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
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7 -07
Emergency Procedures I Plan Knowledge of annun ciators alarms and indications, and use of the respon se instructions. LOOP
KiA ju stification: applies since the applicant is required to discriminate between a loss of off-site power to the eSST -Start Buss-Unit
( boar d actuating the common alarm (1-AR-M1-B, B-3) vs. lock-o ut ac tuation from a Unit Board fault (87- 1C relay actuation of the 86-1C
jock-out relay).
Question No. 49
Tier 1 Group 1
Importance Rating: R03.3
Technical Referen ce: AR-M1B, B-3
Proposed references to be provided to applicants during examination: None
Learning Objective: OPL271AOP-P.01, B.7
Quest ion Source : New
Que stion History:
Question Cognitive Level : Highe r
10 CFR Part 55 Content: 41.7
Comments: editorial change to stem on location of 86 relay
MCS Time: Points: 1.00 Version: o I 234 56789
Answer: ADA BDBABCA Scramble Range : A - D
Source: NEW Source If Bank:
Cognitive Level: HIGHER Difficu lty:
Job Posi tion : RO Plant: SEQ UOYAH
Date: 412007 Last 2 NR C?: NO
(
Monday , May 07 , 2007 3:2 3:06 PM 100
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
51. 057 AK3 .01 00 1
( 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 requ ired 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 Auct ionee 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 manua lly 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 for the following responses as theyapplyto the Loss of Vital AC Instrument Bus: Actions contained in EOP
for loss of vital ac electrical instrument bus
( Question No. 50
Tier 1 Group 1
Importance Rating: R04.1
Technical Reference : AOP P.03
Proposed references to be provided to applicants during examination : None
Learning Objective: OPL271AOP-P.03 & 04, B.3
Question Source: New
Question History:
Question Cognitive Level : Higher
10 CFR Part 55 Content: 41 .7
Comments: corrected typo in stem.
( MCS Time: Points: 1.00 Version: oI 2 34 56789
Answer: A D DC B A B B B D Scramb le Range: A - D
Source : NEW Source If Bank:
Cog nitive Level: HI GHER Difficulty:
Job Position : RO Plant: SEQUOYAH
Date: 4/2007 Last 2 NRC? : 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 00 1
( 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 and l or monitor the follO'Ning as they applyto the Loss of DC Power: Cross-tie of the affected de bus with the alternate
supply
( Question No. 51
Tier 1 Group 1
Importance Rating: RO 3.4
Techni cal Reference: AOP-P.02
Proposed referen ces to be provided to applicants during examination: None
Learning Objec tive: OPL271AOP-P.02, B.8.b
Question Source: Bank
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Conten t: 41.10
Comments : editorial change to D (one hour) based on NRC comment.
MCS Time: Points: 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
So urce : BANK Source If Bank : SQN BANK
Cognitive Level: III GHER Difficulty:
Job Position: RO Plant: SEQU OYAll
Date: 4/2007 Last 2 NRC?:
(
Monday, May 07. 20073:23:06 PM 104
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
53 . 058 AAl.02 00 1
( Given the following plant cond itions :
- 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 lower ing slowly .
- Battery Charger 11 DC Output Breaker is tripped open .
- Reports from the AUO are that Battery Board II appea rs normal with the exception
of the Charger Output Breaker trip
Which ONE (1) of the followi ng describes the operability of the Battery Board , and the
action required?
A':" Declare Battery Board 11 INOPERABLE. Align the Spare Cha rger 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 load ing as necessa ry 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 becau se it is not inop due to charger disconnect.
C and 0 are incorrect becau se 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 conne cted to the board, it may
be functioning, but it may not be operable (Low Volts)
c.
Monday, May 07, 2007 3:23:07 PM 105
QUESTIONS REPORT
fo r SEQUOYAH 20 07 - NRC EXAM REV FINAL AS G IVE N 5-7-07
Ability to determine and interpret the following as theyapply to the Loss of DC Power: 125V de bus voltage, low/criticallow. alarm
( Question No. 81
Tier 1 Group 1
Importance Rating: SRO 3.6
Technical Reference: AR-M-01C,
Proposed referen ces to be provided to applicants during examination: None
Learning Objective: OPL271AOP-P.02, B.8.b & 9
Question Source: New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Content: 43.5,43.2
Comments:
MCS T ime: Points: 1.00 Version: o I 234 5 6 7 8 9
Answer: ADBCD AA CBB Scramble Range: A - D
Source: NEW Source If Bank:
Cognitive Leve l: IIlGHER Difficulty:
Job Position: SRO Plant: SEQUOYA H
Date: 4/2007 Last 2 NRC?: NO
l
Monday, May 07.20073:23:07 PM 106
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINA L AS GIVEN 5-7-07
54. 059 AL07 00 1
( 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 instrume nt failu res that wou ld cause
this transient? (consider each failure separately)
PT-1-33 PT-3-1
B~ failed HIGH failed LOW .
C. fai led LOW fai led HIGH.
D. failed HIGH failed HIGH .
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.
l 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
fo r SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability to predict and/or monitorchanges in parameters(to prevent exceeding design limits) associated with operating the MFW ccotrols
including: Feed Pump speed, including normal control speed for ICS.
( Question No. 18
Tier 2 Group 1
Importance Rating: R02.5
Technical Refere nce: 47W611-3-2
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 Conten t: 41.7 ,41.4
Comments: editorial change to answers to put in two column format. combined second two
bullets into one statement.
( MCS Time: Points: 1.00 Version: o I 2 3 4 5 6 7 8 9
Answer: B DA B B C C D C C Scramble Range: A - D
Source: BANK Source If Bank: SEQUOYAH BANK
Cognitive Level: HIGHER Difficuhy:
Job Position: RO Plant: SEQUOYAH
Dale: 412007 Last 2 NRC'!: NO
(
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 00 1
( Given the following plant cond itions :
- An accidental spill of the Monitor Tank has occurred in the Aux Build ing.
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 contam ination 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 the follo.vingconceptsas they apply to Accidental Liquid Ra<twaste Release: Biological
( effects on humans of various types of radiation, exposure levels that are acceptable for nuclear power plant personnel, and the units
used for radiation-intensity measurements and for radiation exposure levels
Question No. 60
Tier 1 Group 2
Importance Rating: R02.6
Technical Reference: SPP-5.1: RCI-15, Sects 6,7, 6.8, 6.12 & 6.13
Proposed reference s to be provided to applicants during examination: None
Learning Objective: RWT-0 10,
Question Source: New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Content: 41.12
Comments: removed second part of each answer based on NRC comment
MCS T ime: Po ints: 1.00 Version: oI 23456789
Answer. ABD CDADC BC Scramble Range : A - 0
Source: NEW Source If Bank:
Cogniti ve Level: HIGHER Difficu lty:
Job Pos ition : RO Plant: SEQUOYAH
Date: 4/2007 Last 2 NRC ?: 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
( Wh ich 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?
Monitored Location Unit of Measurement
A. Turbine Building Vent counts per minute
B:' Service Build ing Vent counts per minute
C. Turbine Building Vent mRem per hour
D. Service Building Vent 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. Mea sured in CPM, but is a monitored vent path .
(
Monday. May 07, 200 7 3:23 :07 PM 111
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FI NAL AS GIVEN 5-7-07
Knowledgeof the operational implications of the followi ng concepts as they apply to Accidental Gaseous Radwaste Release: Types of
( radiation, their units of intensity, and the location of sources of radiation in a nuclear power plant
Question No. 61
Tier 1 Group 2
Importance Rating: R02 .5
Technical Reference : O-AR-M12-B, A-5/A-6; ODCM, Section 1.1.2 requi rements; 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
Quest ion Source : Modified
Question History: SQN ODCM B.2-2
Question Cognitive Level: Lower
10 CFR Part 55 Content: 41 .13
Comments : modified question based on NRC comment.
MC S T ime: Points: 1.00 Version: o I 234 56789
Answer: BAAADB CDAB Scramb le Range: A - D
Source : MODIFIED Source If Bank:
Cognitive Level: LOWE R Difficulty:
Job Position: RO Plant: SEQUOYAH
Date: 4/2007 Last 2 NRC?: 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 the effect of a loss or malfunction of the following will haveen the AFW components: Pumps
( Question No. 19
Tier 2 Group 1
Importance Rating: 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.
MCS Tim e: Points: 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: BANK Source If Bank : WTS I
Cognitive Level: HIGH ER Difficult y:
Job Position: RO Plant: SEQUOYAl l
Date: 4/2007 Last 2 NRC? :
Monday, May 07 ,20073:23:07 PM 114
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 Inject ion 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 provi ded 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.
l
Monday, May 07, 2007 3:23:07 PM 115
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV F INAL AS GIVEN 5-7-07
Knowledge of the reasons for the following responses as theyapply to the Loss of Nuclear Service Water The conditions that will initiate
( the automatic opening andclosing of the SWS isolation valves to the nuclear service water coolers
Question No. 52
Tier 1 Group 1
Importance Rating: R0 3.2
Technical Referen ce: AOP-M.01 , section 2.4 step 8
Proposed references to be provided to applicants during examination: None
Learning Objective: OPL27 1AOP-M.01, B.8.c
Question Source: New
Questi on History:
Question Cognitive Level: Higher
10 CFR Part 55 Conten t: 41.8
Comments :
MC S Ti me: Points: 1.00 Version: o I 23 456789
Answer: B DAC BACA B D Scra mble Range: A - D
Source: NEW Source If Bank :
Cognitive Leve l: HIGHER Diffi culty:
Job Position : RO Plan t: SEQUOYAl I
Date: 4/2007 Last 2 NR C?: 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, 1-11 1operable.
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
Conduct of Operations: Knowledgeof conditions and limitations in the facility license.
Question Number: 20
Tier 2 Group 1
Importance Rating: 2.7
Technical Reference: TS Basis 3.8.2.2
Proposed references to be provided to applicants during examination: None
Learning Objective:
10 CFR Part 55 Content: 43.2
Comments:
MC S Time: Points: 1.00 Version: o I 234 5 6 7 8 9
Answer: AC D BA DBDCB Scramb le Range: A - D
Source: BANK Source If Bank:
Cognitive Level : LOWER Difficu lty:
Job Position: RO Plant: SEQUOYAH
Date: 4/2007 Last 2 NRC?: 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
Wh ich 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 V may be substituted for any other bank
B. Correct. Charger V is 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 and safetylimits..
( Question No. 21
Tier 2 Group 1
Importance Rating: RO 3.4
Technical Reference: TS 3.8.2.3
Proposed references to be provided to applicants during examination: None
Learning Objective: OPT200.DC, B.6
Quest ion Source: Bank
Question History:
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 LCO 3.8.2.3.
MCS Tim e: Points : 1.00 Version: o I 23 4 567 8 9
Answer: B B B DAD B A CA Scramble Range: A - D
Source: BANK Source If Bank : SQN BANK
Cognitive Level: LOWER Diffi culty:
Job Position: RO Plant: SEQUOYAlI
Date: 4/2007 Last 2 NRC?: NO
(
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
Knowl edge of ED/G systemdesign feature(s) and/or i n ter~lock(s) which provide for the follO'Ning: Trips 'While loading the EDfG
(frequency, 'IOltage , speed).
( Question No, 22
Tier 2 Group 1
Importance Rating: R0 3.8
Technical Reference: OPT200DG
Proposed references to be provided to applicants during examination: None
Learning Objective: OPL200DG Obj 4.i
Question Source: Bank
Ques tion History: SQN Bank
Quest ion Cognitive Level: Lower
10 CFR Part 55 Content: 41,7
Comments: Corrected typo in D
MCS T ime: Points: 1.00 Ve rsion: o I 2 34 56789
A nswer: DDD C DD A CAD Scramb le Range: A - D
Source: BANK Source If Bank : SQN BANK
Cognitive Level: LOWE R Difficulty:
Job Position: RO Plant: SEQUOYAH
Dat e: 4/2007 LasI 2 NRC?: NO
(
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 00 1
( Given the following plant cond itions:
Unit 1 is at 100%.
- A fire is in prog ress in the Contro l Build ing Cable Spreading Room .
- The Fire Brigade is on the scene and has requested backup assistan ce.
W hich ONE (1) of the following describes the correct pro cedure to be entered , and
how RCS boration will be monitored throughout the RCS cooldown after the reacto r is
tripped?
A'! Enter AOP-N.01, Plant Fires.
Initiate and monitor borat ion to cold shutdown cond itions in accordance with
AOP-C.04, Shutdown From Auxiliary Cont rol 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.0 1 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. Incorrec t. 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 to determine and Interpret the following as they apply to the Control 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 durin g examination: None
Learni ng Objective: OPL271AOP N.01 B.6
Question Source : New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Content: 43.5
Comments : corrected typo In C and D. Removed indication from Aux Control Room in A and
B.
MCS Time: Poi nts: 1.00 Version: o 1 23 4 5 6 7 8 9
Answer: ADAAD BADAA Scramble Range: A- D
So urce: NEW Source If Bank:
Cogn itive Level: IIIOIlER Difficulty:
Job Position: SRO Plant: SEQUOYAH
Date: 4/2007 Last 2 NRC? : NO
(
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 spread ing 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
person nel to perform applicable sections of AOP-C.04, Shutdown From Auxiliary
Control Room, Appendi x 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 personn el dispatched...
C. Incorrect. See A; EOPs are not applicable when evacuating MeR
D. Incorrect. A OP-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 App endix 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 the Interrelations between the Control Room Evacuation and the following: Reactor trip system
( Question No. 62
Tier 1 Group 2
Importance Rating: R03.7
Technical Reference: AOP C.04
Proposed references to be provided to applicants during examinat ion: 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 : Editor ial change to D wording to be similar to wording in the AOP .
MC S T ime: Points: 1.00 Version: o I 2 3 4 5 6 7 8 9
Answer: B B B A C AAA B D Scramble Range: A - D
Source : BANK Source If Bank : SQN BANK
Cognitive Level: LOWER Difficult y:
Job Position: RO Plant: SEQUOYAlI
Date : 412007 Last 2 NRC? : NO
(
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 runn ing.
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 relea se,
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 theeffect that a los s ormalfunction of the Waste Gas Disposal System will haveon the following: VenUlation system.
( Question No. 35
Tier 2 Group 2
Importance Rating: R02.7
Technical Reference: 0-50-77-15, Section 6.0 Step 9 and NOTE ; 47W611-77-4;
47W611 -30-6
Proposed references to be provided to applicants during examination : None
Learn ing 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
MCS T ime: Points: 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: BANK Source If Bank: SQN BANK
Cognitive Level: LOWER Difficulty:
Job Position: RO Plant: SEQUOYAH
Date : 412007 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 Mitigating Action
A. Loss of power to the Manually terminate S /G blowdown release .
radiation monitor (there is no automatic termination)
B~ Loss of power to the Ve rify automatic termination of
rad iat ion monitor S /G blowdown release .
C. High flow through the rad iation Verify automatic termination of
monitor S/G blowdown release.
D. High flow through the Manually terminate S /G blowdown release .
radiation monitor (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 malfunctions oroperations onthe PRM system: and(b) based on those predictions, use
procedures to correct, control, or mitigate the consequences of those matfunctions or operations: Erratic or failed power supply.
( Question No. 24
Tier 2 Group 1
Importance Rating: R0 2.5
Technical Reference: 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:
MCS T ime: Point s: 1.00 Version: o 1 23 4 5 678 9
Answer: B B D B A B C B B D Scram ble Range: A - D
Source: BANK Source If Bank: SQN BANK
Cogni tive Level : LOWER Difficulty:
Job Position: RO Planl: SEQUOYAH
Date: 4/2007 Last 2 NRC? : NO
(
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 belie ve that since RE-90-119
has its own sample pump, adequate sample flow to/from the rad monitor could be
independent of back pressure effe cts; see B belo w.
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 of activity 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 FI NAL AS GI VEN 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.
( Ques tion No. 23
Tier 2 Group 1
Importance Rating : R0 2.5
Tech nical Refer ence: 0-AR- M12-A , C-2; OPT200.RM, Slide 69 /70
Proposed references to be provided to appl icants during examination: None
Learning Objective: OPT200.RM, B.4
Question Source: New, 2007 ILT NRC Exam
Question Histo ry:
Question Cognitive Level: Lower
10 CFR Part 55 Content: 41.11
Comments:
MCS Ti me: Points : 1.00 Version: a I 2 3 4 567 8 9.
Answer: BADADDD D C A Scramb le Range: A - D
Source: NEW Source If Bank :
Cognit ive Level: LOW ER Difficulty:
Job Position: RO Plant: SEQUOYAH
Date : 4/2007 Last 2 NRC?: NO
(
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.
- Conta inment 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 restor ing the Core
Cooling CSF?
A. Depressurize the RCS by vent ing to Containment.
B. Initiate RHR flow to provide maximum cooling flow.
C. Rapidly depressuri ze 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 monitor the follO'Ning as they apply to a Inadequate Core Cooling: HPI System
Question No. 63
Tier 1 Group 2
Importance Rating: R04.2
Technical Referenc e: FR-C.1
Proposed references to be provided to applicants during examination: None
Learning Object ive: OPL271 FR-C.1, B.3
Question Sou rce: Bank
Question History: SQN Bank
Question Cognitive Level: Lower
10 CFR Part 55 Content: 41.10
Comments :
MCS Tim e: Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Ans wer : D AD B D D B CAB Scramble Range : A - D
Source: BANK Source If Bank: SQN BANK
Cognitive Level: LOWE R Difficulty:
Job Position: RO Plant : SEQUOY AH
Date; 4/2007 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 flo w, 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 , therefo re power factor, is adjusted to bring the CCW Motor to synchronous
rated spe ed. Discharge valve open ing, is limited until this adjus tment 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
appro ximately 5% open; Step 10.c directs placing the appropriate pump hands witch to
'START'; Step 10.d directs the AUO at appro ximately 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
fo r SEQUOYAH 20 0 7 - NRC EXAM REV FINAL AS GIVEN 5- 7-07
Conduct of Operations: Abil ityto perform specific system and integratedplant procedu res during ell modes of plant operation..
( Question No. 37
Tier 2 Group 2
Importan ce Rating: RO 3.9
Technical Reference: 0-SO-27-1
Proposed references to be provided to applicants during examination: None
Learning Objective: OPT200.CCW, B.4.g
Quest ion Source: New
Question History:
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.
MCS Time: Points: 1.00 Ve rsion: o12 34 5 6 7 89
Answer: B A ABC B C AA C Scramble Range: A * D
Source: NEW Source If Bank:
Cognitive Level: LOWE R Difficulty:
Job Position: RO Plant: SEQUOY AH
Date: 4/2007 Last 2 NRC?: 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 K I.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-si te 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 follow ing 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
blacko ut 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 runn ing
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
cons ider 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, May 07, 2007 3:23:09 PM 136
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledge of the physical connections and/or cause- effect relationships betweenthe SWS andthefollowing systems: ESF.
( Quest ion No. 25
Tier 2 Group 1
Importance Rating: R0 3.6
Techn ical Reference: 0-50-67-1, OPT200.ERC W , 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
Comments: need to look at procedure. Has different names for the selector switch.
MCS 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
So urce: BANK Source If Bank: SQ N BANK
Cognitive Level: HIGHER Difficulty:
Job Position: RO Plant: SEQ UOYAH
Date: 4/2007 Last 2 NRC?: NO
(
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 00 1
( 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 act ions necessary to RESTORE
Auxiliary Feedwater normal and meet design basis requirements fo llowing 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 A lignment of TO AFW LeV Backup Air Supply; isolate the
backup air supply and ma inta in bott le pressure at a min imum of 1500 psig.
C. Us ing 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. Us ing M.02, Loss of Co ntrol Air, Section 2.1 for Loss of Auxiliary Air; isolate the
bac kup air supply and ma intain 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. Incorre ct 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. 90
Tier 2 Group 1
Importance Rating: SRO 4.0
Technical Reference: 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
Comment s:
MCS T ime: Points: 1.00 Version: o 1 23 456789
Answer: AAAC A BC A D D Scramble Range: A - D
Source: lJANK Source ff Bank: SEQUOYAH BANK
Cognitive Level: LO WER Difficulty :
Jo b Position: SRO Plan t: SEQ UO YAH
Date: 4/2007 Last 2 NRC'! : NO
(
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.0 4 001
( 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 ind icating 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 cool ing 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 and the following systems: Coolingwater to
compressor.
( Question No. 26
Tier 2 Group 1
Importance Rating: R02 .6
Techn ical Reference: 1AR-M1 5-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
Ques tion Cognit ive Level : Higher
10 CFR Part 55 Content: 41.10
Comments: Editorial modification to A based on NRC comments . Revised B to ensure answer
is incorrect.
MCS Time: Points : 1.00 Version: o 1 2 34 5 6 7 8 9
Answer: C DC C D A AAAD Scramble Range: A - D
Source: BANK Source If Bank: SQN BANK
Cognitive Level: LOWER Difficulty:
Job Pos ition: RO Plant: SEQUOYAH
Date: 4/2007 Last 2 NRC?: NO
(
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 dispa tched 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 Wate r will maintain system
pressure at the normal standby value without Fire Pump operation.
B. The fire pump will not restart. Jockey Pumps will opera te to mainta in system
pressure at the normal sta ndby 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 pre vent 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 if pressure 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 on the Fire Protection System; and (b) based on those
predictions, use procedures to correct. control, or mitigate the consequences of those malfunctions or operations: Manual shutdown of
( the FPS.
Question No. 38
Tier 2 Group 2
Importance Rating: R0 2.9
Technical Reference: 0-SO-26 -1
Proposed reference s to be provided to applican ts during examination: None
Learning Objective : OPT200.HPFP, 6 .16.a
Questi on Source: New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Content: 41.10
Comments : editorial change to D. Removed greater than to make it incorrect.
MCS Time: Poi nts: 1.00 Version; o I 234 5 67 8 9
Answer: C CA CA CD D B D Scramble Range: A - D
Source : NE W Source If Bank:
Cognit ive Level: HIGHER Difficulty.
Job Position: RO Plant: SEQU OYAH
Date: 4/2007 Last 2 NRC? : 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 A l.OI 00 1
( 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?
Param eter Design Limit
A. Tempera ture 250°F
Bt Pressure 12 psig
c. Temperature 125°F
D. 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 containm ent setpoint
for pla cing 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 EXA M REV FINAL AS GIVEN 5-7-07
Abilityto predict and/or monitor changes in parameters (to prevent exceedingdesign limits) associated with operating the containment
( system controls including: Containment pressure, temperature. and humidity.
27
Question No.
Tier 2 Group 1
Importance Rating: R03.7
Techni cal Referen ce: 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
Questi on Cognitive Level: Higher
10 CFR Part 55 Content: 41.5
Comments :
MCS Time: Points: 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: BANK Source If Bank: IlARRlS 2005 NRC
Cognitive Level: HIGHER Difficuhy:
Job Position: RO Plant: SEQUOY Ali
Dale: 4/2007 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 of ABGTS is required operable if One Airlock door will be open.
Refueling does not have to stop if ABGTS 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
fo r SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledgeof the effectthat a loss or malfunction of the containment system will have on the following: Loss of containment integrity
( under refueling operations.
Question No. 28
Tier 2 Group 1
Importance Rating: R03.?
Technical Reference: TS 3.9.4
Proposed references to be provided to applicants during examinat ion: None
Learning Objective: OPT200 .CntmtStructure, B.6.c
Question Source : New
Question History:
Question Cognitive Level : Lower
10 CFR Part 55 Conten t: 41.10/43.2
Comments :
MCS Time: Poin ts: 1.00 Ve rsion: oI 234 56789
Answer: CC DA B D BCAB Scramble Range: A - 0
Source: NEW Source If Bank:
Cognitive Level : LOWER Difficulty:
Job Position: RO Plant : SEQUOYAH
Date: 4/2007 Last 2 NRC?: 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 00 1
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 Sp ray pump immed iately upon transition from ES-1. 1?
Containment Spray Pump
A. 1 CCP injecting via CCPIT In Service
B. 1 CCP injecting via CCPIT Stopped and placed in A-AUTO
C. 1 CCP injecti ng via seal injection Stopped and placed in A-AUTO
and normal charg ing
D~ 1 CCP injecting via seal injection In Servic e
and normal charging
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 G IVEN 5-7-07
Abilityto operate and I or monitor the following as they apply to the (5 1Termination) Desired operatingresults during abnormal and
( emergency situations.
Question No. 64
Tier 1 Group 2
Importance Rating: R03.8
Technical Refe rence : ES-1.1
Proposed references to be provided to applicants during examination : None
Learning Object ive: OPL271ES-1.1 , Objective 6
OPL273C502C; Obj. a.i, a.j
Question Source : Bank
Question History: SQN ES-1.1.B.1-2
Question Cogn itive Level : Higher
10 CFR Part 55 Conten t: 41.10
Comments:
MCS Time: Points: 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: BANK Source If Bank: SEQUO YAH BANK
Cognitive Level: HIGHER Difficulty:
Job Position: RO Plant: SEQUOYAH
Dale : 4/2007 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 lea k 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. Incorre ct. 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 5-7-0 7
Conduct of Operations: Kncwledq e of the purpose and function of majorsystem components and contro ls.
( Question No. 53
Tier 1 Group 1
Importance Rating: R0 3.2
Technical Reference: ECA-1.2
Proposed references to be provided to applicants during examination: None
Learning Objective: OPL271ECA-1.2 Objective 4
Question Source: New
Question History:
Question Cognitive Level: Lower
10 CFR Part 55 Content: 41 .10
Comments:
MC S Time: Point s: 1.00 Version:' o 1 23 456789
Answer: DB C A A A CBB C Scram ble Range: A - D
Source : N EW Source If Bank :
Co gni tive Level : LOWER Difficul ty:
Job P osition: RO Plant: SEQ UOYAH
Date: 4/2007 Last 2 NR C?: 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 respond ing to a Loss of Heat Sink per FR-H.1 , Response to Loss of
Secondary Heat Sin k.
- All Steam Generator W ide Range levels are Off-S cale 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 reestabl ish 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 setpo int.
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 reco ver heat sink. This minim izes 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 no t 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
Monda y. May 07, 2007 3:23 :11 PM 152
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowl edgeof the reasons for the followin g responses as they apply to the(Loss of SecondaryHeat Sink) Desiredoperating results
( during abnormal and emergency situations.
Question No. 54
Tier 1 Group 1
Importance Rating : R0 3.8
Technical Reference : FR-H.1 BD
Proposed referen ces to be provided to applicants during examination: None
Learning Objective: OPL271FR-H.1 Objective 4
Question Sou rce: Bank
Question History: WTSI Various previous NRC
Question Cognitive Level: Higher
10 CFR Part 55 Conten t: 41 .10
Comment s:
Mes Time: Points: 1.00 Version: oI 23456789
Answer: C A D B D B C B DA Scramble Range: A - D
Source: BANK Source If Bank : WTSI
Cognitive Level: Ill GHER Difficulty:
Job Position: RO Plant: SEQU OYAl I
Date: 412007 Last 2 NRC? : NO
(
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 00 1
( 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 of yellow 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 Core Cooling) Facility condttions and selection of
( appropriate procedures during abnormal and emergency operations .
Question No. 83
Tier 1 Group 2
Importance Rating: SRO 4.0
Technical Refere nce: EOP User's Guide, FR-C.3 step 1
Proposed references to be provided to applicants during examination: None
Learning Objective: OPL271 EPM-4, B.11.c
Question Source : New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Conten t: 43.5
Comments: Editorial change to Band 0 wording based on NRC comment
MCS T ime: Points: 1.00 Version: o123 4 5 6 7 8 9
Answer: D D A A C B CB A A Scrambl e Range: A - D
Source : NEW Source If Bauk:
Cogn itive Level: HIGHER Difficulty:
Job Position: SRO Plant: SEQUOYAH
Dale: 4/2007 Last 2 NRC?: NO
Monday, May 07, 2007 3:23:11 PM 155
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-S ite 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 requi rements prior to, and after the cooldown , and the minimum action require d
if Shutdown Margin requ irements 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 Cool down ;
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 Boratio n, to restore
Shutdown Marg in.
D. 1.6% delta k/k prior to RCS Cooldown;
1.0% delta k/k upon completion of RCS Cooldown ;
Perform borat ion in accordance with SO-62-7 , Boron Concentration Control, to
restore Shutdown Margin.
A. Incorrect. Correct boration procedure but required Shutdo wn Margins are reversed
from Tech Spec requirements.
B. Incorrect. required Shutdown Margin s are reversed from Tech Spec requirements.
Incorrect boration procedure. Incorrec t 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.
c.
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 operations and safetylimits.
( KA Match: the KA is matched since the
Question No. 84
Tier 1 Group 2
Importance Rating: SRO 4.1
Technica l Reference: EA-68-4, TS 3.1.1.2
Proposed references to be provided to applicants during examination: None
Learning Objective: OPL271ES-O.2. 6.6.a
Question Source: New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Conten t: 43 .5
Comments:
MCS Time: Po ints: 1.00 Version : oI 2 345 6 7 8 9
Answer: C B C BAA B C I3A Scramble Range: A - D
Source : NEW Source tf Bank:
Cognitive Level: HIGHER Difficulty:
Job Position: SRO Plant: SEQUOYAII
Date: 4/2007 Last 2 NRC?: NO
Monday, May 07,20073:23:11 PM 157
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
c
80 . Ell EK3.2 00 1
Which ONE (1) of the follow ing describes two objectives of proce dure ECA-1 .1, Loss
A. Ensure only one train of SI in serv ice 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 reci rculation
capability and stab ilize RCS temperature to minimize RCS inventory requirements .
D~ Redu ce 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 requ ired 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 plaus ible
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: Minim izes depletion of RWST,
depressurize RCS to minimize break flow and cause acc umulator injection , and
cont inue attempts to resto re 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
Knowl edge of the reasons for the following responses 8 5 they apply to the (Loss of Emergency Coolant Recirculation) Normal . abnormal
( and emergency operating procedures associated with (Loss of Emergency Coolant Recirculation).
Question No. 55
Tier 1 Group 1
Importan ce Rating: R0 3.5
Technical Reference: ECA-1.1 and basis
Proposed references to be provided to applicants during examination: None
Learning Object ive: OPL271 ECA-1 .1 Objective 4
Question Source : Bank
Question History : WTSI Last Exam VCS 06 Audit
Question Cognit ive Level: Lower
10 CFR Part 55 Content: 41.10
Comments:
MCS Time: Poin ts: 1.00 Version: o I 23 4 5 6 78 9
Answer: D D BBA DDC DC Scramble Range: A - D
Source: BANK Source If Dank:
Cog nitive Level: LOW ER Difficulty:
Job Position: RO Plant: SEQUOYAH
Date : 4/2007 Last 2 NRC?: NO
Monday, May 07,20073:23:11 PM 159
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
81. E l2 G2.4 .3 1 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 ressu rization of All Stea m 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. Ra ise 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 AF W flo w 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 of AFW flow, FR-H. 1 actions
would not be performed
l
Monday, May 07,2007 3:23:11 PM 160
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Emergency Procedures I Plan Knowledgeof annunciators alarms and indications. and use of the response instructions
( Quest ion No. 56
Tier 1 Group 1
Importance Rating: RO 3.3
Technical Reference: ECA-2.1, AR M3
Proposed references to be provided to applicants during examination: None
Learning Objective: OPL271ECA-2.1, B.6.a
Quest ion Source: New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Conten t: 41.10
Comments:
MC S Time: Points: 1.00 Version: o I 2 3 4 5 6 7 8 9
Answer: C BA B CC B B A B Scramble Range: A - D
So urce : NE W Source If Bank:
Cognitive Level: HI GH ER Difficulty:
Job Position: RO Plan t: SEQ UOYAI I
Date: 4/2007 Last 2 NRC?: NO
Monday. May 07. 2007 3:23:12 PM 161
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 if pressure 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.
l
Monday, May 07,20073:23:12 PM 162
QUESTIONS REPORT
for SEQUOYAH 2007 - N RC EXAM REV FINAL A S GIVEN 5- 7-07
KnO'Nledge of the jnteereaucoe between the(Steam Generator Overpressure) and the foilOVo1ing: Ccmponents,and functions of control
( and safetysystems, Including jnstrornertauoo. signals. interlocks . failure modes, and autcmatic and manual features
Question No. 65
Tier 1 Group 2
Importance Rating: R0 3.0
Technica l Reference: 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
Questio n Cognitive Level: Higher
10 CFR Part 55 Content: 41.10
Comments:
MCS Time: Point s: 1.00 Version: oI 2 34 567 89
Answer: BDD AD D C AA C Scramble Range: A - D
Source: NEW Source If Bank:
Cognitive Level: HIGHER Diffic ulty:
Job Position: RO Plant: SEQ UOYAH
Date : 412007 Last 2 NR C? : NO
Monday, May 07, 2007 3:23:12 PM 163
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
83 . E I S 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.
Uppe r and Lower Conta inment 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 Conta inment Flooding.
C. Transi tion 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 yello w 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
l
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 expl ain and apply all systemlimits and precautions.
( Question No. 85
Tier 1 Group 2
Importance Rating: SRO 3.8
Technical Reference: FR-Z.2 background, FR-O
Proposed references to be provided to applicants during examination: None
Learning Objective: OPL271FR-Z.2, 8 .5
Question Source : New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Content: 43.5
Comments:
MCS Time: Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer: BD A C CDD C CD Scramble Range: A - D
Source : NEW Source If Bank:
Cognitive Level: LOWER Difficulty:
Job Position: SRO Plant: SEQUO YAH
Date: 4/2007 Last 2 NRC?: 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/Un it Supervisor ONLY
C. Security or Duty Operations Manager ON LY
D. Security or Duty Plant Manager ONLY
A. Incorrect. SM/US are also issued keys
B. Correct. The Shift Manager/U S holds the Vital Area Acce ss key, and issues it as needed.
[Refer to NSDP-8 Sect 3.0 B: *...AII unissued keys, locks , and cores are stored and
ma intained in locked repos ito ries or in cabinets und er the direct control of Se cu rity or the
Shift Man ager (SM) to reduce the proba bility 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
Knowled ge of facility requiremen ts for controlling vi tali controlled access.
( Question No. 95
Tier 3 Group 1
Importance Rating: SRO 2.9
Technicai Reference: SPP-1.3 ; NSDP-8
Proposed references to be provided to applicants during examination: None
Learning Objective : OPL271 SECURITY Objective 4
Question Source: New
Question History:
Question Cognitive Level: Lower
10 CFR Part 55 Content: 43.5
Comments:
MCS Time: Points: 1.00 Version: o I 2 3 4 5 6 7 8 9
Answer: B CA C AB CB A A Scramble Range: A - D
Source: NEW Source If Bank:
Cognitive Level: LOWER Diffi culty:
Job Positi on : SRO Plant: SEQUOYAH
Date : 4/2007 Last 2 NRC?: NO
l
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 requ ired any time that requ ired informat ion 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 appro ved, and the log is
annotated with "LA TE 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
Ability to make accurate. clear and concise logs. records . statusboards. and reports .
( Question No. 67
Tier 3 Group 1
Importance Rating : R02.9
Technica l Referenc e: OPDp*1 , Appendi x E, section E
Proposed references to be provided to applicants during examination: None
Learning Objective: OPL271 C209 Obje ctive 9
Question Source: New
Question History:
Question Cognitive Level : Lower
10 CFR Part 55 Content: 41.10
Comments:
MCS T ime; Points: 1.00 Version: o 1 2 345 6789
Ans wer: BCDC BBDBA C Scramble Range: A - D
Source: NEW Source If Bank:
Cogniti ve Level: LOWER Difficulty;
Job Position; RO Plant: SEQUOYAH
Date; 4/2007 Last 2 NRC'!; 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 licens e condition or technica l 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 reaso n for invoking the rule, but Plant
Manager concurrence or appro val 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 all modes of plant operation.
( Que stion No. 66
Tier 3 Group 1
Importance Rating: R03.0
Technical Reference: OPDP-1 , Appendi x F
Proposed references to be provided to appli cants during examination: None
Learning Objec tive: OP1271C209, B.8
Question Source: Ban k
Que stion History:
Question Cogn itive Level : Lower
10 CFR Part 55 Con ten t: 41.10
Comm ents :
MCS Time : Point s: 1.00 Version: o 1 234 5 6 7 8 9
Answer: A AC B DD B B AA Scramble Range: A - D
Source : BANK Source If Bank: WTS I
Cognitive Leve l: LOWER Difficully:
Job Position: RO Plant: SEQUOYAH
Date : 4/2007 Last 2 NRC'!: NO
c.
Monday, May 07,2007 3:23:12 PM 171
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
87 . G2.1.21 00 1
t: 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 Contro l Room ONLY
B. Main Control Room, Operations Field Office ONLY
C. Main Contro l 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
Ability to obtain and verify controlled procedure ropy.
Question No. 68
Tier 3 Group 1
Importance Rating: RO 3.1
Techn ical Reference: SPP-2.2
Proposed references to be provided to applicants during exam ination : None
Learning Obje ctive: OPL27SPP-2.2 Objective 2 and 5
Question Source : Bank
Quest ion History:
Question Cognitive Level : Lower
10 CFR Part 55 Conten t: 41.10
( Comments:
Monday, May 07, 2007 3:23:13 PM 172
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
r MCS
Source:
T ime: I
NEW
Cognitive Level: LOWER
Points: 1.00 Version : 0 I 2 3 4 5 6 7 8 9
Answer: AAA DDBCC CD
Source [fBank:
Difficulty:
Scramble Range: A - D
Job Position: RO Plant: SEQUOYAH
Date : 412007 Lasl2 NRC?: NO
Monday, May 07, 2007 3:23:13 PM 173
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
88. G2.1.7 001
( Given the following plant conditions:
- A Normal Plant cooldown is in progress.
- The following table is a plot of the cooldown :
0800 547"F 0945 425°F
0815 530°F 1000 395 °F
0830 520°F 1015 382°F
0845 505°F 1030 364°F
0900 498°F 1045 340°F
0915 478°F 1100 320°F
0930 447"F 1115 220°F
Which ONE (1) of the following describes the first time that the Techn ical Specificat ion
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 fract ure 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 lim its that prov ide a margin to brittle failure of
the reactor vesse l and piping of the reactor coolant pressure boundary (RCPB).
The vessel is the component most subject to brittl e 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 f unctions. 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
fo r SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability toevaluate plant performance and make operational judgments basedon operating characteristics, reactor beha-.Aor. and
( instru ment interpretation.
Question No. 94
Tier 3 Group 1
Importance Rating : SRO 4.4
Technical Reference : 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:
MCS T ime: Points: 1.00 Version: oI 23456789
Answer : CBCC BCB0 C C Scrambl e Range: A - D
Source: BANK Source If Ban k: ROBINSON 2007 NRC
Cognitive Leve l: HIGHER Difficulty:
Job Position: SRO Plant: SEQUOYAII
Date: 412007 Last 2 NRC?: NO
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 condit ions:
Unit 2 is currently in MODE 4.
At 0900 today, it is discovered that a routine 24-hou r 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 Techni cal 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 FI NAL AS G IVEN 5-7-07
Knowledgeof surveillance proceclures.
( Question No. 69
Tier 3 Group 2
Importance Rating: RO 3.0
Technica l Reference : TS 4.0.1 . TS 4.0.3
Proposed referenc es to be provided to applicants during examination: None
Learning Objective: OPL271SPP-2.2 Objective 4
Quest ion Source: Bank
Question History:
Question Cogniti ve Level: Lower
10 CFR Part 55 Content: 41.10
Comments:
MCS Time: Poin ts: 1.00 Version: o 1 234 5 6 7 8 9
Answer: ABC BDCA B B D Scramble Range: A - D
Source : NE W Source If Bank:
Cognitive Level: LOWER Difficulty:
Job Position: RO Plaut: SEQUOYAlI
Date : 412007 Last 2 NRC? : 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 00 1
( Wh ich ONE (1) of the following describes the requirement for logging of LCO's in
accordan ce 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 require d
A incorre ct. 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 2 4 states: The US/designee is responsible for logging the entry
and exit fro m 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
Trac king Log. The Unit Log shall be the official log for LCOs. Tim es and dates entered on
his/her log shall be used as the official time/date for TS LCO act ion 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 EXA M REV FINAL AS GIVEN 5-7-07
Ability to track limiting conditions for operations.
( Question No. 70
Tier 3 Group 2
Importance Rating: R0 2.6
Tech nical Reference: OPDP-8
Proposed refere nces to be provided to applicants during exam ination : None
Learning Objective: OPS271OPDP-8 Objective 6
Question Source: New
Question History:
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
MCS Time: Points: 1.00 Ver sion: oI 2 34 567 89
Answer: BD C DDD A AB A Scramb le Range: A - D
Source: NEW Source If Bank :
Cognitive Level: LOWER Difficulty:
Job Position: RO Plant: SEQUOYAH
Date: 412007 Last 2 NRC ?: NO
l
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 00 1
( 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 requ irements.
Question No. 71
Tier 3 Group 2
Importance Rating: R02.5
Technical Reference: TS 3.9.3
Proposed references to be provided 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
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
MCS Time: I Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
( Source: BANK
Answer; A A C D BA B D C B Scramble Range: A - D
Source If Bank: SEQUOYAH BANK
Cognitive Level: LOWER Difficulty:
Job Position: RO Plant: SEQUOYAH
Date: 4/2007 Last 2 NRC?: NO
(
Monday, May 07, 2007 3:23;13 PM 181
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
92 . G2.2.5 00 1
( Given the following plant conditions:
- A plant des ign 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 follo wing describes the final management position, by title ,
required to approve the change prior to implementation?
A'! Plant Manager
B. Site Vice Pres ident
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.
l
Monday, May 07,2007 3:23:13 PM 182
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXA M REV FINAL AS GIVEN 5-7-07
Knowleclge of the process for makingchanges in the facility as described in the safety analysis report.
Question No. 96
Tier 3 Group 2
Importance Rating: SRO 2.7
Techn ical Reference: SPP-9.3
Proposed references to be provided to applicants during examination: None
Learning Objective: OPL271 C209, 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:
MCS Time: Points: 1.00 Version: oI 234 567 8 9
Answer: A D B B C C B C B B Scramble Range: A - D
Source: BANK Source If Bank: SEQUOYAH BANK
Cognitive Level: LOWER Difficulty:
Job Position: SRO Planl: SEQUOYAH
Date: 4/2007 Last 2 NRC?: NO
l
Monday, May 07,20073:23:14 PM 183
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
93 . G2.2.9 00 1
( 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.
l
Monday. May 07, 2007 3:23:14 PM 184
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINA L AS GIVEN 5-7-07
Knowleclge of the process for determining if the proposed change, test or experiment increases the probability of occurrence or
consequencesof an accident during the change, test or experiment.
( Question No. 97
Tier 3 Group 2
Importance Rating : SRO 3.3
Technical Reference: 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
MCS T ime: 3 Points: 1.00 Version: o I 2 3 4 5 6 7 8 9
Answer: D DDDDD D DDD ScrambleRange:A- D
Source : BANK Source If Bank: SEQ UOY AH BANK
Cogn itive Level: LOWER Difficulty:
Job Position: SRO Plant: SEQUOYAH
Date : 412007 Last 2 NRC'!: NO
Monday, May 07,2007 3:23: 14 PM 185
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
1 --o-,.,---:--.,....--c--~--------------------,
94 . G2.3...:..:10,-,0",0-,-
( 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 Techn ical 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 IA W 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 pla cing
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
fo r SEQUOYAH 2007 - NRC EXAM REV FIN AL AS GIVEN 5-7-07
Ability 10 perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
( Question No. 73
Tier 3 Group 3
Importance Rating: RO 2.9
Technical Referenc e: TS 3.4.8, AOP R.06
Propose d 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
Comme nts:
MCS Time: Points: 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: BANK Source If Bank : WTSI
Cognit ive Level: II1GHER Difficulty;
Job Position : RO Plant: SEQUOYAl l
Date: 4/200 7 Last 2 NRC ?: NO
l
Monday. May 07. 2007 3:23:14 PM 187
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
95 . G2.3.200 1
( 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.
- Tim e 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 resp irator will be zero.
- A dose rate of 40 mremlhr will be received whil e placing the
shield ing .
- All tasks will performed by one worker, including initial placement of
shielding , if requi red .
- Shielding can be placed in 15 minutes with or without a respirator.
- The shiel ding will not be removed
Which ONE of the following wou ld result in the lowest whole body dose?
A. Conduct task WITHOUT respirator or shield ing .
B. Conduct task WITH respirator and WITHOUT shielding.
C. Place shiel ding 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
l personnel exposure.
Monday, May 07, 2007 3:23:14 PM 188
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
MCS 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 : BANK Source If Bank: WTSI
Cognitive Level: HIGHER Difficulty: C/A(2.9/3.3)
Job Position: RO Plant: SM0530 1
Date: R Last 2 NRC?: MC/SDR
Mo nday, May 07,20073:23:14 PM 189
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
96. 02 .3.4 00 1
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 of radiation 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.
l
Monday. May 07. 2007 3:23:14 PM 190
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FI NAL AS GIVEN 5-7-07
Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
( Question No. 98
Tier 3 Group 3
Importance Rating: SRO 3.1
Tech nical Reference: EPIP 15
Proposed references to be provided to applicants dur ing examinat ion: None
Learning Objective: OPL271 C198REP Objective 1.f
Question Source: Modified
Question History: Robinson 2007 NRC Exam
Question Cognit ive Level: Higher
10 CFR Part 55 Content: 43.5
Comments:
MCS Time: Points: 1.00 Version: o I 2 3 4 5 6 7 8 9
Answer: DDADD C B AD D Scramble Range: A - D
So urce: MO DIFIED Source If Bank:
Cognitive Level: HIGHER Difficulty:
Job Position: SRO Plant: SEQUOY AH
Date: 4/2007 Last 2 NRC'!: NO
Monday, May 07,2007 3:23:14 PM 19 1
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-0 2 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 Action Required
A. sprinkler flow occurs with or without a Fire Brigade is NOT immediately
heat source. dispatched .
B~ sprinkl er flow occurs ONLY with a Immediately dispatch the Fire
heat source. Brigade.
C. sprinkler flow occurs with or without a Immediately dispatch the Fire
heat source . Brigade.
D. sprinkler flow occurs ONLY with a Fire Brigade is NOT immediately
heat source. dispatched .
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.
l
Monday, May 07, 2007 3:23:14 PM 192
QUESTIONS REPORT
fo r SE QUOYAH 200 7 - NRC EXA M REV FINAL AS GIVEN 5-7-07
Knowledge of fire protection procedures.
( Question No. 74
Tier 3 Group 4
Importance Rating: R0 2.9
Technical Reference: 0-SO-13-1 ; 0-A R-M -29
Proposed references to be provided to applicants during examination: None
Learning Objective: OPT200.HPFP B.1 6.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:
MCS Time: 3 Points: 1.00 Versi o n: o I 2 345 6789
Ans we r: B CACD C B CAD Scramble Range: A - 0
Source : MODIFI ED Source If Bank: SEQUOYAH BANK
Cognitive Level: HIGHER Difficulty:
Job Position: RO Plant: SEQUOYAH
Date: 4/2007 Last 2 NRC? : NO
l
Monday, May 07,20073:23:14 PM 193
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.
Wh ich 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 condit ions 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.
l
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 Wh ich events related to system operations/status should be reported to outside agencies .
( Question No. 100
Tier 3 Group 4
Importance Rating: SR03.6
Technical Reference : EPIP-1
Proposed references to be provided to applicants during examination: EPIP-1
Learning Objective: OPL27 1C168 Objective z.c
Question Source : New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Content: 43.5
Comments :
MCS Time : Points: 1.00 Version: oI 2 34 5 6 7 89
Answer: C BC D D DA B CA Scramble Range: A - D
Source: NEW Source If Bank:
Cognitive Level: III GHER Difficulty:
Job Position: SRO Plant: SEQU OYAH
Date: 412007 Las t 2 NRC?: 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% po wer 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
fo r SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability to perform without reference to procedures thos e actions thatrequire immediate operation of system components andcontrols .
( Question No. 99
Tier 3 Group 4
Importance Rating: SR0 4.0
Technical Reference: ARPs, E-O
Proposed references to be provided to applica nts 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:
MCS Time: Points: 1.00 Version: o I 2 3 45 6 7 8 9
Answer: C C C AD ADDDD Scramble Range: A - D
Source: BANK Source If Bank: WTSI
Cognitive Level: HIGHER Difficulty:
Job Position: SRO Plant: SEQUOYAH
Date: 412007 Last 2 NRC?: NO
(
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.
- Tra in "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 poten tially be used if required but would be an alternate heat
remo val, not preferred .
(
Monday, May 07, 2007 3:23:15 PM 198
QUESTIONS REPORT
fo r SEQUOYAH 2007 - NRC EXAM REV FINAL AS G IVEN 5-7-0 7
Knowledge of low power I shutdown Implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.
( Question No. 75
Tier 3 Group 4
Importance Rating; RO 3.3
Technical Reference; AOP-R.03
Proposed references to be provided to applica nts during examina tion; None
Learn ing Objective; OPL271 C358, Obj. B.2
OPL271 AOP-R.03; 4
Question Source; Bank
Question History; Sequ oyah AOP R.02.B.2-4
Question Cognitive Level; Higher
10 CFR Part 55 Content: 41 .10
Comments;
MCS T ime: Poin ts: 1.00 Version: o I 23 456789
Answer: C B AAA B C B D A Scramble Range: A - D
Source: BANK Source If Bank: SEQUOYAl l BAN K
Cognitive Level: illGII ER Difficul ty:
Job Position: RO Plant: SEQUOYAl I
Date: 4/2007 Last 2 NRC?: NO
(
Monday, May 07, 20073 :23:15 PM 199