psig and rising.
Sump level is 70% and rising.
Upper and Lower Containment Radiation level is 102 Rem per hour.
Which ONE (1) of the following describes the procedure required to mitigate the above
conditions?
A. Transition to FR-Z.1 , Response to High Containment Pressure.
B~ Transition to FR-Z.2, Response to Containment Flooding.
C. Transition to FR-Z.3, Response to High Conta inment Radiation.
D. Remain in E-1, Loss of Reactor or Secondary Coolant.
A. Incorrect. Pressure is below the criteria for an orange path that would require entry
to FR-Z.1
B. Correct.
C. Incorrect. A yellow condition for radiation level does exist, but the orange condition
on cntmt flood level requires entry to a higher priority procedure
D. Incorrect. There is an orange and yellow condition"on the Containment CSF. E-1
will be performed after addressing the CSF
Monday, May 07, 2007 3:23:12 PM
164
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Conduct of Operations: Ability to explain and apply allsystemlimits and precautions.
(
Question No.
Tier 1 Group 2
Importance Rating:
Technical Reference:
85
SRO 3.8
FR-Z.2 background, FR-O
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPL271FR-Z.2, 8 .5
New
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
43.5
Comments:
(
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
NEW
LOWER
4/2007
1.00
Version:
0 I 2 3 4 5 6 7 8 9
Answer:
BD A C CDD C CD
Source If Bank:
Difficulty:
Plant:
Last 2 NRC?:
Scramble Range: A - D
SEQUOYAH
NO
Monday, May 07,2007 3:23:12 PM
165
(
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
84. G2.1.I 3 001
A card reader is broken, prohibiting access to a vital area.
If conditions requ ire immediate access, who by title, has control over Vital Area Access
keys in accordance with SPP-1.3, Plant Access and Security and NSDP-8, Keys and
Locks?
A. Security ONLY
B~ Security or Shift Manager/Unit Supervisor ONLY
C. Security or Duty Operations Manager ONLY
D. Security or Duty Plant Manager ONLY
A. Incorrect. SM/US are also issued keys
B. Correct. The Shift Manager/US holds the Vital Area Access key, and issues it as needed.
[Refer to NSDP-8 Sect 3.0 B: *...AII unissued keys, locks , and cores are stored and
maintained in locked repositories or in cabinets under the direct control of Security or the
Shift Manager (SM) to reduce the probability of compromise...")
C. Incorrect. SM, see above
D. Incorrect. SM, see above.
Memory level item.
Monday, May 07, 2007 3:23:12 PM
166
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledge of facility requiremen ts for controlling vitali controlled access.
(
Question No.
Tier 3 Group 1
Importance Rating:
Technicai Reference:
95
SRO 2.9
SPP-1.3; NSDP-8
Proposed references to be provided to applicants during examination:
None
Learning Objective :
Question Source:
Question History:
OPL271SECURITY Objective 4
New
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
43.5
Comments:
l
Time:
Source:
Cognitive Level:
Job Positi on:
Date:
Points:
NEW
LOWER
4/2007
1.00
Version:
Answer:
o I 2 3 4 5 6 7 8 9
B CA C AB CB A A
Source If Bank:
Difficulty:
Plant:
Last 2 NRC?:
Scramble Range: A - D
SEQUOYAH
NO
Monday, May 07, 2007 3:23:12 PM
167
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
85. G2.1.18 001
In accordance with OPDP-1, Conduct of Operations, which ONE (1) of the following
describes when the words 'LATE ENTRY' are required in eSOMS and how the 'LATE
ENTRY' is made?
A late entry is required any time that required information was not entered at the time
of event...
A. if logs have NOT been approved since the time of the event.
Enter 'LATE ENTRY' followed by the event description.
B~ if logs have been approved since the actual time of the event.
Enter 'LATE ENTRY' followed by the event description .
C. if logs have NOT been approved since the time of the event.
Enter the event description followed by 'LATE ENTRY' .
D. if logs have been approved since the actual time of the event.
Enter the event description followed by 'LATE ENTRY'.
A. Incorrect. Late entries are only required after they are found when approval has
been made without the original entry of event (For instance, after shift turnover it is
found that an entry was not made). The sequence ofthe entry is correct.
B. Correct. Late entry is only required after the log has been approved, and the log is
annotated with "LATE ENTRY" followed by event description.
C. Incorrect. wrong requirement wrong order of entry.
D. Incorrect. Partially correct, but the order of the log entry is wrong.
Monday. May 07, 2007 3:23:12 PM
168
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Abilityto make accurate. clear andconcise logs. records. statusboards. and reports.
(
Question No.
Tier 3 Group 1
Importance Rating:
Technical Reference:
67
R02.9
OPDp*1 , Appendi x E, section E
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPL271 C209 Objective 9
New
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
41.10
Comments:
(
Time;
Source:
Cognitive Level:
Job Position;
Date;
Points:
NEW
LOWER
4/2007
1.00
Version:
Answer:
o 1 2 345 6 7 8 9
BCDC BBDBA C
Source If Bank:
Difficulty;
Plant:
Last 2 NRC'!;
Scramble Range: A - D
SEQUOYAH
NO
Monday, May 07,20073;23;12 PM
169
(
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
86. 0 2.1.2 001
OPDP-1, Conduct of Operations, describes the " Departure From License Condition"
which can be invoked to protect the health and safety of the public.
As a minimum, which ONE (1) of the following conditions must ALWAYS be met when
departing from a license condition or technical specification in accordance with 10
CRF 50.54 (x) and (y)?
At The action must be approved by a licensed SRO prior to taking the action.
B. Theaction must be taken in accordance with the provisions of the Emergency Plan.
C. The NRC must be notified prior to the action and must concur with the action to be
taken.
D. The Plant Manager must be notified prior to the action and must concur with the
action to be taken.
A Correct.
B incorrect. Although the unit is most likely in the E-Plan, it is not a requirement prior to
invoking 10CFR50.54(x)
C incorrect. NRC concurrence is not required for the action; they must be notified as
soon as possible but no more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior.
o incorrect. Preventing damage or injury is a reason for invoking the rule, but Plant
Manager concurrence or approval is not required
Monday, May 07, 20073:23:12 PM
170
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledge of operator responsibilities during allmodes of plant operation.
(
Question No.
Tier 3 Group 1
Importance Rating:
Technical Reference:
66
R03.0
OPDP-1 , Appendix F
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Que stion History:
OP1271C209, B.8
Bank
Question Cognitive Level :
Lower
10 CFR Part 55 Content:
41.10
Comments:
SEQUOYAH
NO
c.
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
BANK
LOWER
4/2007
1.00
Version:
Answer:
o 1 234 5 6 7 8 9
Scramble Range: A - D
Source If Bank:
WTSI
Difficully:
Plant:
Last 2 NRC'!:
Monday, May 07,2007 3:23:12 PM
171
t:
\\.
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
87 . G2.1.21 001
You are preparing to perform a control rod exercise surveillance on your shift.
BSL is not operating.
Which ONE (1) of the following describes the correct location(s) to obtain the current
controlled copy revision of the procedure?
A~ Main Control Room ONLY
B. Main Control Room, Operations Field Office ONLY
C. Main Control Room, Work Control Center ONLY
D. Main Control Room, Operations Field Office or Work Control Center
A. Correct. .
B. Incorrect. Copies in the OFO are not controlled, but plausible because OSC is
controlled
C. Incorrect. wee does not have controlled copies of surveillances
('
D. Incorrect. Copies in the OFO are not controlled
Abilityto obtainandverifycontrolled procedure ropy.
Question No.
Tier 3 Group 1
Importance Rating:
Technical Reference:
68
RO 3.1
SPP-2.2
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPL27SPP-2.2 Objective 2 and 5
Bank
(
Question Cognitive Level :
Lower
10 CFR Part 55 Conten t:
41.10
Comments:
Monday, May 07, 2007 3:23:13 PM
172
Scramble Range: A - D
SEQUOYAH
NO
NEW
LOWER
412007
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Time:
I
Points:
1.00
Version:
0 I 2 3 4 5 6 7 8 9
Answer:
AAA DDBCC CD
Source [fBank:
Difficulty:
Plant:
Lasl2 NRC?:
Source:
Cognitive Level:
Job Position:
Date:
r
Monday, May 07, 2007 3:23:13 PM
173
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
88. G2.1.7001
Given the following plant conditions:
- A Normal Plant cooldown is in progress.
- The following table is a plot of the cooldown:
0800
0815
0830
0845
0900
0915
0930
RCS TCOLD
547"F
530°F
520°F
505°F
498°F
478°F
447"F
TIME
0945
1000
1015
1030
1045
1100
1115
RCS TCOLD
425°F
395°F
382°F
364°F
340°F
320°F
220°F
(
Which ONE (1) of the following describes the first time that the Technical Specification
RCS Cooldown rate limit was exceeded, and the Technical Specification basis for the
cooldown rate limit?
A. 1000; brittle fracture of reactor vessel ONLY
B. 1115; brittle fracture of reactor vessel and RCS pressure boundary
C!" 1000; brittle fracture of reactor vessel and RCS pressure boundary
D. 1115; brittle fracture of reactor vessel ONLY
A. Incorrect.
Correct time, but PZR is excluded from concern about brittle fracture
B. Incorrect.
Incorrect time and PZR is excluded from brittle fracture concern.
C. Correct.
This is 103 degrees in one hour.
D. Incorrect.
Limits were exceeded at 1000 because cld rate was 103 deg F for that
hour
The LCO establishes operating limits that provide a margin to brittle failure of
the reactor vessel and piping of the reactor coolant pressure boundary (RCPB).
The vessel is the component most subject to brittle failure, and the LCO limits
apply mainly to the vessel. The limits do not apply to the pressurizer, which has
different design characteristics and operating functions. The reactor vessel
materials have been tested to determine their initial RTNDT and the results of
these tests are shown on Table B 3/4.4-1.
Monday, May 07, 2007 3:23:13 PM
174
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Abilitytoevaluate plant performanceandmake operational judgments basedonoperating characteristics, reactor beha-.Aor. and
instrument interpretation.
(
Question No.
Tier 3 Group 1
Importance Rating:
Technical Reference:
94
SRO 4.4
TS 3.4.9.1 and basis, 0-SI-SXX-068-127, PTLR
Proposed references to be provided to applicants during examination :
None
Learning Objective:
OPT200.RCS Objective 6.a
Question Source:
Bank
Question History:
Robinson 2007 NRC
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
43.2
Comments:
SEQUOYAII
NO
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
BANK
HIGHER
412007
1.00
Version:
Answer:
o I 2 3 4 5 6 7 8 9
C B C C B C B 0 C C
Scramble Range: A - D
Source If Bank:
ROBINSON 2007 NRC
Difficulty:
Plant:
Last 2 NRC?:
Monday. May 07. 2007 3:23:13 PM
175
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
89. G2.2.1-=-2 "'00"'2'---0---"------,-_-----:----,-_---,,.,.,..-
--,
Given the following plant conditions:
Unit 2 is currently in MODE 4.
At 0900 today, it is discovered that a routine 24-hour surveillance involving
Shutdown Margin was last performed at 0600 on the previous day.
Which ONE (1) of the following is the LATEST time the surveillance may be performed
in accordance with Technical Specification requirements?
A':' 1200 today
B. 1500 today
C. 0600 tomorrow
D. 0900 tomorrow
A. Correct. The surveillance requirements are satisfied if the surveillance is completed
by 1200, because the surveillance interval of 1.25 would be satisfied.
B. Incorrect. This time would represent the surveillance interval times 1.25 from the
time of discovery of the missed surveillance
C. Incorrect. This time indicates the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> extension granted by TS 4.0.3 from the
time the surveillance was missed. LCO 4.0.3 does not apply in this condition. It is
applied if failure to perform a surveillance, outside the allowable surveillance interval
including allowable extension time is discovered; the delayed LCO entry allows
performance time for surveillance completion.
D. Incorrect. This time indicates the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> extension from time of discovery of the
missed surveillance. LCO 4.0.3 does not apply in this condition. It is applied if
failure to perform a surveillance, outside the allowable surveillance interval including
allowable extension time is discovered; the delayed LCO entry allows performance
time for surveillance completion.
Monday, May 07, 20073:23:13 PM
176
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledgeof surveillance proceclures.
Question No.
69
Tier 3 Group 2
Importance Rating:
Technical Reference :
RO 3.0
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPL271SPP-2.2 Objective 4
Bank
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
41.10
Comments:
Time:
Source:
Cognitive Level:
Job Position:
Date:
Poin ts:
NEW
LOWER
412007
1.00
Version:
Answer:
o 1 234 5 6 7 8 9
ABC BDCA BBD
Source IfBank:
Difficulty:
Plaut:
Last 2 NRC?:
Scramble Range: A - D
SEQUOYAlI
NO
Monday, May 07,20073:23:13 PM
177
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
90. G2.2.23 001
Which ONE (1) of the following describes the requirement for logging of LCO's in
accordance with OPDP-8, Limiting Conditions for Operations Tracking, if the LCO is
entered and exited during the same shift?
Unit Log
LCO Tracking Log
A.
Log entry required
Log entry required
B~
Log entry required
Log entry NOT required
C.
Log entry NOT required
Log entry required
D.
Log entry NOT required
Log entry NOT required
A incorrect. LCO may entries may be put in LCO Tracking log but the only ones
required are the entries that will go past the end of the shift
B Correct. OPDP-8 page 4 of 24 states: The US/designee is responsible for logging the entry
and exit from TS LCOs. LCOs should be entered into the LCO Tracking Log. LCOs that
will be exited before the end of the assigned shift do not need to be entered into the LCO
Tracking Log. The Unit Log shall be the official log for LCOs. Times and dates entered on
his/her log shall be used as the official time/date for TS LCO action statements and for all
matters that require a time/date of discovery.
C incorrect. The Unit Log is required at all times for all entries as the primary log.
o incorrect. The Unit Log is required as the official log
Monday. May 07. 2007 3:23:13 PM
178
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Abilitytotrack limitingconditions foroperations.
(
Question No.
Tier 3 Group 2
Importance Rating:
Technical Reference:
70
R0 2.6
OPDP-8
Proposed references to be provided to applicants during examination:
None
Learning Objective:
Question Source:
Question History:
OPS271OPDP-8 Objective 6
New
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
41.10
Comments: editorial change to Band 0 to make them read the same as the OPDP
l
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
NEW
LOWER
412007
1.00
Version:
Answer:
o I 2 3 4 5 6 7 8 9
BD C DDD A AB A
Source If Bank:
Difficulty:
Plant:
Last 2 NRC?:
Scramble Range: A - D
SEQUOYAH
NO
Monday. May 07. 2007 3:23:13 PM
179
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
91. G2.2.26 001
According to Tech Spec 3.9.3, Decay Time, which ONE (1) of the following describes
when irradiated fuel movement in the reactor vessel would be allowed?
100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> from
_
A'!' Hot Standby
B. Hot Shutdown
C. Cold Shutdown
D. Refueling Shtudown
A. Correct. TS 3.9.3 specifies 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> from critical. In this case, achieving Hot
Standby.
B. Incorrect. This is 100 hrs from Hot Shutdown.
C. Incorrect. This is 100 hrs from Cold Shutdown.
D. Incorrect. This is 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> from Refueling.
Knowledge of refueling administrative requirements.
Question No.
Tier 3 Group 2
Importance Rating:
Technical Reference:
71
R02.5
(
Proposed references to beprovided to applicants during examination:
None
Learning Objective:
OPT200.FH Objective 6.a
Question Source:
Bank
Question History:
Sequoyah FH-B.5.C-1 1,
Developed from Kewaunee NRC 2000 exam
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
41 .10,43.2
Comments:
Monday, May 07,20073:23:13 PM
180
SEQUOYAH
NO
BANK
LOWER
4/2007
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Time:
I
Points:
1.00
Version:
0 I 2 3 4 5 6 7 8 9
Answer;
A A C D BA B D C B
Scramble Range: A - D
Source If Bank:
SEQUOYAH BANK
Difficulty:
Plant:
Last 2 NRC?:
Source:
Cognitive Level:
Job Position:
Date:
(
(
Monday, May 07, 2007 3:23;13 PM
181
(
l
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
92. G2.2.5 001
Given the following plant conditions:
-
A plant design change request form is in the approval process.
-
The proposed modification will modify the control rod overlap setpoints in the
logic cabinets.
Which ONE (1) of the following describes the final management position, by title ,
required to approve the change prior to implementation?
A'! Plant Manager
B. Site Vice President
C. Maintenance and Mods Manager
D. Engineering and Support Manager
A. Correct.
Per SSP-9.3
B. Incorrect.
The Site Vice President will be involved in the approval process, but the
Plant Manager has final authority for approval.
C. Incorrect.
The MODs manager has responsibility for completion of the physical
work, but does not have final approval authority.
D. Incorrect. The engineering manager does handle the completion of the DCN and
MODs package, but does not have final approval authority.
Monday, May 07,2007 3:23:13 PM
182
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowleclge of the process for makingchanges in the facilityas described in the safety analysis report.
Question No.
Tier 3 Group 2
Importance Rating:
Technical Reference:
96
SRO 2.7
SPP-9.3
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPL271C209, Obj. 12
Question Source:
Bank
Question History:
Sequoyah Bank SPP-9.3-2
Question Cognitive Level:
Lower
10 CFR Part 55 Content:
43.3
Comments:
SEQUOYAH
NO
l
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
BANK
LOWER
4/2007
1.00
Version:
Answer:
o I 2 3 4 5 6 7 8 9
A D B B C C B C B B
Scramble Range: A - D
Source If Bank:
SEQUOYAH BANK
Difficulty:
Planl:
Last 2 NRC?:
Monday, May 07,20073:23:14 PM
183
(
l
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
93. G2.2.9 001
Given the following plant conditions:
Unit 2 is in Mode 3.
Engineering has requested that the 2A SI pump be started with the
discharge valve throttled to 75% open to determine starting current.
The test is NOT described in the current test procedure or the Safety Analysis
Report.
The Operations Manager has determined that an Urgent Procedure change is
required to support the outage critical path schedule.
The Shift Manager may approve the test procedure change
_
A. with concurrence from licensing ONLY.
B. with concurrence from another SRO ONLY.
C. with concurrence from licensing AND another SRO.
D!' after a written 10CFR50.59 safety evaluation has been approved.
A. Incorrect;
Not described in FSAR, then the SM cannot approve by him(her)self.
B. Incorrect;
2 SROs can approve normal procedure changes.
C. Incorrect;
Licensing concurrence is not required, results of a review would be sent
through Licensing.
D. Correct;
See SPP-9.4 Screening Review Form, question number 4. The
screening review will result in a 50.59 safety evaluation.
Monday. May 07, 2007 3:23:14 PM
184
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowleclge of the process for determining if the proposed change, test or experiment increases the probabilityof occurrence or
consequencesof an accidentduring the change, test or experiment.
(
Question No.
Tier 3 Group 2
Importance Rating:
Technical Reference:
97
SRO 3.3
SPP-2.2, SPP-9.4
Proposed references to be provided to applicants during examination :
None
Learning Objective:
OPL271 C209 Objective 12
Question Source:
Bank
Question History:
Sequoyah Bank 10CFR50.59-1
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
43.3
Comments :
I need the procedure to verify and justify. Need to beef up justification
SEQUOYAH
NO
Time:
Source:
Cognitive Level:
Job Position:
Date:
3
Points:
BANK
LOWER
412007
1.00
Version:
Answer:
o I 2 3 4 5 6 7 8 9
D DDDDD D DDD
ScrambleRange:A- D
Source If Bank:
SEQUOYAH BANK
Difficulty:
Plant:
Last 2 NRC'!:
Monday, May 07,2007 3:23:14 PM
185
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
94. G2.3...:..:10,-,0",0-,-1 --o-,.,---:--.,....--c--~--------------------,
(
Given the following plant conditions:
-
A rapid load reduction from 100% power to 60% power was performed on Unit 1
approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago.
Chemistry confirms that RCS 1-131 activity exceeds Technical Specification
limit of acceptable operation.
-
The US directs a plant shutdown to be performed .
Which ONE (1) of the following post shutdown actions is subsequently performed to
limit the release of activity?
A. All MSIVs are closed
B~ RCS temperature is reduced below 500'F
C. All SIG PORV setpoints are raised
D. Maximum Condensate Polishers are placed in service
A is incorrect because closing MSIVs does not prevent rad release from SG ARVs
B is correct. Reduce temp IAW TS
C is incorrect. Would not stop a release from SG SV
o is incorrect. Cation Demin may be placed in service on Letdown, but placing
Condensate Demins in service would still not minimize a release off-site if SV or SG
ARV lifted
l
Monday. May 07, 2007 3:23:14 PM
186
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability 10 performprocedures to reduce excessive levels of radiationand guard against personnel exposure.
(
Question No.
Tier 3 Group 3
Importance Rating:
Technical Reference:
73
RO 2.9
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPL271AOP-R.06 Objective 6 and 9
Question Source:
Bank
Question History:
WTSI Bank
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
41.10
l
Comments:
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
BANK
II1GHER
4/2007
1.00
Version:
0 1 2 3 4 5 6 7 8 9
Answer:
B CA D A D B D A A
Scramble Range: A - D
Source IfBank:
WTSI
Difficulty;
Plant:
SEQUOYAll
Last 2 NRC?:
NO
Monday. May 07. 2007 3:23:14 PM
187
(
l
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
95. G2.3.2001
Given the following conditions at a work site:
Airborne activity - 3 DAC
Radiation level - 40 mremlhr.
Radiation level with shielding - 10 mremlhr.
Time to place shielding - 15 minutes.
Time to conduct task WITH respirator - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Time to conduct task WITHOUT respirator - 30 minutes.
Assumptions:
The airborne dose with a respirator will be zero.
A dose rate of 40 mremlhr will be received while placing the
shielding.
All tasks will performed by one worker, including initial placement of
shielding, if required.
Shielding can be placed in 15 minutes with or without a respirator.
The shielding will not be removed
Which ONE of the following wou ld result in the lowest whole body dose?
A. Conduct task WITHOUT respirator or shielding.
B. Conduct task WITH respirator and WITHOUT shielding.
C. Place shielding WITH respirator and conduct task WITH respirator.
D~ Place shield ing WITH respirator but conduct task WITHOUT respirator.
DISTRACTORS:
A INCORRECT
20 mrem (conduct task) + 3.75 mrem (airborne) = 23.75 mrem.
B INCORRECT
40 mrem (conduct task) + 0 mrem (airborne) = 40 mrem.
C INCORRECT
10 mrem (place shielding) + 10 (conduct task) + 0 mrem (airborne) = 20
mrem.
D CORRECT
10 mrem (place shielding) + 5 mrem (conduct task) + 3.75 mrem (airborne)
18.75 mrem. NOTE: 3 DAC x 2.5 mrem = 7.5 mrem
REFERENCES:
1.
KIA CATALOGUE QUESTION DESCRIPTION:
- Ability to perform procedures to reduce excessive levels of radiation and guard against
personnel exposure.
Monday, May 07, 2007 3:23:14 PM
188
Source:
Cognitive Level:
Job Position:
Date:
BANK
HIGHER
R
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Time:
I
Point"
1.00
Version:
0 I 2 3 4 5 6 7 8 9
Answer:
D DB A A B A A A C
Scramble Range: A - D
Source IfBank:
WTSI
Difficulty:
C/A(2.9/3.3)
Plant:
SM05301
Last 2 NRC?:
MC/SDR
Monday, May07,20073:23:14 PM
189
l
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
96. 02.3.4 001
Given the following plant conditions:
A General Emergency has been declared .
A severely injured individual is in the Pipe Chase in a radiation field of 50 RlHr.
Two individuals have volunteered for the rescue. BOTH of the volunteers have been
briefed on the risks involved:
Individual A is a 37 year old male.
Individual B is a 46 year old male.
In accordance with EPIP-15, Emergency Exposure Guidelines, which volunteer should
be selected for the rescue, and what is the maximum exposure the SED may authorize
him to receive?
A. Individual A; 10 Rem.
B. Individual B; 10 Rem.
C. Individual A; 25 Rem.
D!" Individual B; 25 Rem.
A
Incorrect.
because the older employee will be selected due to a lower chance of
long term effects ofradiation exposure affecting this person. 10 Rem is
the maximum authorization limit for procection of equipment.
B
Incorrect.
because the authorization is only for 25 rem.
C
incorrect
because the older employee will be selected due to a lower chance of
long term effects of radiation exposure affecting this person.
o Correct
The older individual will be selected and the maximum authorization
exposure is 25 Rem per EPIP-15, page 6 and page 4, section 4.1.E.
Monday. May 07. 2007 3:23:14 PM
190
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledge of radiationexposure limitsand contamination control, including permissible levels in excess of those authorized.
(
Question No.
Tier 3 Group 3
Importance Rating:
Technical Reference:
98
SRO 3.1
EPIP 15
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPL271 C198REP Objective 1.f
Question Source:
Modified
Question History:
Robinson 2007 NRC Exam
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
43.5
Comments:
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
MODIFIED
HIGHER
4/2007
1.00
Version:
Answer:
o I 2 3 4 5 6 7 8 9
DDADD C B AD D
Source If Bank:
Difficulty:
Plant:
Last 2 NRC'!:
Scramble Range: A - D
SEQUOYAH
NO
Monday, May 07,2007 3:23:14 PM
191
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
97. G2.4.25 0",0-,-1---,--------,,----
-
- -,---
-,---
c:-----::---:-:--=-=--=c:--=,----:;------,--,,---- ---
-
The following lines are observed on the 0-M-29 "Blue Goose" and printer:
2D43 A 50 IN 07-Nov-Q2 09:15 ZONE 85 CHARGING PUMP ROOM 2A CROSS ZONE
W/ZONE 82 ACTUATES FSV-26-191;
2D46 A 50 IN 07-Nov-02 09:16 ZONE 82 U2 SI & CHARGING PUMP ROOMS CROSS
ZONE W/Z ONES 83, -84, -85, 86, & 87 ACTUATES FSV-26-191 ZN LOCATED IN PNL
0-L-606;
2H38 A 50 IN 07-Nov-Q2 09:16 PNL 0-L-670/ELECTRIC FIRE PUMP A RUNNING ZONE
528 FIRE PUMP HOUSE RM A NOT OPERATIONALLY REQUIRED ZONE SEND OPERATO R
TO PUMP.
0-FCV-26-191 is an Auxiliary Building el 669' Pre-action Valve.
Wh ich ONE (1) of the following describes the condition under which sprinkler flow
occurs and the whether the fire brigade is required to be dispatched in accordance
AOP-N.01, Plant Fires?
Sprinkler Flow
A. sprinkler flow occurs with or without a
heat source.
B~ sprinkler flow occurs ONLY with a
heat source.
C. sprinkler flow occurs with or without a
heat source .
D. sprinkler flow occurs ONLY with a
heat source.
Action Required
Fire Brigade is NOT immediately
dispatched.
Immediately dispatch the Fire
Brigade.
Immediately dispatch the Fire
Brigade.
Fire Brigade is NOT immediately
dispatched.
l
A. Incorrect. and a cross zone alarm has occurred and spray would be initiated in the
area. According to the AOP- N.01 the fire brigade will be dispatched.
B. Correct. Actuation has occurred.
C. Incorrect. Spray would occur. Correct that the fire brigade would be dispatched.
D. Incorrect. Sprinkler heads did not actuate as indicated by Alarm 2H38.
Monday, May 07, 20073:23:14 PM
192
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXA M REV FINAL AS GIVEN 5-7-07
Knowledge offire protection procedures.
Question No.
74
Tier 3 Group 4
Importance Rating:
Technical Reference:
R0 2.9
0-SO-13-1 ; 0-AR-M-29
Proposed references to be provided to applicants during examination:
None
Learning Objective:
OPT200.HPFP B.16.c, 17.a, c, 18.b
Question Source:
Bank
Question History:
Sequoyah FPS-3
Question Cognitive Level:
HIgher
10 CFR Part 55 Content:
41.10
Comments:
SEQUOYAH
NO
l
Time:
Source:
Cognitive Level:
Job Position:
Date:
3
Points:
MODIFIED
HIGHER
4/2007
1.00
Version:
Ans wer:
o I 2 345 6 7 8 9
B CACD C B CAD
Scramble Range: A - 0
Source If Bank:
SEQUOYAH BANK
Difficulty:
Plant:
Last 2 NRC?:
Monday, May 07,20073:23:14 PM
193
(
l
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
98. G2.4.30 00 1
Given the following plant conditions on Unit 1:
Time
Plant Status/Condition
0955
Unplanned loss of 80% of MCR alarms and annunciator
printer and CRT in horseshoe.
1025
SM determines that increased surveillance is required
above current shift complement.
1040
Loss of ICS.
Which ONE (1) of the following correctly states the time requirement for notifying state
and local authorities in accordance with EPIP-1, Emergency Plan Clasification Matrix?
Assume that the REP classification is made as soon as conditions are met to make
the declaration.
(Reference provided)
A. 1010
B. 1025
C~ 1040
D. 1055
A. Incorrect.
15 minutes from initial event; this timeframe is allowed to diagnois and
determine classification.
B. Incorrect.
Actual time of classification. 15-minute notification clock starts at this
time.
C. Correct.
15 minutes maximum allowed following event declaration for notification
of state and local authorities.
D. Incorrect.
15 minutes from NOUE declaration to Alert diagnosis based on ICS
loss-may be confused with Alert declaration time.
Monday, May 07, 2007 3:23:14 PM
194
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledge of Which events related to system operations/status should be reportedto outside agencies.
(
Question No.
Tier 3 Group 4
Importance Rating:
Technical Reference:
100
SR03.6
EPIP-1
Proposed references to be provided to applicants during examination:
EPIP-1
Learning Objective:
Question Source:
Question History:
OPL271C168 Objective z.c
New
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
43.5
Comments:
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
NEW
IIIGHER
412007
1.00
Version:
Answer:
o I 2 3 4 5 6 7 8 9
Source If Bank:
Difficulty:
Plant:
Last 2 NRC?:
Scramble Range: A - D
SEQUOYAH
NO
Monday, May 07,2007 3:23:15 PM
195
(
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
99. G2.4.49 001
Given the following plant conditions:
Unit 1 is at 100% power with Control Rods in manual.
A transient occu rs resulting in the following alarms:
OTOT RUNBACKIROD STOP ALERT
.OVERPOWER ROD STOP
OPDT RUNBACK
Reactor power indicates the following and is rising:
N41 - 105.2%
N42 - 106.2%
N43 - 105.9%
N44-106.1 %
Tavg is 571°F
Which ONE (1) of the following identifies the procedure(s} required to be
implemented?
A. AOP-C.01, Rod Control Malfunctions, then E-O, Reactor Trip or Safety Injection.
B. AOP-C.01 , Rod Control Malfunctions ONLY.
C!" AOP-S .05, Steam Line or Feedwater Line Break/Leak, then E-O, Reactor Trip or
Safety Injection.
D. AOP-S .05, Steam Line or Feedwater Line Break/Leak ONLY.
A and B are incorrect because Tave is lower than required for the power level. Tavg
should be at 578 for 100% power, so a rod withdrawal is likely not the
initiator. Also, rods will not withdraw if there is an urgent failure.
A does
contain the correct action. Action for B would be correct if a trip wasn't
required and the event was a rod withdrawal.
C is correct. Must recognize that the action of AOP-S.05 requires a reactor trip if
reactor power is >100% power and increasing.
D is incorrect because a setpoint for reactor trip has been exceeded as indicated by the
first out annunciator for OPOT
Monday, May 07,2007 3:23:15 PM
196
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability toperform without reference to procedures those actions thatrequire immediate operation of system components andcontrols.
(
Question No.
Tier 3 Group 4
Importance Rating:
Technical Reference:
99
SR0 4.0
ARPs, E-O
Proposed references to be provided to applicants during examination:
None
Learning Objective:
E-O, B.6.a
Question Source:
Bank
Question History:
WTSI
Question Cognitive Level:
Higher
10 CFR Part 55 Content:
43.5
Comments:
SEQUOYAH
NO
(
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
BANK
HIGHER
412007
1.00
Version:
Answer:
o I 2 3 45 6 7 8 9
C C C AD ADDDD
Scramble Range: A - D
Source If Bank:
WTSI
Difficulty:
Plant:
Last 2 NRC?:
Monday, May 07, 2007 3:23:15 PM
197
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
100. G2.4.9 001
(
Given the following plant conditions:
-
Unit 1 is in Mode 5.
-
RCS temperature is 195°F.
-
RCS pressure is 325 psig.
-
Train "A" RHR in service.
-
Train "B" RHR out of service for surveillance testing.
-
SGs #2 and #3 are intact and at 33% NR.
-
Pressurizer level at 30% cold cal.
Which ONE (1) of the following is the preferred method of core cooling if a loss of RHR
shutdown cooling occurs with RCS temperature rising, in accordance with AOP-R.03,
RHR System Malfunctions?
A. RWST fill to RCS; bleed through Reactor Head Vents.
B. Normal charging to RCS; bleed through RHR letdown.
C~ Natural or forced RCS flow while steaming intact S/Gs .
D. Normal charging to RCS; bleed through the PZR PORVs.
A. Incorrect; With RCS intact, steaming will be the preferred method. Cold leg
manway will not be open.
B. Incorrect; Hot leg manway not open if in Mode 5 with RCS pressure higher than
atmospheric.
C. Correct. AOP-R.03 Section 2.3 will transition to Section 2.6 due to the inability to
restore RHR shutdown cooling. The stem states that the RCS is intact. With one
RHR train operable, TS 3.4.1.4 requires the two-SG level requirement to meet TS
heat sink requirements. #s 2 and 3 SGs satisfy the TS requirement as stated.
Therefore, Section 2.3 Step 7 RNO transitions to Section 2.6 since forced flow
cannot be re-established. Section 2.6 steps 5, 6, and 9.a are satisfied. Pzr level
greater than 20% cold cal satisfies step 7. Whether forced flow is established or
not, step 9 uses steaming from intact SGs.
D. Incorrect; Could potentially be used if required but would be an alternate heat
removal, not preferred .
(
Monday, May 07, 2007 3:23:15 PM
198
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledge of lowpower I shutdown Implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.
(
Question No.
Tier 3 Group 4
Importance Rating;
Technical Reference;
75
RO 3.3
Proposed references to be provided to applicants during examination;
None
Learning Objective;
OPL271 C358, Obj. B.2
OPL271 AOP-R.03; 4
Question Source;
Bank
Question History;
Sequoyah AOP R.02.B.2-4
Question Cognitive Level;
Higher
10 CFR Part 55 Content:
41.10
Comments;
SEQUOYAlI
NO
(
Time:
Source:
Cognitive Level:
Job Position:
Date:
Points:
BANK
illGIIER
4/2007
1.00
Version:
Answer:
o I 23 4 5 6 7 8 9
C B AAA B C B D A
Scramble Range: A - D
Source If Bank:
SEQUOYAl l BANK
Difficulty:
Plant:
Last 2 NRC?:
Monday, May 07, 20073:23:15 PM
199