ML071490433
| ML071490433 | |
| 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: ML071490433 (100) | |
See also: IR 05000327/2007301
Text
Final Submittal
(Blue Paper)
SEQUOYAH APRIL/MAY 2007 EXAM
EXAM NOS. 05000327/2007301
AND 05000328/2007301
APRIL 9 - 11, 2007 AND
MAY 9, 2007 (writte n)
Combined RO/SRO Written Exam with KAs,
Answers, References, and Analysis
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
1 . 001 A2.12 001
( Given the followi ng plant conditions:
A reactor startup, using control rods, is in progress per 0-GO-2, Unit Startup
From Hot Standby to Reactor Critical.
RCS boron concentration value used in the ECP calculation is 1100 ppm.
Actual current RCS boron concentration is 1000 ppm.
W hich ONE (1) of the following describes the correct actio n?
The actual critica l rod position will be.......
A. LOWER than estimated. Immediately initiate Emergency Boration in accordance
with EA-68-4, Emergency Boration.
B. HIGHER than estimated. Immediately initiate Emergency Boration in accordance
with EA-68-4 , Emergency Boration.
CY LOWER than estimated. Insert Control Banks and recalculate the ECP prior to
re-in itiating the startup if it becomes apparent that criticality will occur >1000 pcm
below the Estimated Critical Rod Position.
D. HIGHER than estimated . Insert Control Banks and recalculate the ECP prior to
c re-initiating the startup if it becomes appa rent that criticality will occur >1000 pcm
above the Estimated Critical Rod Position.
A. Incorrect. Correct effect; wrong action- per O-GO-2, Sect 5.2 and Appendix D
B. Incorrect. Incorrect effect, and wrong action.
C. Correct. With actual boron less than expected, it will take less reactivity added to reach
criticality. Startup would be aborted according to D-GO-2; it directs plant management
notifications, ECG re-evaluation/recalculation and performance of Appendix 0 , Actions if
Reactor Startup Must Be Aborted, which directs the operators to fully insert all control bank
rods.
D. Incorrect. Incorrect effect. Consistent with required action
(
Monday, May 07, 2007 3:22:57 PM 1
QUESTIONS REPORT
fo r SEQUOYAH 2007 - NR C EXA M REV FINAL AS G IVEN 5-7-0 7
Ability to(a) predict ee impacts d the following malfunction or operations on the e ROs. and (b) based on eeee predietions, use
( procedures 0 corect. CQ'ltrol , or miti9atethe consequences of Ihose ~ or ope-ations: Erroo e0u5 ECP calcUation.
Question No. 91
Tier 2 Group 2
Importance Rating: SRO 4.2
T echnical Reference : 0-SI-NUC-OOO-00 1.0 R5; O-GO-2;
P roposed refe rences to be provided to applicants durinq examination: No ne
Learning Objective: OPT200RDCNT. B.5.a. OPL271GO-2. B.4
Que stion Source: New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Content: 43.5
Comments:
( MCS Time: Points: 1.00 Version :
Answer.
o 1 23 456789
CCCCACC BA B Scramble: Range: A - 0
Source: NEW Source If Bank:
Cognitive Level: HIGHER Difficulty:
Job Position: SRO Plant: SEQUOYAI I
Dale: 4/2007 Last 2 NRC?: NO
(
Monday, May 07, 20073:22:57 PM 2
QUE STIO NS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
2 . 001 AAl .04 001
( Given the following plant conditions :
Unit 1 ha s just reached 90% power after a linear power asce nsion from 50%
over the last four hours.
Control Bank D continues to withdraw with no motion demanded.
W hich ONE ( 1) of the following describes the initial effect on the unit?
A. Reactor Power decreases AND OT Delta T setpoint dec reases
B. Reactor Power decreases AND OT Delta T setpoint increases
C~ Reactor Power increases AND OT Delta T setpoi nt decreases
D. Reactor Power increases AND OT Delta T setpoint increases
A-Incorrect. Reactor Power response is incorrect; Control Rod withdrawal results in
Hot leg temperature rise, reactor power increase due to the po sitive reactivity being
added with no additional RCS heat removal . OTdeita T setpoint response is correct;
OT and OP delta T setpoints will lower as power and temperature rise.
B-Incorre ct. Reactor Power response is incorrect; Control Rod withdrawal results in
( Hot leg temperature rise, reactor powe r increase due to the posttive reactivity being
added with no addftional RCS heat remo val . OTdeitaT setpo int response is
incorrect; OT and OP delta T setpoints will lower as power and temperature rise.
C-Correct. Control Rod withdrawa l results in Hot leg temperature rise and reactor
power increase due to the positive reactivity being added with no additional RCS
heat removal. OTdeltaT setpoint response is correct; OT and OP delta T setpoints
will /ower as power and temperature rise.
D-Incorrect. Reactro Power respo nse is correc t; Control Rod wfthdrawal results in Hot
leg temperature rise and reactor power increase due to the positive reactivity being
added with no addftional RCS heat remo val. OTdeitaT setpoint response is
incorrect; OT and OP delta T setpoints will/ower as power and temperature rise.
(
Monday. May 07,2007 3:22:57 PM 3
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
( Abi lity 10detennine and interpret !he folowing as It1ey apply to ee Continuous Rod Withd rawal : Reactlf power and its lJend
Question No . 57
Tier 1 Group 2
Importance Rating : R04.2
Te chnical Refere nce : T&AA
Proposed referen ces to be provided to applicants during exa mination : None
Learning Objective: OPL271CGFES Attachment 16 Objective 20
Question Source: Bank
Question History: Robinson 200 7 Editorially Modified
Question Cognitive Level: Higher
10 CFR Part 55 Content: 41.5
Comments: modified bullet in stem
MCS Time: I Points: 1.00 Version: oI 23 45 67 89
Answer: C C C A D D A D DC Scramble Range:A- D
( Source :
Cognitive Level: HIGHER
BANK Source If Bank:
Difficu lty:
ROBINSON 2007 NRC
Job Position : RO Plant: SEQUO YAJ I
Date: 412007 Last 2 NRC!: NO
(
Monday, May 07, 2007 3:22:57 PM 4
QUESTIONS REPORT
for SEQUOYAH 200 7 - NRC EXAM REV FINAL AS GIVEN 5-7-07
3 . 001 K2.03 001
( Which ONE ( 1) of the following is the primary source of power to the Rod Co ntrol Logic
Cabin ets?
A~ Rectified AC from the Rod Drive MG output.
B. Rectified AC from 120 VAC Instrum ent Bus
C. 125 VDC stepped down from station battery boards
D. 250 VDC stepped down from station battery boa rds
A. Correct.
B. Incorrect. Backup source is this supply
C. Incorrect. Correct that it DC; incorrect supply. Plausible since 125v is supplied to
the Rod Control system via the shunt trip coil on the RTBs and as control power to
the MG set output breakers that are opened locally following an ATWS condition.
D. Incorrect. Correct that it is DC; incorrect supply. Plausible since 250v DC is used as
control power to the MG set motor breakers that are opened locally following an
A7WS condition.
(
KncM1edge d bus po.ver supplies to the loIIcM1ng: One-line diag'a'n of pclWEf supplies to Ioojc circuits .
Que stion No. 29
Tier 2 Group 2
Importance Rating: R0 2.7
Technical Reference: Rod Control SD. Pg 32; 1.2-45N777-3 r17
Proposed references to be provided to applicants during examination: None
Learning Objective: OPL200RDCNT Objective 4
Question Source: New
Question History:
Question Cognitive Level: Lower
10 CFR Part 55 Content: 41 .6
Comments:
( MCS Time: Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Answer: ACA B CC D D BC Scramble Range: A - D
Monday, May 07,20073:22:57 PM 5
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Source : NEW Source If Bank:
( Cognitive Level :
Job Position:
LOWER
Difficulty:
Plant: SEQUOYAH
Date: 412007 Last 2 NRC?: NO
(
(
Monday, May 07, 2007 3:22:57 PM 6
QUESTIONS REPORT
for SEOUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
4 . 003 K4.04 00 1
( On a loss of CCS to an RCP thermal barrier heat exchanger, which ONE (1) of the
following choices contains parameters that indicate proper seal injection in accordance
with AOP-M.03, Loss of Component Cooling Water?
Seal Injection Flow veT Outlet Temperature
A. 6G PM 126* F
B. 9 GPM 135*F
12 GPM 128* F
D. 14 GPM 125*F
A. Incorrect. Seal Inj ection flow too low per the referenced procedure.
B. Incorrect. VCT temperature too high per the referenced procedure.
C. Correct. 8-13 GPM flow to seals and less than 130 degree s F from VCT is the
requirement if TBHX cooling is lost per the referenced procedure.
D. Incorrect. Seal Inj ection flow too high per the referenced procedure.
(
Knowledge of Re ps design leature( s ) and/or interlock(s) which proWje for the folICM'ing: Adequate cooling of Rep mob" and seals.
Question No. 1
T ier 2 Group 1
Importance Rating: R0 2.8
Technical Reference: AOP-M.03
Proposed references to be provided to applican ts during exa mination: None
Learning Obje ctive : OPL271AOP-M.03 Objective 6
Question Source: New
Q ue stion History:
Question Cognitive Level: Lower
10 CFR Part 55 Content: 41 .3
( Comments: Modified wording in stem to include AOP-M.03 and changed 0 temperature from
125 to 132 to ensure it is incorrect.
Monday, May 07,20073:22:57 PM 7
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIV EN 5-7-07
Mes T ime: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
( Source: NEW
Ans wer. C AC BCA D BA B
Source If Bank :
Scramble Range: A * D
Cogn itive Level: LOWER Difficulty:
Job Position: RO Plant: SEQUOYAII
Date: 4/200 7 Last 2 NRC'? : NO
(
(
Monday, May 07, 2007 3:22:57 PM 8
QUESTIONS REPORT
for SEQUO YAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
5. 004 A2.03 00 1
( Given the following pla nt conditions:
Unit 1 is at 100% power.
All control systems are in normai alignment.
Charging fiow is 92 GPM and rising.
1-TI-62-71, Regen HX Outlet Temp - Letdown, has decreased 5°F from its
steady state value.
VCT level is 33% and lowering.
PZR level is 59% and lowering slowly.
RCS temperature is 578°F and stable.
Which ONE (1) of the following describes the effect on the unit and the action required
in accordance with AOP R.05, RCS Leak and Leak Source Identification?
A. RCS leakage is from the charging line downstream of the regenerative heat
exchanger. Make a contai nment entry to determine if the leak is isolable .
B~ RCS leakage is from the charging line downstream of the regenerative heat
exchanger. Isolate Charging and Letdown.
C. RCS leakage is from the charging line upstream of the regenerative heat
exchanger. Initiate an investigation to determine if the leak is isolable.
( D. RCS leakage is from the charging line upstream of the regenerative heat
exchanger. Isolate Charging and Letdown.
A. Incorrect. wrong action per AOP R.D5. Plausible because this would be required
per tech specs if leak cannot be isolated.
B. Correct. If RHX QuIet temperature is lowering, then more charging ffow is going
through the RHX. This means the leak is downstream of the RHX in containment.
Since Charging ffow increase d from a normal value of 87 GPM to 92GPM with no
other changes, leakage is greater than TS limits which would require shutdown.
C. tncorrect. Wrong location of leak, wrong action
D. Incorrect. Wrong location, correct action
(
Monday. May 07, 2007 3:22 :57 PM 9
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability 10(a) predict the impacts of the following malfunctions or operntioos m the eves; and (b) based on 1tlose pndctions, use
procedures to correct,control. or mitigatethe ccosecoeocee of eeee ~ or operations: 8ourIda'y isoIaticn vat.oe leak.
(
Question No. 2
Tier 2 Group 1
Importance Rating: RO 3.6
Technical Reference: R.0 5
Proposed references to be provided to ap plicants during examination: Non e
Leaming Objective : OPL271AOP-R.05 Objective 4
Que stion Source : New
Question History :
Question Cognitive Level: Higher
10 CFR Part 55 Co ntent: 41 .10
Comments: Correc t typo in stem "downstream". Added value s to PZR and VCT level, Re S
temp. Ch anged cha rging flow to 92 gp m. Added TI information to letdown temp indica tion in
stem. Removed the Tech Spec from each an swer. This will cause applicant to different iate
( between break location and correct procedura lffech Spec action. Added in accordance with
AOP to stem to rule out A be ing correc t.
MCS Time: I Points: 1.00 Version: o I 2 3 4 5 6 7 8 9
Answer: BDDA CB A D A A Scramble Range: A * D
Source : NEW Source If Bank:
Cogni tive Leve l: HIGHER Difficulty:
Job Position: RO Plant: SEQU OYAI I
Date: 4/2007 Lasl2 NRC?: NO
(
Monday, May 07, 20073:22:58 PM 10
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
6 . 005 AI.OI 00 1
( Given the following plant conditi ons:
Unit 1 cooldown in progress.
RCS temperature is 225°F.
Current RCS cooldown rate is 25°F per hour.
The OATC is placing 1A-A RHR Pump in service in accorda nce with
0-SO-74-1 ,
Section 5.5.2, Placing RHR in service for normal shutdown cooling.
Whi ch ONE (1) of the following actions is required to control RHR HX temperature in
accordance with 0-SO- 74-1, Residual Heat Removal System, and the reason?
Throttle open RHR HX A CCS To maintain RHR HX CCS
Outlet Valve FCV-70-156 outlet temperatur e <145°F.
B. Throttle open RHR HX A CCS To maintain RHR HX outlet
Outlet Valve FCV-70-156 to RCS temperature <235°F.
( C. Throttle open RHR HX A Outlet To maintain RHR HX outlet
Valve FCV-74-16 to RCS temperature <235°F.
D. Thro ttle open RHR HX A Outlet To maintain RHR HX CCS
Valve FCV-74-16 outlet tempe rature <145°F.
A. correct: SO-74- 1 throttles the RHR HX CCS outlet valve to control CCS outlet
temperature <145F.
B. Incorrect: corre ct valve manipulation but the CCS valve is not used to control RHR
tempera ture. Applicant may confu se with a different precaution on placing RHR in
service at >235F which may cause flashing in the RHR system. 0-5 0 -74-1 , section 5.5.1
step 17 caution.
C.I ncorrect: Incorre ct valve, applicant could confuse the precaution since throttling this
valve would accomplish the same re sult.
D. Incorrect: Wrong valve but correct reason.
(
Monday. May 07 , 200 7 3:22:58 PM 11
QUESTIONS REPORT
for SEQUO YAH 2007 - NRC EXAM REV FINAL AS G IVEN 5-7-07
Abi~ty to pe:Ict and/or monitro changes in ~ (to pervent exceeding design ~mits) associated with op8'ating the RHRS cootrols
( including : Heatup/cooIdoMl rates .
Question Number: 4
Tier 2 Group 1
Importance Rating: RO 3.5
Technical Referen ce: 0- 5 0 -74-1 , section 5.5.2 step 8 caution. page 71 of 204 .
Proposed reference s to be provided to applicants durinq examination: None
Learning Objective: OPL200.RHR Objective 5.b
10 CFR Part 55 content: 41.10
Comments:
MCS T ime: Points: 1.00 Version: oI23456789
Answer: A BC DCA DCC B Scram ble Rang e: A * 0
Source: NEW Source If Bank:
( Cognitive Level: HIG HER
Job Position : RO
Difficulty:
Plant: SEQUOYAH
Date: 412007 Last 2 NRC? : NO
(
Monday. May 07. 2007 3:22:58 PM 12
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
7. 005 AA2.02 00 I
( Given the follo wing plant conditions:
During a power decrease, ONE ( 1) Control Bank D rod becomes
misposi tioned 14 steps out from its group .
The crew is attempting to realign the rod in accordance with the appropriate
procedure.
The rod has been misaligned for 40 minutes.
Assuming the rod can be moved, which ONE (1) of the following is the speed at which
the rod will move when it is realigned ?
A. 32 steps per minute
B~ 48 steps per minute
C. 64 steps per minut e
D. 72 steps per minut e
A. Incorrect. 32 SPM is part of the variable speed for auto rod control 3-5 deg F
mismatch.
( B. Corre ct. Control Bank in Manual or Bank Select will initiate motion at 48 SPM
C. Incorre ct. 64 SPM is for Shutdown Bank s
D. Incorre ct. 72 SPM is maximum variable speed
(
Monday, May 07 , 2007 3:22:58 PM 13
QUEST IONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability to determine and interpr et the following as they apply to the Inoperable f Stuck Conlrol Rex!: Difference betweeo jog and run rod
( speeds , effect on CRDM of stuck rod
Que stion No. 58
Tier 1 Grou p 2
Importance Rating : R0 2.5
Technical Reference : Rod Control SD, pg 38
Proposed references to be provided to applicants duri ng examination: None
Learning Objective: OPL271AOP-C.O l Objective 5
OPT200RDCNT Objective 4.e
Question Source: New
Question History:
Question Cognitive Level: Lower
10 CFR Part 55 Content: 41.6
Comments:
MCS Time: Po ints: 1.00 Vers ion : o t 2 3 4 5 6 7 8 9
( Source: NEW
Answer. BDAB CB CAD B
Source I f Bank:
Sc ramb le Ran ge : A - D
Cognitive Level: LOWER Difficuhy:
Job Position: RO Plant : SEQUOYAH
Dale: 412007 Last 2 NRC?: NO
(
Monday, May 07, 2007 3:22:58 PM 14
QUES TIO NS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
8 . 005 KI.QI 00 1
( Given the following plant conditions:
Th e Unit was in Mode 1, at 100% load .
A LOCA is in progress.
Step 11 (DETERMINE if RHR pumps should be stopped) of E-1, Loss of Reactor
or Seconda ry Coolant, is in progress.
RCS Pressure is 350 psig and dropping.
Both RHR Pumps are running.
Wh ich ONE (1) of the followi ng proced ural actions is required?
A. Immediately stop both pumps and place handswitches in pull-to-lock .
B~ Open 1-FCV-70-153 and 156, CCS to the RHR Heat Exchangers.
C. Transition to ECA-1.1, "Loss of RHR Recirc".
D. Reset the Safety Injection Signal, stop both RHR Pumps, and place their
Handswitches in A-Auto.
A. Incorrect. With pre ssure dropping, pumps will not be stopped.
( 8 . Correct. Open valves to ensure pump cooling. [EPM-3-E-l Step 10 ERG statement:
On low-head systems where the pump recirculates on a small volume circuit. there is concern for
pump and motor overheating. Shutdown of the pump and placement in the standby mode. when
the ReS pressure meets the criteria outli ned in this step. allows for future pump operability.)
G. Incorrect. Would not go to EGA- I . 1 based upon indications given. Gredible
because loss of both RHR pumps is an entry to EGA-I . 1.
D. Incorrect. With press ure still dropping, pumps will remain running.
(
Monday, May 07, 2007 3:22:58 PM 15
QUESTIO NS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVE N 5-7-07
Knowledge of the ~ieaI connectionsMd/Ol" cause-effect r~ationshi ps betweeI'l the RHRS and the following systems: ccws.
( Question No. 3
Tier 2 Grou p 1
Importance Rating: R0 3.2
Techn ical Reference: E-l ; EPM-3- E-1
Proposed references to be provided to applica nts during exam ination: No ne
Learn ing Objective: OPT200 RHR.R2 Obje cl ive 4.d
Q ues tio n Source: New
Q ue stion History:
Que stion Cognitive Level: Higher
10 CFR Part 55 Content: 4 1.10
Com ments: Add ed proce dure step in stem . Rem oved last part of each answer that was not
required info rmation to different iate be tween answers. Removed RHR flow indications from
stem to pre vent overlap with question 006A3.0 1.
( MCS Time: 3 Points: 1.00 Vers ion: o I 2 3 4 5 6 7 8 9
Answer: BAB CD AB CDA Scramble Range: A - D
Source: BANK Source If Bank: WBN BANK
Cognitive Level: HIGHER D ifficu lty.
Job Position: RO Plant: SEQUOYAH
Date : 3 Last 2 NRC?: NO
(
Monday, May 07,20073:22:58 PM 16
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
9. 006 AJ .O! 001
( Given the following plant conditions:
A plant cooldown was in progress in accordance with 0-GO-7 , Unit Shutdown
from Hot Standb y to Cold Shutdown.
RCS pressure was at 800 psig when a LOCA occurred.
RCS pressure is currently 450 psig and lowering slowly.
Wh ich ONE (1) of the following describes the status of the ECCS equipment identified
below?
A. Cold Leg Accumulator level is stable;
RHR flow is rising
B. Cold Leg Accumu lator level is lowering;
RHR flow is zero
C~ Cold Leg Accumu lator level is stable;
RHR flow is zero
D. Cold Leg Accumulator level is lowering;
RHR flow is rising
( A. Incorrect. Accumulators would be stable but RHR would not be injecting.
B. Incorrect. With RCS pressure at 450 psig, Cold Leg Accumulators would be
injecting if not isolated. Plausible because if power were not removed, the SI signal
would automatically open the valves. RHR flow will not be indicated untif RCS
pressure drops to approximately 180 psig.
C. Correct. CLAs would be not be lowering since they would be isolated with power
removed in accordance with GO- 7. RHR flow will not be indicated untif RCS
pressure drops to approximately 180 psig .
D. Incorrect. Accumulator level is stable and RHR is not injecting.
(
Monday, May 07 , 20 07 3:22:58 PM 17
QUESTIONS REPORT
for SEaUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7 -07
Ability to monitor automatic operaliOn of the ECCS. inCluding: Accumulators.
( Question No. 6
Tier 2 Group 1
Importance Rating: R04.0
Technical Referen ce: ECCS SD; 0-G O-7 Sect. 5 .2 Step 18 incl ;
Proposed references to be provide d to app licants during examina tion : None
Learning Objective: OPT200.ECCS Objective 3
Question Source : New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Conlent: 41.4
Comments: Removed 51 flow from each answer based on NRC comments . Mod ified stem to
have accumulators isolated based on NRC comments. This chang ed correct answer to C.
Minor editorial change to stem word ing .
( MCS Time: Points : 1.00 Version: o12 3 4 5 6 7 8 9
Answe r: C DDAADD BBA Scram ble Ran ge: A - D
Source: N EW So urc e If Bank:
Cognitive Level : HIGHER D ifficu lty:
Job Position : RO Plant: SEQUOYAH
Dale : 412007 Last 2 NRC ?: NO
(
Monday, May 07,2007 3:22:58 PM 18
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
10. 006 K3.0 \ 00 \
( Given the following plant conditions:
A LOCA has occurred.
RCS pressure is 100 psig.
All CETC's are reading approximately 810°F and rising slowly.
Centrifugal Charging Pumps are running .
Both SI pumps are tripped .
RVLlS Lower Range Level is 55% and decreasing slowly.
In accordance with FR-O, Status Trees, which ONE (1) the following describes the
current status of core cooling and the reason why?
A. Core cooling is inadeq uate because both SI pumps are required to sustai n core
cooling .
B. Core coo ling is inadequate because RVLlS Lower Range level is too low to sustain
core cooling .
C. Core cooling is degraded because both SI pumps are required to sustain core
cooling .
( D~ Core cooling is deg raded because RVLlS Lower Range level is too low to sustain
core cooling .
A. Incorrect. Inadequate core cooling does not exist with the given CETC values.
Safety analysis assumes 1 CCP, 1 SI, 1 RHR, and 2 S I Accumulators.
B. Incorrect. Inadequate core cooling does not exist with the given CETC values and
stated RVLlS level.
C. Incorrect . Safety analysis assumes 1 CCP, 1 St, 1 RHR, and 2 SI Accumulators.
Without an SI pump running, safety analysis assumptions are not met. Applicant
may confuse the safety analysis with the TIS LCO entry conditions .
D. Correct. RVLlS Lower Range is above the FR-C. l minimum of 42% for inadequate
core cooling but is too low to sustain core cooling.
(
Monday, May 07, 200 7 3:22:58 PM 19
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM RE V FINAL AS GI VEN 5-7-07
KnO'Nl edge ollhe effect thai a loss or malfunction of the ECCS will have on the following : ReS.
( Question No. 5
Tier 2 Gro up 1
Import ance Ratin g: R04.1
Technical Ref erence: TS 3.5 .2; 1-FR-O, EPM-3-FR-O
Proposed references to be provided to applicants du ring exa minat ion: None
Learnin g Objective: OPL200.ECCS Objective 6
Question Source: Bank
Question History: WTS I (Various Exam s)
q uest ion Cognitive Level: Higher
10 CFR Part 55 Content: 41,8
Comm ents: Modified A and B distracto rs to change adequate to inadequ ate core coo ling
based on NRC com me nts and changed B distractor to read similar to D. Modifi ed stem to
refe rence FR-O.
(
MCS Time: Points: 1.00 Version: o J 2 34 5 6 7 8 9
Answer : DD C B B A C C A A Scramble Range:A- D
Source: BANK Source If Bank: ROBINSON 2007 NRC
Cognitive Level: HIGHER Difficulty:
Job Position: RO Plant: SEQUOYAH
Date: 412007 Last 2 NRC ?: NO
(
Monday, May 07, 2007 3:22:58 PM 20
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
11. 007 EAI. 08 00 1
( Given the following plant conditio ns:
Unit 1 was opera ting at 40% power.
1A-A EDG was running in parallel for monthly surveillance testing .
A reactor trip occurred due to a loss of offsite power.
Tavg is 549' F and decreas ing.
All equipment is ope rating as designed.
SG levels dropped to the following val ues:
SG 1 - 10% NR
SG2- 14%NR
SG 3 - 17% NR
SG 4 - 12% NR
W hich ONE (1) of the following describes the operation of the 1A-A MDAFW and
Tu rbine Driven AFW pumps?
A. OFF OFF
B~ RUNNING RUNNING
( C. RUNNI NG OFF
D. OFF RUNNING
A. Incorrect. Indications are that they may not have starte d o n SG level, but they do start on
FWI whe n the reactor is tripped and Tavg is less than 550°F. Plau sible if applican t
mistak es the SG level AFWP start with the AMSAC setpoint of 8% and is con fused with
wha t starts the A FW pumps (0110 wing a Rx trip (i.e. low level vs. trip of both MFPs)
B. Correct. Bot h p umps will auto start from the feedwater isolatio n signal. DG 1A -A breaker
will open on emergency start and the 1A-A AFW pump will tie onto the SO BD following
return of voltage when the DG ties back on.
C. Incorrect. If 1 SG was less than 10. 7%, this could be true if the reactor wa s not tripped.
D. Incorrect. Applicant may think that the board wi/I not reenergize following the LOOP sinc e
the DG is paralleled to the board. This co nditio n would only have the TDAFW pump
running.
NOTE: TI-28 Art 9 pg 10/ 16
SG level <10. 7% decreasing on 1 out of 4 SGs will initiate MDA FW;
SG level <10. 7% decreasing on 2 out of 4 SGs will initiate TDAFW.
(
Monday, May 07,2007 3:22:59 PM 21
QUESTIONS REPORT
for SEQUOYAH 2007 - N RC EXA M RE V FI NA L AS GIVEN 5- 7-0 7
Ability to operate and monitor the following as they apply to a reactor trip: AFW System
( Que stion No. 39
Tier 1 Group 1
Importance Rating: RO 4.4
Techn ical Reference: TI-28 Att 9 [selpoints]
Proposed references to be provided to applicants during examination: None
Learning Objective: OPT200 .AFW Objective 12.b
Question Source : New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Conlent: 41.7
Com ments: Modified wo rdin g on C and 0 based on NRC com ments.
MCS Time: Po ints: 1.00 Version: o I 23 4 5 6 7 8 9
BB CD CADA CA
( Source: NE W
Answer:
So urce I f Bank:
Scramble Range: A * D
Cognitive Level : H IGH ER Difficulty:
Job Position : RO Plant: SEQUOYAH
Dat e: 4/2007 Last 2 NR C? : NO
Monday. May 07, 2007 3:22:59 PM 22
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
12. 007 EA2.06 ool
( Given the following plant conditions:
A manual reactor trip was attempted .
The following conditions exist:
Reactor Trip Breaker 'A' Red indica tion exists.
Reactor Trip Breaker 'B' Green indication exists.
Reactor Power is 3% and lowering.
Rod bottom lights are lit with the ex cept ion of FOUR control bank D rods.
Their positions are as follows:
H-8 - 16 steps
K-2 - 220 steps
M-12 - 8 steps
M-8 - 20 steps
Which ONE (1) of the following describes the condition of the reactor, and the action
that will be requi red?
A. The reactor is tripped ; perform nonnal RCS boration for the stuck rods as directed
in ES-0.1, Reactor Trip Response.
( B~ The reactor is tripped; initiate emergency boration for the stuck rods in accordance
with EA 68-4, Emergency Boration, as directed in ES-0.1, Reactor Trip Response.
C. The reactor is no t tripped; manually insert contro l rods as directed in FR-S.1,
Nuclear Power Generation/ATWS .
D. The reactor is not tripped; initiate emergency boration for the stuck rods in
accordance with EA 68-4, Emergency Boration, as directed in FR-S.1, Nuclear
Power Generation/ATW S.
A. Incorrect. Boration will be fhro ugh EA procedure, not normal bora fion.
B. Correct. Power decrea sing and 1 RTB open means the reactor is tripped. ES-O. l
will direcf emergency borafion.
C. Incorrect. Indication is that reactor is tripped. If if was not, this would be correct.
D. Incorrect. Indication is that reactor is tripped. If not, these actions would occur, but
rods would also be inserted
(
Monday, May 07, 20073:22:59 PM 23
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Abi~1y to detennine or interpret the following as they appty to a reactor tri9: OCCurrence d a reac tor trip.
( Question No . 76
Tier 1 Group 1
Importance Rating : SRO 4.5
Technical Reference : E-O. ES-o.1
Proposed refe ren ces to be provided to applicants during examination: None
Learnin g Objective: OPL27 1E-O Obj ective 4
Question Sou rce: New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Co nte nt: 43.5
Com ments: mod ified rx power to 3% to be less than FR-S .1 setpoint.
MCS Time: Points: 1.00 Vers ion : oI 234567 89
( So urce : NE W
Answer: BADACADDCB
Source If Bank
Scramble Ran ge: A - 0
Cognitive Level : HIGH ER Difficully:
Job Position : SRO Plant: SEQUOYAH
Date: 4/2007 Last 2 NRC?: NO
(
Monday, May 07, 2007 3:22:59 PM 24
QUESTION S REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
13. 007G2.1.I 2001
( Given the following plant conditions:
The Control Room was evacuated due to a fire .
The crew is preparing to cool down the RCS from the Aux Control Panel.
All Pressurizer Relief Tank indications were lost during the fire.
Wh ich ONE (1) of the following describes the impact, if any, on Technical Specification
3.3.3.5, Remote Shutdown Instrumentation, of the loss of PRT indication?
A~ Action will be entered for loss of PRT pressure indication ONLY.
B. Action will be entered for loss of PRT level indication ONLY.
C. Action will be entered for loss of PRT pressure and level indication .
D. Actio n entry is NOT required.
A. Correct. TS 3.3.3.5 Table 3.3-9, Remote Shutdown Monitoring Instrumentation,
Instru ment PRT Pressure is required.
B. Incorrec t. Plau sible becau se TS requ ire s PR T instrumentation but not level.
( C. Incorrect. Only PRT pressure is included in TS 3.3.3.5
D. Incorre ct. PRT pressure is include d in TS 3.3.3.5
Conduct of Operations: Ability to apply tectncal specifi cations for 8 system.
Question No. 86
Tie r 2 Gro up 1
Importance Rating : SR0 4.0
Te chnical Reference: TS 3.3.3.5
Proposed referen ces to be provided to applicant s during exam ination: None
Learning Objective: OPT200PZRPCS Objective 6
Question Source : New
Que stion Histo ry:
Question Cogn itive Level: Higher
' 0 CFR Part 55 Content: 43.2
( Co mments:
Monday, May 07, 2007 3:22:59 PM 25
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIV EN 5-7-0 7
MCS Time: I Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
( Source: NEW
Answe r: A D D D DA A B B D
Source If Bank:
Scramble Range: A - 0
Cogn itive Level : HIGHER Difficulty:
Job Position: SRO Plant: SEQ UOYAH
Date: 412007 Last 2 NRC?: NO
(
(
Monday, May 07, 2007 3:22:59 PM 26
QUESTIO NS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
14. 007 Kl.03 00 1
( Given the following plant conditions:
A reactor trip has occurred.
RCS pressure is 1810 psig and loweri ng.
Conta inment Pre ssure is 1.5 psig a nd rising.
Whi ch ONE (1) of the following describes the status of RCP #1 seal leakofl?
Directed to...
A. VCT
B~ PRT
C. RCDT
D. Reactor Building Floor and Equipment Sump
A. Incorrecf. Normal f1owpath.
B. Correct.
( C. Incorrect. Flow path of #2 seal.
D. Incorrect. The seal bypass is isolated but applicant may mistake this alignmen t
under these conditions.
(
Monday, May 07, 2007 3:22:59 PM 27
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
KnoM edge of Ihe physical connections and/or cause-effect relationshlps between the PRT 5 and the followingsystems: Res.
( Qu estion No. 7
Tier 2 Group 1
Importance Rating : R03.0
Technica l Reference : OPT200.CVCS, Slide 71
Proposed referen ces to be provided to applican ts du ring exam ination: None
Learning Objective: OPT200RCP Objective 3
Questio n Source: Bank
Question History: WTSI
Question Cognitive Level: Higher
'0 CFR Part 55 Content: 41 .7
Comments: changed D distra ctor to seal bypa ss ba sed on NRC com ents .
MeS Time: Poin ts: 1.00 Version: oI23456789
( Source: BANK
Answer : BACDACCDCD
Source If B ank:
Scra mb le Range: A - 0
Cognitive Level: HIGHER Diffi culty:
Job Position: RO Plant: SEQUOYAH
Date: 412007 Last 2 NRC?: NO
(
Mo nday, May 07, 2007 3:22:59 PM 28
QUESTIONS REPORT
for SEQUO YAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
15. 008 A4.09 00 1
( Given the following plant conditions:
Unit 1 is operating at 100% RTP
0-XA-55-27B-B, Window A-5, "LETDOW N HX OUTLET FLOWfTE MP
ABNORMAL" alarms.
The RO determines that Letdown HX Outlet temperature is 132°F and rising
slowly.
W hich ONE ( 1) of the following describes the event that has occurred, and the effect
on the unit prior to any action by the crew?
1-TCV-70-192, Letdown Heat Exchanger Temperature Control Valve......
A. temperature input is failing high. Mixed Bed demins have automatica lly bypassed.
B. temperature input is failing high. Letdown is aligned to the Mixed Bed demins.
C. temperature input is failing low. Mixed Bed demins have automatically bypassed.
D~ temperature input is fail ing low. Letdown is aligned to the Mixed Bed demins.
A. Incorrect. Incorre ct input faifure, incorrect MB status- MB bypa ss occurrs at 137"F.
If MB bypassed at alarm SP, alignment would be this way.
B. Incorre ct. Incorrect input faifure,correct MB status.
C. Incorrect. Correct input faifure, incorrec t MB status.
D. Correct. if temperature input fails iow, the rev wiil close to raise temperature . If
temperature from the letdown HX rises, the mixed bed demin s wiil auto bypass when
letdown temperature reaches 137"F.
(
Monday, May 07,20073:22:59 PM 29
QUESTIONS REPORT
for SEQUO YAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Abi lity 10 rnanuaIIy operate and/or monitel' in !he etrllrOl room: CON T emperalure control wive.
( Que stion No. 8
Tier 2 Group 1
Importance Rating : R0 3.0
Technical Reference : OPT200
Proposed references to be provided to ap plicants during examination: None
Leaming Objective: OPT200.CVCS Objective 8
Question Source: New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Content: 41 .7
Comments: mod ified each an swe r to reference alarm setpoint vs. mixed bed bypas s setpo int
base d on NRC comments and made it a new qu estion.
( MCS Time: Points: 1.00 Version: oI 23456789
Answer: DBBDBB ACCD Scramble Range : A - D
Source: NEW Source If Bank:
Cog nitive Level: HIGH ER D ifficu lty:
Job Position : RO Plant : SEQ UOYAH
Dat e: 4/2007 Last 2 NR C?: NO
(
Monday. May 07.20073:22:59 PM 30
QUESTIONS REPORT
for SEQUO YAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
16. 008 G2.4.4 00 1
( Given the followi ng plant conditions:
- A LOCA has occurred.
- The crew has just entered E-1, Loss of Reactor or Secondary Coolant.
- The following parameters exist:
- All SG pressures - 730 psig and slowly trending down.
- All SG levels - being controlled at 40% NR.
- PRZR level - off-scale high .
- RVLl S Lower Range indicates 50%.
- Contai nment Pressure - 2.5 psig .
- RWST level- 74% and decreasing slowly.
- RCS pressure - 875 psig and decreasing slowly.
- Highest CET - 500°F.
Based on these indicatio ns, which ONE (1) of the followi ng procedures will the crew
enter ne xt?
B~ ES-1.2, Post LOCA Cooldown and Depressurization
( C. ES-1.3, Transfer to RHR Containment Sump
D. E-2, Faulted Steam Generator Isolatio n
A-Incorrect. (see B- SI termination criteria not met).
B-Correct. RCS Pressure not stable, and low RCS inven tory (low reactor vessel level
and high PRZR level indicates a large head bubble).
C-Incorrect. RCS pressure and RWST level are high. Entry to ES-l.3 on low RWST
level.
D-Incorrect. SG pressures are trending down because RCS tempera ture is trending
down and AFW flows maintaining levels.
(
Monday. May 07, 2007 3:22:59 PM 31
QUESTIONS REPORT
for SEOUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
EmergencyProcedures I Plan Abiity to rec::oglil:e abnormal indications lor system operating parc.neterr> whiCh are entry-leve cen:1itions
( for emergency and abnormal operaling prooedlXes.
Question No. 77
Tier 1 Group 1
Importan ce Rating : SR0 4.3
Technical Reference : E-1
Proposed references to be provided to applicants du ring examination: None
Leaming Objective: OPL271 E-1 Objeclive 5
Question Source : Bank
Question History: North Anna 2006
Question Cognitive 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: BDDD C CDBD C ScrambleRange: A- D
Sourc e: BANK Source If Bank: NORTH ANNA 2006 NRC
Cognitive Leve l: HIGHER Difficulty:
Job Position: SRO Plant: SEQ UOYAH
Date: 412007 Last 2 NRC?: NO
(
Monday, May 07, 2007 3:22:59 PM 32
QUESTIONS REPORT
fo r SEQUO YAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
17. 010 K2.03 001
( Which ONE (1) of the followi ng describes the power supplies to the PZR PORVs and
their associated MCR positio n indicating lights?
PORVs Ind ic ati ng Lights
A. 120 VAC Vita l Instrument Power 125 VDC Vital Battery Boards
B. 125 VDC Vita l Battery Boards 120 VAC Vital Instrument Power
C~ 125 VDC Vita l Battery Boards 125 VDC Vital Battery Boards
D. 120 VAC Vital Instrument Power 120 VAC Vit al Instrument Power
A. Incorrect. Credible due to low voltage source and 120 v AC is used for control of the
SG POR Vs and for indication of the PZR spray valves. If applicant confuses this with
the POR Vs or the spray valves then he may select 120 v AC as correct answer.
B. Incorrect. Credible due to low voltage source, and partially correct.
C. Correct. Ul POR Vs and indications are from 125V DC Battery Boards I and II.
D. Incorr ect. Credible due to low voltage source
( KnoMedge of bus power supplies t) the foloNing: Indicator for PORV position.
Question No. 9
Tie r 2 Group 1
Importance Rating: R0 2.8
Technical Refe rence : 45N601-4
Proposed references to be provided to applicants during examination: None
Learning Objective: OPT200.PZRPCS Objective 4.b
Question Source: New
Q uestion H istory:
Question Cognitive Level: Lower
10 CFR Part 55 Content: 41.7
Comme nts:
(
Monday, May 07, 200 7 3:23:00 PM 33
QUESTIONS REPORT
for SEOUOYAH 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: NEW
Answer: C ACCCA C B BC
Source If Bank:
Sc ramble Range : A * D
Cognitive Level: LOWER Difficul ty:
Job Position: RO Plant: SEQ UOY AI I
Date: 4/2007 Last 2 NRC? : NO
(
Monday, May 07, 20073:23:00 PM 34
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
18. 011 EA2.10 001
( Given the following plant conditions:
A Reactor Trip and Safety Injection have occu rred.
Containment pressure is 5.6 psig and stable .
RCPs have been stopped .
RVLl S Lower Range is indicating 35%.
Core Exit Thermocouples are indicating 710°F.
PZR level is off scale low.
PZR pressure is 400 psig.
RCS W ide Range Hot Leg Temperatures are indicati ng 680°F.
W hich ONE (1) of the following conditi ons could currently exist, and which procedure
would be required?
A. A PZR vapor space break has occurred and a transition to FR-C.l , Response to
Inadequate Core Cooling, is required.
B. A PZR vapo r space break has occurred and a transition to FR-C.2, Response to
Degraded Core Cooling , is requi red.
C~ An RCS hot or cold leg break has occurred and a transition to FR-C.l , Response to
Inadequate Core Cooling , is required .
( D. An RCS hot or cold leg break has occ urred and a transitio n to FR-C.2, Response to
Degraded Core Cooling , is requi red.
A. Incorrect. Incorrect event, correct procedure entry.
B. Incorrect. Incorrect event, incorrect procedure entry.
C. Correct. Requires applicant to disfinguish between Orange and Red Path on Core
Cooling CSF. Also requires determination of break location by determining that PZR
level is not off-scale high.
D. Incorrect. Correct event, incorrect procedure entry
(
Monday, May 07, 2007 3:23:00 PM 35
QUESTIONS REPORT
for S EQUOYAH 200 7 - NRC EXAM REV FIN AL AS GIVE N 5-7-07
Ability 10 detetmine or interpret Ihe following as they apply to a Large Bfeak l OCA: Vefifteation of adequate core cooling
( Question No. 78
Tier 1 Group 1
Importance Rating : SRO 4.7
Te chnical Reference : CSFSTs Core Cooling F.02
Prop osed referen ces to be provided to applicants during exa mination: None
Learning Objective: OPL271FR-C.1 Objeclive 2.b
Question Source: Modified
Qu estion History: WTSI Various (Harris)
Question Cognitive Level: Higher
10 CFR Part 55 Content: 43.5
Com ments:
MCS Time: Points: 1.00 Vers ion: oI 23456789
( Source : M ODIFIED
An swer: CAA BCC DDDD
Source If Bank:
Scramble Range : A - D
Cognitive Level: HIGH ER D ifficulty:
Job Position : SR O Plant: SEQUOYAH
Date : 4/2007 Last 2 NRC? : NO
(
Monday, May 07,2007 3:23:00 PM 36
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
19. 011 EK3.14 001
( Given the following plant conditio ns:
A LOCA has occurred .
Safety Injection has failed to actuate.
The crew is performing E-O, Reactor Trip or Safety Injection .
RCS pressure is 100 psig and lowering.
Contai nment pressure is 5.5 psig and rising.
The crew is attempting to initiate ECCS flow.
W hich ONE (1) of the followi ng describes the operation of RCPs for this event?
A. Maintain RCPs running to provide core cooling until SI is actuated.
B. Maintain RCPs running to prevent phase separation of RCS liquid.
C. Trip all RCPs to minimize mass flow out of the RCS break.
D~ Trip all RCPs to prevent damage due to loss of cooling water flow.
A. Incorrect. Plausible because Rep Trip criteria for Westinghouse SBLOCA requires SI or
Charging Pumps running to allow trip of Reps
( B. Incorrect. Reps will be tripped, but plausible because the Westinghouse analysis for Re p
trip on SBLOCA indicates that phase separation is a concern if Reps are not tripped in a
timely manner, and are subsequently tripped later in the event due to loss of power or
other reason
C. Incorrect. Correct operation of pumps, but a LBLOGA is in progress. SBLOCA analysis is
concerned with mass being pumped out of the break, consistent with B above.
D. Correct. Phase B has occurred and CCS to Reps is lost. *Reps must be stopped to
prevent running with no cooling water.
Phase B isolation due to loss of CCS cooling water. Continued pump operation without
cooling water willresult in pump damage.
(
Monday, May 07, 2007 3:23:00 PM 37
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Kna.Medge of the reas ons lor the following respon ses as the apply to the Large Br eak l OC A; Re p trippi ng requ irement
( Question No. 40
Tier 1 Group 1
Importance Rating: R04.1
Technical Reference: E-O: EPM-3-E-0 Foldout Page Ilem : ERG Executive Volume.
RCP Trip/Restart
Propo sed references to be provided to applicant s during examination: None
Learning Objective:
Question Source : Bank
Question History: WTS I Bank
Question Cognitive Level: Higher
10 CFR Part 55 Conlent: 41.5
Comments:
( Mes Ti me: Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer: D O C A A C D A D A Scram ble Range: A - 0
Source : BANK Source If Bank: WTSI
Cognitive Level: HIGH ER Difficulty:
Job Position : RO Plant: SEQUOYAJ-I
Date: 412007 Last 2 NRC?: NO
(
Monday. May 07 , 2007 3:23:00 PM 38
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXA M REV FINAL AS G IVEN 5-7-07
20 . 012 KI.04 001
( Given the following plant conditions:
A secon dary steam leak has occurred with Co ntro l Bank D initially at 220 steps.
Over th e past 5 minutes, reactor power has been slowl y rising, followed by a
sharp spike from 104% to approximately 109%.
All equipme nt has ope rated as designed in response to th e transient.
W hich ONE (1) of th e followin g describes the Cont rol Bank D Rod Position and Group
Demand ind ica tions foll owi ng the termination of this event?
A. Rod Bottom Lights ext ingu ished ; Group Demand ind ication at 220 steps.
B. Rod Bottom Lights extinguished; Group Demand indication less than 220 steps.
C~ Rod Bottom Lights illuminated ; Group Demand indication less than 220 steps.
D. Rod Bottom Lights illuminated; Grou p Demand indicatio n at 220 steps.
A. Incorrect. Rod bottom lights will be on. Runback and reactor trip should occur {see
C].
B. Incorrect. Rod bottom lights will be on. Runback and reactor trip should occur {see
( C].
C. Correct. Rod Bottom lights would all be illuminated following the reactor trip. OPDT
runback would ha ve demanded rod insertion {setpoint: 1% below the reactor trip
setpoint], prior to the reactor trip resulting in Control Bank 0 {CB 'D' Groups 1 & 2
indicators l -XI-85-5105D l & l-XI-85-5 105D2} demand being lower. Also, bank
demand is lower because control rods insert in response to the turbine runback load
reduction, Tave above Tref. The power spike to 109% would cause a reactor trip
{setpoint: 2/4 PRN ls ~ 1 0 9% reactor trip setpoint}.
D. Incorrect. Rod Bottom lights would all be illuminated following the reactor trip.
Although CB 'D' rod stop is at 220 steps, it is an outward motion stop ONLY. CB 'D'
Groups 1 & 2 indicators will be below 220 steps indicated from the runback prior to
the reactor trip.
(
Monday. May 07,20073:23:00 PM 39
Q UESTIONS REPORT
fo r S EQ UOYAH 2007 - NRC EXAM RE V F INA L AS G IV EN 5-7-07
Knowledge of tile physiCal connectiMs andJOf cause effect relationships between the RP $ and the following systems: RPIS.
( Question No. ,,
Tier 2 Grou p 1
Import ance Rating : R0 3.2
Technical Reference : (TI-28)
Proposed references to be provided to applicants during examination : None
Learning Objective : OPT200 .RPS. B.3 & 4
Question Source: New
Que stion History:
Que stion Cog nitive Level: Higher
10 CFR Part 55 Cont ent: 41.6
Comm ents: Modified B and C wording based on NRC comment. Removed "Rod Position
Indication below 220 steps" from A and B based on NRC comme nt.
MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
Ans wer: C B B B B AC DC D Scramble Range: A - D
Source: NEW Source If Bank:
Cognitive Level: HtGHER Difficu lty:
Job Position: RO Plant: SEQUOYAH
Da te : 4/200 7 Last 2 NR C? : NO
(
Monday, May 07, 2007 3:23:00 PM 40
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
21 . 012 K2.0 1 001
( Given the followi ng plant conditions:
Unit 1 is at 100% power.
A loss of 125 VDC Vital Battery Board I occurs.
W hich ONE (1) of the following describes the effect on the assoc iated Reactor Trip
Breaker?
A~ Reactor Trip Breaker indication on the MCB is losl and RTA is NOT capable of
tripping on a SHUNT l rip .
B. Reacl or Trip Brea ker indication on the MCB is lost and RTA lrips OPEN.
C. Reactor Trip Breaker indication on the MCB remains IiI and RTA trips OPEN.
D. Reactor Trip Breaker indication on the MCB remains IiI and RTA is NOT capable of
tripping on a SHUNT trip.
A. Correct. 125 VDC Vital Battery Board I supplies control power, and indication power,
to R TA and also shunt trip mechanism. Without this power, M-4 indication is lost and
the shunt trip feature of RTA is disabled- the RTA will not open from the loss of 125
VDC control power.
( B. tncorrect. Correct indication, but loss of power to shunt coil will not cause RTA to
trip. Plausible since UV coil losing power [from 120 VAC] will cause the reactor trip
breakers to open.
C. Incorrect. RTA indication is not available at M-4 or at other location s in the MCR or
from other sources or power supplies but applicant may assume indication is from a
different source. Loss of power to shunt coil will not cause RTA to trip. Plausible
since UV coil losing power [from 120 VAC] will cause the reactor trip breakers to
open .
D. Incorrect. Indication is not available on MCB; losing power to shunt coil will not
cause RTA to open.
(
Monday, May 07. 2007 3:23:00 PM 41
QUESTIONS REPOR T
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
KnoMedge of bus power supplies to the following: RPS chMnels. components. and Inlercormections.
( Qu estion No. 10
Tier 2 Group 1
Importa nce Rating : RO 3.3
Technical Reference: 0-45N706*3
Proposed referen ces to be provided to applicants during exam ination: None
Learning Objective: OPL271AOP-P.02. Obj 2.d
Que stion Source : Bank
Question History:
Question Cognitive Level: Lower
10 CFR Part 55 Cont en t: 41.7
Comments: mod ified B and C based on NRC comments .
MCS Time: I Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer: A A B A CAB D A B Scramble Range: A * D
Source: BANK Source If Bank: WTSI
( Cognitive Level: LOWER
Job Position: RO
Diffi culty:
Plant: SEQUOYAH
Date: 4/2007 Las12 NRC! : NO
(
Monday, May 07, 2007 3:23 :00 PM 42
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
22 . 013 K3.03 00 1
( Given the following plant conditions:
A Loss of Off-Site Power has occurred.
A stea m line break generated a safety injection signal but only Train B of Safety
Injection actuated.
Containment pressure indicates 2.9 psig and rising.
Assuming no manual actio ns have been initiated, which ONE (1) of the following
correctly describes a consequence of the failure of Train A of Safety Injection to
actuate?
A. 1A-A CCP will NOT be sequenced onto the Shutdown Board.
B. Only two Main Steam Isolation Valves (MSIV's) will be closed .
C. Only one Phase B Containment Isolation Valve in each penetration will be closed.
D~ Only one Phase A Containment Isolation Valve in each penetration will be closed.
A. Incorrect. 'A' train loads will be loaded in blackout mode, including 1A -A CCP . Applicant
may recognize that the EDG will automatically start but incorrectly think a loss of the A train
ESFAS will pre ven t the load sequencing and not load/start 1A-A CCP.
( B. Incorrect. 2 MSIVs get signals from 1 of 2 slave or 'K' relays from each train; both trains
function this way; so only 2 closing is incorrect. Plausible since a failure of 1 of 2 'A train K
I
relays for the MSIVs will prevent two valves from closing on an actuation signal. This is
consistent with what the applicants have seen on the simulator.
c. Incorrect. Both trains of phase B CIVs will isolate, Applicant may think the ESFAS failure
will will affect the phase B isolation.
D. Correct. Failure of 1 train of ESFAS will result in 1 group of CIA valves closing.
(
Monday, May 07 ,20073:23:00 PM 43
QUESTIONS REPORT
for SEQUO YAH 20 07 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Kno.vI edgeof the effect that a loss or malfunction d ~e ESFAS win have on lhe foIloMng : Containmenl
( Que stion No. 12
Tier 2 Group 1
Importa nce Rating: R04.3
Technical Reference : 47W61 1-88-1, 63-1; TI-28 AU g BfO Load Sequence, page 5
Proposed refe rences to be provided to app licants during examination : None
Learning Objective: OPT200.CtmtStruclure
Question Source: Bank
Question History: Salem 2002
Question Cognitive Level: Higher
10 CFR Part 55 Content: 41,7
Comments:
MCS Time: Points : 1.00 Version: oI 2 345 6 789
( Source: BANK
Answer: D C CBD C CCB A
Source If Bank: SALEM 200 2
Scramble Range: A* O
Cognitive Level : HIGHER Difficulty:
Job Po sition: RO Plant: SEQUOYAII
Date: 4/2007 Last 2 NRC?: NO
(
Monday, May 07, 2007 3:23:01 PM 44
QUESTIONS REPORT
for SEQUOYA H 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
23. 01S AAl.1O00 1
( Given the following plant conditions:
A malfunction has occurred that resulted in a reduction of Component
Cooling Water (CCS) flow to the RCPs.
The US has entered AOP-M.03, Loss of Component Cooling Water.
The OATC is referring to AOP-R.04, Reactor Coolant Pump Malfunctions.
Current parameters for ALL RCPs are as follows:
RCP Lower Bearing temperature is 222°F and rising.
RCP Seal Wate r Outlet temperature is 228°F and rising.
Based on current conditions, which ONE (1) of the following describ es the action
required in relation to the RCPs?
A. Initiate a plant shutdown to Mode 3.
Trip RCPs based upon RCP Lower Bearing temperature exceedi ng an operating
limit.
B. Trip the reactor and enter E-O, Reactor Trip or Safety Injection.
Trip RCPs based upon RCP Lower Bearing temperature exceeding an operating
limit.
( C. Initiate a plant shutdown to Mode 3.
Trip RCPs based upon RCP Seal Water Outlet temperature exceeding an
operating limit.
D~ Tri p the reactor and enter E-O, Reactor Trip or Safety Injection.
Trip RCPs based upon RCP Seal Water Outlet temperature exceeding an
operating limit.
A. Incorrect. Bearing is not exceeding a limit. Plausible since if the applicant applies
the tech spec methodoiogy of an inoperable RCP, then the plant would have to be
in HSB in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
B. Incorrect. Wrong bearing exceeding limit, but correct actions.
C. Incorrect. Correctlimit, incorrect actions.
D. Correct. RCP seal water outlet limit is 225 °F.
(
Monday, May 07, 2007 3:23:01 PM 45
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FI NAL AS G IVEN 5-7-07
Ability to detennine and interpret the following as they apply to the Reactor CooI¥It P lJTlp Malhn:tions (Loss d RC Flow): When kl
secze Rep s on loss of cooling or seal if1ec:tioo
(
Question No . 41
Tier 1 Group 1
Importance Rating : R0 3.7
Technical Reference : AOP-M.03 R11. AOP-R.04 section 2.1.
Proposed references to be provided to applicants during exam ination: None
Learning Objective : OPL271AOI -M.03 Objective 8
Question Source : Modified
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Content: 41.10
Comments : Modified stem based on NRC comments. Added R.04 to stem for Re p trip
criteria monitoring. AOP -M.03 does not contain the Rep trip criteria.
(
MCS Time: Points: I.()() Version: oI 234 5 6 7 8 9
Answer: DCDABD ACC B Scramble Rang e: A - 0
Sou rce: NEW Source If Bank:
Cognitive Level: LOWER Diffi cul ty:
Job Position: RO Plant: SEQUOYAH
Date: 412007 Last 2 NRC? : NO
(
Monday, May 07, 2007 3:23:01 PM 46
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
24 . 0' 5 Kl.08 001
( Given the foll owing plant conditions:
Unit 1 is in Mode 5
Operators are preparing for a plant heatup .
W hich ONE ( 1) of the following describes the MiNIMUM requirement for monitoring
Source Range indications while starting RCPs, and the reason why, in accordan ce
with the precautions and limitations of 1-5 0-68-2, RCP Operations?
A. Monitor indications during startup of the f irst RCP to monitor for indications of a
cold water transient.
B~ Monitor ind ications during startup of the first RCP to monitor for indications of a
boron dilution event.
C. Monitor indications during startup of all RCPs to monitor for indications of a cold
water transient.
D. Monitor indications during startup of all RCPs to monitor for indications of a boron
dilution event.
A. Incorrect. Correct action butreason is incorrect. Applicantmay mistake this
( precaution with a different pre caution in 50-68-2 for circulating cold water on the
start of the first RCP but this precaution is tied to a pressure transient vice a
reactivityaddftion. Both would cause a positive reactivity addition.
B. Correct. Per 50-68-2 P&L L: 'The Source Range Monitor instrumentation must be monitored
during startup of the first Re p. This precaution is necessaryin order to detect rapid boron dilution
from unborated water that could be flushed into the cere."
Per S O-68-2 P&L M: "If af! Rep's are shutdown, do not start the first Rep if it is known that any
volume of dilute water has been introduced into any reactor coolant loop untit an actionplan for
recovery is developed as described in Appendix F Prevention of Rapid Boron Dilution...
C. In corre ct. P er 50-68- 2 P &L F : *Only performed for first RCP start and is concerned with
boron dilution. Regarding an RCP start-eold water concern, 5 0-68-2 When RCS temperature is
greater than charging and seal injection water temperature and RCPs have been idle >5 minutes, a
steam bubble is needed in the pressurizer prior to starting an RCP. This precaution will minimize the
pressure transient when the cold wa ter injected by the charging pump is circulated in the RCS."
D. Incorrect. Only performed for first RCP start per the SO.
(
Monday, May 07,20073:23:0 1 PM 47
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Know1edge of !he phr-; icaI connections andIor ceose-ettect relationships bet\oieen!he N IS and the folloMng systems: RCS (pump start ).
( Question No . 30
TIer 2 Group 2
Importance Rating : R02.6
Technical Reference : 1-50-68-2
Proposed references to be provided to ap plicants du ring exam ination:
Learning Objective: OPT200,RCP Objective 5a
Question Sou rce: New
Question History:
Question Cognitive Level: Lower
10 CFR Part 55 Content: 41.5
Comments: Editorially mod ified A and C wo rding transient vs. accident.
Mes Time: Points: 1.00 Version: oI 23456789
Answer: BBB CDAD BCB Scramble Range: A - 0
( Source :
Cognitive Level: LOWER
NEW Source If Bank:
Difficulty:
Job Position: RO Plant: SEQUOYAil
Date: 412007 Last 2 NRC? : NO
(
Monday , May 07, 2007 3:23:01 PM 48
QUESTIONS REPORT
for SEOUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-0 7
25. 017 A4.02 001
( Given the following plant conditions:
A LOCA has occurred.
RCS pressure is 200 psig.
Due to equipment failures, the crew has transitioned to FR-C.1, Response to
Inadequate Core Cooling.
W hich ONE ( 1) of the following describes operatio n of the RCPs for this event?
A. RCPs are only started following transition to SACRG-1.
B. All available RCPs are started prior to performing secondary depressurization.
C~ If seconda ry depressurization is ineffective as determined by Core Exit
Thermocouple temperature greater than 1200'F, then start one RCP at a time, if
available.
D. Following secondary depressurization and when its associated SG NR level is
greater than 10% and support conditions are established per EA-68-2, Establishing
RCP Start Conditions, then start each available RCP.
A. Incorrect. Reps are started one at a time but the sta rt criteria is 1200 vs 700 of . 700 OF
( is the tempera ture to en ter FR-G. 1 coincident with loss of RVLlS level <42% and is also
used in FR-C.1 to determine if actions are effective.
B. Incorrect. While forced coofing is desirable, Reps are no t running when secondary
depressurization is initiated.
C. Correct. One Rep at a time is starte d if GETs remain > 1200 OF followi ng secondary
dep ressurization until all available Re p s are ru nn ing. To temporarily restore core cooling,
the op era tor is ins truc ted to start Re ps one at a time until core exit res < 120 0°F. The
Reps should force two phase flow through the core , te mporarily keep ing it coo l. Even
single phase forc ed steam flow will coo l the core for so me time provide d the RCPs can be
kep t runn ing and a heat sink is available.
D. Incorrect. early in FR -C.1, operators are directe d to attempt to *esta blish RC P start
co ndition s, but RCPs are not started until secondary depre ssurization is determined to be
unsuccessful much late r in th e C-1. Subsequantiy, when C- 1 directs RCP sta rt, SG(s)
availablility is m et if seco ndary side > 10% ; th en R CP started regardless of EA -68
conditions . RCP damage due to absence or los s of no rm al support conditio ns is an
acceptable consequence in this procedure.
(
Monday, May 07, 2007 3:23:01 PM 49
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5*7*07
Abi~ty to manually operate and/or monitar in the control room: Temperature vaIoes used to determine RCSJRCP operation durng
inadequate core cx:ding (i.e., if applieable. average d fi..-e hiItJe5t values ).
( Question No . 31
Tier 2 Group 2
Importanc e Rating : R0 3.8
Technical Reference: FR-C.1; EP M-3-FR-C.1
Proposed references to be provided to applicants during examination: None
Learning Objective : OPL271FR-C.1 Objective 3
Que stion Sou rce: New
Question History:
Question Cognitive Level: Lower
10 CFR Part 55 Content 41.10
Com ments: Ed itorial change to D Distractor and C answer wording .
MCS Ti me: Poin ts: 1.00 Version: o I 23 4 5 6 7 8 9
( Source: NEW
Answer: CC AAB CA BAD
Source If Bank:
Scramb le Range: A - D
Cognitive Level: WWER Difficul ty:
Job Position : RO Plant: SEQ UOYAII
Date: 412007 Last 2 NRC?: NO
(
Monday. May 07, 2007 3:23:01 PM 50
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
2 6 . 022 A2.03 001
( Given the following plant conditions:
Unit 1 is at 100% power.
The followi ng alarm is received:
1-AR-M6E-E5. MOTOR TRIP OUT PNL 1-M-9
Lower Compartment Cooli ng Fan 1B-B control switch has a white light
ill uminated .
Fans 1A-A and 1C-A are running.
Which ONE (1) of the following describes the primary concem related to this failure,
and the procedural action(s) required?
A. Lower Ice Condenser doors may open due to high DP: Stop one Upper
Compartment Cooling fan to equalize pressure in accordance with 1-AR-M6E-E5.
B. Lower Ice Condenser doors may open due to high DP: Start any Lower
Compartment Cooling fan in standby using the alarm response and 0-SO-30-5,
Lower Compartment Cooling.
C. PZR Enclosure may heat up and cause PZR Safety Valves to leak; Isolate the
tripped coo ler TCV and bypass the in-service Lower Compartment Cooler TCVs to
increase coo ling to the PZR Enclosure in accordance with 1-AR-M6E-E5.
D~ PZR Enclosure may heat up and cause PZR Safety Valves to leak; Start any Lower
Compartment Cooling fan in standby using the alarm respo nse and 0-SO-30-5 ,
Lower Compartment Cooli ng.
A. Incorrect. Containment DP is a concern for other ventilation systems such as purge, or an
e vent such as a LOGA.
B. Incorrect. Containment DP is a concern for other ventilation systems such as purge, or an
event such a s a LOCA. Action to start a fan is correct
C. Incorrect. rev for the trippe d fan is allowed to go open. Not isola ted
D. Correct.
Three fan s should be runn ing. With one in standby, it ma y be started.
(
Monday, May 07 , 2007 3:23:01 PM 51
_.
QUESTIONS REPORT
for S EQ UOYAH 2007 - NRC EXAM RE V F INAL A S G IVEN 5-7-07
Abil ity to (a) predict the impacts 01 the following matfunclicns or opemtio1s on Ihe CCS: and (b ) based on those predictions . use
procedures to correct. control, or:mitiga te the coosecoe-ces of thase malfunctions or opera tions : Fan motor Ihemlal ovef1oadIhigl-speed
(
Question No . 87
Tier 2 Group 1
Importance Rating: SRO 3.0
Technica l Reference : AR-M6E, E5; 0-50-30-5
Proposed references to be provided to applicants during examination: None
Learning Objective: OPT200 .CONTCOO LING Objective 7
Question Source: New
Question History :
Question Cognitive Level: Higher
10 CFR Pa rt 55 Content: 43.5
Comments:
MCS Time: Points: 1.00 Version: oI 23 4 5 6 7 8 9
Answer: DDCDDDAAB D Scramble Range: A - 0
Sou rce : NE W Source If Bank:
Cognitive Level: HIGHER Difficulty:
Job Position: SRO Plant: SEQUOYAH
Date: 412007 Last 2 NRC?: NO
(
Monday, May 07, 2007 3:23:01 PM 52
QUESTIONS REPORT
for SEQUO YAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
27. 022 M .O I 001
( Given the following plant conditions:
Reactor Trip & Safety Injection occ urred due to Large Break LOCA.
Containment Phase B isolation has occurred
All systems responded normally
W hich ONE ( 1) of the following describes the response of the Lower
Compartment Coo lers whe n Phase B is reset?
Fans in A*P AUTO Cool er ERCW Valves
A. remain off Cooler ERCW con tainment
isolation valves open.
B~ start Cooler ERCW containment
isolation valves remain closed .
C. remain off Cooler ERCW containment isolation
valves remain closed.
D. start Cooler ERCW co ntainment isolatio n
valves open.
( A. Incorrect. Fans will start. Valves will remain closed
B. Correct.
C. Incorrect. Fans will start but valve p osition is correct.
D. Incorrect. Correct fan operation but valves will not ope n
ER CW does not realign on Phase B reset. Fans in A-P AUTO will start as the Phase B
is cleared
(
Monday. May 07, 2007 3:23:0 1 PM 53
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability to manuallyoperate andIa monitor irl lhe rontrol room: ccs fans.
( Question No. 13
Tier 2 Group 1
Importance Rating: R03 .6
Technical Reference: 1-47W611-67-3,1-47W61 1-30-4
Proposed referen ces to be provided to appli cant s during examination: None
Learning Objective : OPT200.CONTCOOLlNG, Obj . B.4
OPT200.ERCW, Obj B.4
Que stion Source: Bank
Question History: Sequoayah Bank
Questi on Cogniti ve Level: Lower
10 CFR Pa rt 55 Co nlen t: 41.4
Comments:
( MCS Time: Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer. B A C B A BC CAe Scramble Range : A - 0
Source: BANK Source If Bank: SEQUOYAll BANK
Cogn itive Level : LOWER Difficulty:
Job Position: RO Plant: SEQUOYAH
Date: 4/200 7 Lasl2 NRC?: NO
(
Monday. May 07, 2007 3:23:01 PM 54
QUESTIONS REPORT
fo r SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
28 . 022 AKJ .03 001
( Given the following plant conditions:
Unit 1 is at 100% RTP whe n a smail RCS leak develops.
Th e ope rati ng crew takes the necessary action s to stabilize PZR level.
Subsequently , the crew attempts to determine the leaka ge source.
Aft er iso lating charging and letdown, the crew observe s the foilowing
parameters/indications:
Letdow n flow 0 gpm;
Cntm t press ure approximately 0.3 and de creas ing;
RCS pressure approximately 2235 psig and stable;
pzr level appro ximatel y 82% and increasing;
Cha rging flow 40 gpm;
Cntmt radiation monitors trending down ward slowly.
W hich ONE (1) of the following actio ns will the operating crew perfo rm next?
A. Immediately trip the reactor and enter E-O, Reactor Tr ip or Safety Injection because
PZR level exceeds the maximum limit.
B~ Place excess letdown in service and adjust seal injection flow to maintain PZR level
within limits.
( C. Initiate Emergency Shutdown per AOP-C .03, Emergency Shutd own due to RCS
leakage exceed ing limits.
D. Re-establish normal letdown and dispatch leak search team to identify leakage
source.
A. Incorrect. Applicant may mistake 82 % Pzr level for the reactor trip value of 92 %; however,
the initial conditions do not req uire an immediate reactor trip.
B. Correct. The ReS leak was determ ined to be on norma/letdown based on containment
pressure decreasing and radiation monitor readings stabilized. Therefore to maintain
pressurizer level and ReS chemistry (chemical feed and boretion), excess letdown is
required.
C. Incorrect. Since pressurizer level is stabilized and is controllable by placing Excess
Letdown in service, the other initial conditions indicated the RCS leak has been isolated a
rapid shutdown is not required per AOP-R.05.
D. Incorrect. The leak has been isolated to the normal letdown line. Therefore, a leak search
team is unnecessary.
The student must understand from the initiaf conditions the RCS leak was on the letdown fine
and ha s been isolated. In order to maintain pressurizer fevef and chemistry excess
( letdown is required.
Monday. May 07. 2007 3:23:02 PM 55
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
l<ncI>Medge of the reasons for the IoIIoMng responses as they app/yto the Loss of Reaclor Coolant Pump Makeup : Perfoimance of lineup
( to establish exces s IeldoMl after determining need
Question No. 42
Tier 1 Group 1
Importance Rating: R0 3.1
Technical Reference: AOP-R.05
EA-62-3
Proposed refe ren ces to be provided to ap plica nts du ring examination : None
Learning Objective : OPL271C367, Objectives Obj 2, 4
Question Source : Bank
Question History: AOP R.05-B .2-6
Question Cognitive Level: Higher
10 CFR Part 55 Content: 41 .1 0
Comments: Mod ified 0 distractor.
MCS Time: Points: 1.00 Version: o12 34 56 7 8 9
Answer: B A A C A AA DB C Scramble Range:A - D
Source: BANK Sourc e If Bank: SEQUOYAH BANK
Cognitive Level: Ill GHER Difficulty:
Job Position: RO Plant: SEQUOYAH
Da le : 4/2007 Lasl2 NRC?: NO
(
Monday. May 07. 2007 3:23:02 PM 56
QUESTIO NS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
29. 025 A2.0 1 00 1
( Given the followi ng plant conditions:
Unit 1 is at 100% power.
The following alarm is received:
1-AR-M6E, C7, FLOOR COOLANT DP LO
W hich ONE (1) of the following describes the potential effect of this failure, and the
actio n required to mitigate the effect?
M 1-AR-M6E, 6 6, FLOOR COOLANT TEMP HI, will alarm: Ensure at least 1 Glycol
Floor Circ Pump is running in accordance with 1-AR-M6E, C7.
6 . 1-AR-M6 E, 66, FLOOR COOLANT TEMP HI, will alarm: Swap Glycol Circ Pumps
and chiller packages in accordance with 1-S0-61-1, Ice Condenser.
C. 1-AR-M6E, 67 , FLOOR COOLANT T EMP LO, will alarm: Ensure at least 1 Glycol
Floor Circ Pump is running in accordance with 1-AR-M6E, C7.
D. 1-AR-M6E, 67, FLOOR COOLANT TE MP LO, will alarm: Swap Glycol Circ Pumps
and chiller packages in accordance with 1-S0-61-1, Ice Condenser.
A. Correct: If DP is low, then the floor cooling pump must have tripped, and temperature will
rise
B. Incorrect. Would swap Glycol Pumps and chillers if the Glycol pump tripped.
C. Incorrect. Wrong direction on temperature. Action is correct.
D. Incorrect. Wrong direction on temperature Action is incorrect. Would be taken if a Glycol
e ire Pump tripped.
(
Monday, May 07. 200 7 3:23:02 PM 57
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GI VEN 5-7-07
Ability to (a) predict the impactS of the fo/lolMng malfunctions or operalions on the ice condenser system; correct, contrct or mitigate the
( ccoseoeences of ecee malfunctions or operations: Trip of g/)<:oI eircuIatial pumps .
Question No. 88
Tier 2 Grou p 1
Importa nce Rating : SRO 2.7
Technical Reference: AR-M6 -E, C-7, B-6:
Proposed references to be provided to applicants during examination: None
Learni ng Objective: OPT200 .ICE Objective 5.d
Question Source: New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Content: 43.5
Commen ts:
MCS Time: Points: 1.00 Version: o 1 2 34 5 6 7 8 9
Answer: ADA CB C CAD A Scramble Range : A - 0
Source : NEW Source If Bank;
Cog nitive Level: HIGHER Difficulty:
Job Position : SRO Plant: SEQUO YAII
Date: 412007 Last 2 NRC? : NO
(
Monday, May 07, 2007 3:23:02 PM 58
QUESTIONS REPOR T
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5* 7*0 7
30. 025 A2.06 001
( Given the followi ng plant conditions:
Unit 1 is at 100% power.
Ice Condenser Floor Glycol Temperatu re Control Valve 1-TCV*61-7 1 setpoint
fails .
Ice Condenser floor temperature is 12°F and lowering.
Wh ich ONE (1) of the following describes the potential effect of this failure, and the
action(s) required in accordance with 50-61-1, Ice Condenser?
A. Excessive sublimation of the ice bed; throttle closed 1-TCV-6 1-71 Bypass valve
1-61-751, Temperature Cont rol Valve Bypass Valve .
B. Excessive sublimation of the ice bed; close 1-TCV-61-71 isolation valve and
operate 1-61-751 , Temperature Control Valve Bypass Valve, to control
temperature.
C. Ice Condenser door binding; throttle closed 1-TCV-61-71 Bypass valve 1-61-751,
Temperature Control Vaive Bypass Valve.
D~ Ice Condenser door bindi ng; close 1-TCV-61-71 isolation valve and operate
1-6 1-751, Temperature Control Valve Bypass Valve, to control temperature.
( A. Incorrect. Wrong effect, wrong direction for the valve under the conditions
presented. Would control temperature if valve was open, but valve is normally closed.
B. Incorrect. Wron g effect. Correct actions
C. Incorrect. Corre ct effect. Wrong direction for the valve under the conditions
presented
D. Correct. Temperature swings can cause buckling of the Ice Condenser wear slab,
causing doors to j am. Sublimation happens when temperature is too high. High glycol
flow would cause temperature to be reduced. By isolating the TCV and throttling open
on the bypass valve glycol flow is reduced, allOWing the floor temperature to rise.
(
Monday, May 07, 20073:23:02 PM 59
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability to (a) pred ict the impacts d the following malfunctions or opera tions on the ice cond enser system; COITect. con lr ol. or mitigate the
( consequences 01 thosemafunctions or cceaecos: Decreasingice eeooeose- temperature.
Question No. 14
Tier 2 Group 1
Importance Rating : R02.5
Technical Reference : 50-61-1 , AR-M6E-B7
Proposed refere nces to be provided to appli cants during examination: None
Learning Obje ctive : OPT200.lCE Objective 5
Question Source: New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Content: 41 .10
Com men ts: Editorial change to answers based on NRC comment
Mes Time: Poi nts: 1.00 Versi on: o I 2 34 56789
Ans wer: DDDA CDD AC C Scramble Range: A * D
Source: NE W Source If Bank:
Co gnitive Leve l: HIGHER Difficul ty:
Job Position : RO Plant: SEQUOYAH
Date: 412007 Last 2 NRC?: NO
(
Monday, May 07, 2007 3:23:02 PM 60
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
31. 025 AKI.Ol 00 1
( Given the following plant conditions:
Unit 2 is in Mode 6.
RCS drain ed to elevatio n 701 feet.
Upper internals are installed .
RCS temperature is 110°F.
Core decay heat is approx imately 5 MW.
A total loss of RHR cooling has occurred.
W hich ONE (1) of the following is correct concerning the amcun t of time it will take to
reach 200°F in the RCS using 0-GO- 15. App. U. Time for RCS to reach 200°F?
Reference Provided
A. 26 minutes
B~ 32 minutes
C. 43 minutes
D. 306 minutes
( A. Incorrect. Equation 1 was incorrectly applied to determine value.
Time = 1460[(200-110)/5000KW] = - 26 min
B. Correct. Apply equation 2 of 0-GO-15. Appendix U.
Time = 1780[(200-110)/5000KW] = - 32 min
C. Incorrect. Equation 3 was incorrectly applied to determine value.
Time =2390[(200 -110)/500 0KW] =- 43 min
D. tncottect. Equation 4 was used to determine value.
Time = 17000[(200-110)/5000KW] =306 min
(
Monday, May 07, 2007 3:23:02 PM 61
QUESTIONS REPORT
for SEQUOYAH 200 7 - NRC EXAM REV FINAL AS GIVEN 5-7-0 7
Knowledge of the operatiMaI implications d the foIlONing concepts as they apply to loss of Residual Heat Removal S~Ie-n : loss of
( RHRS during all modes d opEl'"ation
Question No. 43
Tier 1 Group 1
Importance Rating : R03.9
Technical Reference: D-GO-15, App . U
Proposed references to be provided to app licants during exami nation : O*GO*15, App U
Learning Objective : OPL271AOP-R.03, Obj 1
OPL271GO* 15, Obj 16
Question Sou rce: Bank
Question History: A OP-RD3.B.1-6
Question Cognitive Level: Higher
10 CFR Part 55 Content: 41 .5
Comm ents: editorial change to stem based on NRC commen t.
(
MCS Time: Points : 1.00 Version: oI23456789
Answer: B D C CACA B B B Scramble Range: A - D
Source: BANK Source If Bank : SEQUOYAH BANK
Cogni tive Level: HIGHER Difficu lty:
Job Positio n: RO Plant: SEQUOYAH
Date: 4/2007 Last 2 NRC?: NO
(
Monday, May 07, 2007 3:23:02 PM 62
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
32. 026 G2.2.25 001
( Given the following plant conditions:
A loss of Component Cooling Wate r has occurred on Unit 1.
Th e crew is performing actions of AOP M.03, Loss of Component Cooling
Water.
1A Surge Tank level indicates 0%.
1B Surge Tank level indicates 57% and stable.
Assuming no other failures exist, which ONE (1) of the following describes the effect of
this condition, and the action required?
A~ Component Cooling Water System operability meets safety anal ysis assumpt ions.
Trip the reactor.
B. Component Cooling Water System operability meets safety analysis assumptio ns.
Reactor trip is NOT required.
C. Component Coolin g Water operability does NOT meet safety analysis assumptions.
Trip the reactor.
D. Component Cooling Water operability does NOT meet safety analysis assumptions.
Reactor trip is NOT required.
A Correct. Single f ailure loss of 1 train, still have B train available. Trip Rx due to loss
of surge tank level
B Incorrect. Reactor trip is required.
C and 0 are incorrec t because safety function is still met for these conditions. C
contains the correct actions, 0 contains plausible actions for loss of train with TS
implications
(
Monc:lay. May 07. 2007 3:23:02 PM 63
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
EQuipment Control KncM1edge a bases... tecMical specifiea~s for limiting cooditions lor operations and safetyNmits.
( Qu e stion No. 79
Tie r 1 G roup 1
Importance Rating : SRO 3.7
Technical Reference: TS 3.7.3, M.03
Proposed references to be provided to applicants during examination: None
Learning Objective: OPL271AOP-M.03 Objective 5, 6, 9
Que stion Source: New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Content: 43.5
Comments: Editorially modified actions based on NRC comments
MCS Time: Po ints: 1.00 . Version: oI 23456789
Answer. AADDDCC DBD Scramble Range: A - D
Source : NEW Source If Bank:
Cognitive Level: HIGHER Difficulty:
Job Position: SRO Plant: SEQ UOYAH
Dale: 412007 Last 2 NRC?: NO
(
Monday, May 07. 200 7 3:23:0 2 PM 64
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
33. 026 G2.4.6 001
( The following plant conditions exist on Units 1 and 2:
Unit 1 is at 100% RTP.
1 B-B Containment Spray Pump is tagged for maintenance.
Unit 1 CCS is suppl ying the Spent Fuel Pool Cooling System.
C-S CCS pump suffers catastrophic bearing failure.
W hich ONE of the following describes the actions required, if any, to provide B train
cooling for the given conditions in accordance with AOP-M.03, Loss of Component
Cooling Wate r?
A. No requ ired actions.
B~ Only 2B-B CCS pump can be realigned for B train cooli ng.
C. Oniy 1B-B CCS pump can be realigned for B train cooling.
D. Either the 1B-B or 2B-B CCS pump can be realigned for B train cooling .
Justification:
A. Incorrect. The 18-8 and 28 -8 CCS pumps are not aligned for B train cooling and these pumps will
not auto start on a loss of the C-S pump.
B. Correct. Align the unit's B eeS pump that is not aligned to SFP cooling.
C. Incorrect. Align the unit's B eeS pump that is not aligned to SFP coofing.
D. Incorre ct. Align the unit's BeeSpump that is not aligned to SFP coofing.
Knowledge of symptom based EO? mitigation strategies.
Noles:
KIA {CFR}: 026AK3.04 [3.513.71 {41 .S. 41.10}
008A2.01 [3.313.6) {41.S, 43.S}
008 G2 .4.11 [3.4/3 .6) {4 1.10. 43.S}
References: 0-AR-M27-B-B. E-4; AOP-M.03; 0-50-70-1. Sects S.l & 8.4;
LP/Objectives: OPL271C42S. Obj. 3.
History: SON Ba nk
Level: Higher
( Comments:
Monday, May 07 , 2007 3:23:02 PM 65
QU ESTIO NS REPORT
for SEQUOYAH 200 7 - NRC EXAM REV FINAL AS GIVEN 5-7-07
MCS Time: 3 Points: 1.00 Version: 0 1 2 3 4 S 6 7 8 9
( Source: BANK
Answer: B B B B B B B B B B Items Not Scrambled
Source If Bank: SQN BANK
Cognitive Level: HIGHER D ifficul ty:
Job Position: RO Plant: SEQUOYAH
Date : Last 2 NRC?: IL1'2006 PRA C 2
(
Monday, May 07, 2007 3:23:02 PM 66
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
3 4 . 026 K4.01 001
( Wh ich ONE (1) of the following states the interlock(s) that must be satisfi ed before
FCV-72-22 (Containment Spray Suction from RWST ) ("B" train) can be opened ?
A. FCV-63-73 (RHR Suction from Containment Sump) closed.
B~ FCV-72-23 (Containment Spray Suction from Containment Sump) clo sed.
C. FCV-74-21 or FCV-74-3 (RHR Pump Iniet from RWST) control valves closed .
D. FCV-74-21 and FCV-74-3 (RHR Pump Inlet from RWST ) control valve s closed .
A. Incorrect. 63-73 is not required to be open, but 72-21 is required to be closed
B. Correct. Interlock designed to ensure sump and RWST are not cros s-tied
C. Incorrect. 74-2 1 and 3 is not required to be closed.
D. Incorrect. 63-73 is not required to be open
Knowledge of CSS design leature(s) cndIor interiock(s) which proIIide for ee following: Source d water lorCSS. including recirculatioo
phase after LOCA .
Question No. 15
Tier 2 Group 1
Importance Rating: R04.2
Technical Reference: 1-47W611 -72-1; 1-47W611 -74-1; 1-47W611 -6:l-2. 5; 0-45N779-B. l0.
25,26;
Proposed references to be provided to applicants durinq exa mination: None
Learning Objective: OPT200.CS, Obj 12.f
Question Source: Bank
Queslion Histo ry; SQN CSS B.12.F-2
Question Cognitive Level: Lower
10 CFR Part 55 Content: 4 1.7
Comments:
( MCS Time; Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer: BBBB A A CDD B Scramble Range: A - D
Monday, May 07, 2007 3:23:03 PM 67
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXA M REV FIN AL AS GIVEN 5-7-07
Source: BANK Source If Bank: SEQUOYAH BANK
( Cog nitive Level: LOWER
Job Position: RO
Difficulty:
Plant: SEQUOYAI I
Date: 41200 7 Last 2 NRC? : NO
(
Monday, May 07, 2007 3:23:03 PM 68
QUESTIO NS REPORT
for SEQUOYAH 200 7 - NRC EXAM REV FINAL AS GIVEN 5-7-07
35 . 027 G2.4.49 001
( Given the following plan t conditions:
Unit 1 is operating at 100% RTP.
Pressure Contro l Channel Selector Switch, 1-XS-68-340D is selected to
PT-68-340 & 334 position .
PT-68-340 fail s LOW.
All equipment functi ons as designed.
W hich ONE (1) of the following state ments describes (1) the effect on the plant, and
(2) the required actio n?
A. ONE (1) PZR POR V will be inoperable; direct a manual reactor tri p and enter E-O,
Reactor Trip or Safety Injection.
B~ PZR PORVs remain operable; direct manual co ntrol of PZR pressure and enter
AOP 1.04 , Pressurizer Instrument Malfunctions.
C. ONE (1) PZR PORV will be inoperable; direct manual control of PZR pressure and
enter AOP 1.04, Pressurizer Instrument Malfunctions.
D. PZR PORVs remain operable; direct a manua l reacto r trip and enter E-O, Reactor
Trip or Safety Injection .
(
(
Monday, May 07,20073:23:03 PM 69
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXA M REV FINAL AS GIVEN 5-7-07
A. Incorrect. Wrong challenge . PORVs should not be inop as a result of the instrument
( failure, as they are capable of being cycled manually. Incorrect procedure, reactor trip
would not be required. Credible if the applicant thinks the POR V will not operate for this
condition.
B. Correct.TS 3.4.3 bases states that the PORV operability is determined by being
capable of manua l control of PORVs to control reactor coolant system pressure. With
the controlling PZR pressure channel failing low, pressure will rise and be controlled by
PZR PORV 68-33 4. AOP-I- 04, will be used to mitigate the effects ofthe failure.
C. Incorrect. PORV operability will not be affected, correct procedure.
D. Incorrect. Correct that PORVs do remain operable but procedure is incorrect.
Credible if applicant thinks he must rely on manual control of the PORVs to control
pressure and takes conservative actions per EPM-4 to trip reactor.
B. When a paramete r is approaching a protective action setpoint in an
uncontrolled manner, the operator is expected to:
1. Evaluate the parameter magnitude and trend.
2. Take actions as necessary to place the plant in a safe condition without
relying solely on automatic actions.
Emergency Procedures I PIa-1 Ability 10perioml without referencekI procedures !hoseactions thai require immediate operntion 01
syslem components Mel ccntrols.
Question No. 80
Tie r 1 Group 1
Importance Rating: SRO 4.0
Technical Reference: AOP-1.04 , Technical Specification Bases 3.4.3, page B 314 4-2
Proposed references to be provided to applicants durinq exam ination: None
Learning Objective: OPL271AOP-1.04 Objective 3
Question Source: New
Question History:
Question Cognitive Level: Highe r
10 CFR Part 55 Content: 43.5
( Comments :
Monday, May 07, 20073:23:03 PM 70
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
MCS Time: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
( So urce: NEW
Answer: B A C B OD DO C 0
So urce If Bank:
Scramble Ran ge: A - D
Cognitive Level : HIGHER Difficulty
Job Pos ition: SRO Plant: SEQUOYAH
Date: 412007 Last 2 NR C? : NO
(
(
Monday, May 07,20073:23:04 PM 71
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
36. 027 G2.4.6 00 1
( Given the following plant conditions:
A reactor trip and safety injection has occurred on Low PZR pressure.
The crew is performing E-O, Reactor Trip or Safety Injection .
All Train A ECCS equipment is operating as required.
Train 8 ECCS equipment has failed to start.
All RCPs are running.
While performing E*O step 10, Check pressurizer PORVs, safety valves and
spray valve s, the following indications are observed by the OATC:
RCS pressure is 1200 psig.
PZR level is 100%.
PORV 68-340 red position indicator is lit.
Both PZR Spray Vaive indicators are not lit.
W hich ONE (1) of the following describes the actions that are required in accordance
with E-O?
A. Leave RCPs runni ng, attempt to close the failed open PORV and/or block valve.
e 8 . Leave RCPs runnin g, allempt to close the failed open PZR Spray Valve.
C~ Trip RCPs; allemptto close the failed open PORV and/or block valve.
D. Trip RCPs; attempt to close the failed open PZR Spray Valve.
A. Incorrect. RCPs mu st be tripped, and E-O will not be continued if this condition
exists.
B. Incorrect. Correct actions with exception of tripping RCPs.
C. Correct. With RCS pressure < 1250 psig and 1 SI or CCP running, trip RCPs, E-O
step 10 RNO directs operators to attempt to close the PORVl s), associated Block
Va/vels) and tran sffion to E-l if the failed valves cannot be isolated.
D. Incorrect. Correct actions for RCPs. Applicant may confuse spray valves, they
should not be open in the stated conditions.
(
Monday, May 07, 2007 3:23:04 PM 72
QUESTIONS REPORT
for S EQUOYAH 2007 - NR C EXAM RE V FI NAL AS GIVEN 5-7-07
EmergencyProcedures ' Plan Knowledge S)'1TlPtcm based EOP mitigalion strategies.
( Question No. 45
Tier 1 Group 1
Importance Rating : R0 3.1
Techni cal Refere nce: E-O . step 10 RNO, E-O Foldout/Handout Page ; EPM-3-E-0 pgs
18&22/64
Proposed referen ces to be provided to appli cants during exami nation: None
Learning Objective: OPL27 1E-Q Objective 5
Question Sou rce: New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Content: 41.10
Comments: editorial change to A and B base d on NRC comment. Removed all from stem.
MCS T ime: I Points: 1.00 Version: 0 1 2 3 4 5 6 7 8 9
An swer: CADA DC BB C D Scramb le Range : A * D
( Source : N EW Source If Bank :
Cognitive Le vel; HIGHER Di fficulty:
Job Position : RO Plant: SEQUOYAH
Date: 412007 last 2 NRC? : NO
(
Monday, May 07. 2007 3:23:04 PM 73
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7 -0 7
37 . 028 AlO .05 001
( Given the following plant conditions:
Unit 1 is at 100% power.
Load is being reduced to 50 % to remove a Main Feedwater Pump from service.
Pressurizer Level Control is selected to L1-68-339.
Th e Pressurizer Level Master Controller setpoint fail s at its current value.
The load reduction is initiated .
Whic h ONE (1) of the following describes the effect on the unit and the action(s)
required?
A. Actual pressurizer level will be higher than program level for the actual power level
as load is decreased;
Change the pressurizer level channel input to the master controller and restore
Letdown.
B~ Actual pressurizer level will be higher than program level for the actual power level
as load is decreased ;
Take manual contro l of Charging fiow .
C. Actual pressurizer level will be lower than program level for the actual power level
as load is decreased;
Take manual control of Charging fiow .
D. Actual pressu rizer level will be lower than program level for the actual power level
as load is decreased;
Change the pressurizer level channel input to the master controller and restore
Letdown.
A. Incorrect. Changing inpul will not affect the controller because the setpoint has
failed, not the input
B. Correct.
C. tncorrect. Charging flow must be reduces because level will be artificially high
D. Incorrect. Changing input will not affect the controller because the setpoint has
failed. Letdown will not isolate because actual level will indicate the same on all
channels
(
Monday, May 07, 2007 3:23:04 PM 74
QUESTIONS REPORT
for SEQUOYAH 200 7 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowtedge 01 the reascns for the following responses as Ihey apply 10 the PressLriz er level Conlrol ~nctions : Actions contained in
EOP for PZR level metfunction .
( KA Match Jl,I$tification: KA is matched since Ihe actions for this failure are included in ARP's vs. EOP's . Actions would be the same if
faiue occured during performance of EOP's .
Question No . 59
Tier 1 Group 2
Importance Rating:
Technical Reference : 1-AR-M5-A E-4
Proposed references to be provided to applicants dunnq exam ination: None
Learning Objective: OPT200.PZRL CS Objective 5.d
Question Sou rce : New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Co ntent: 41.10
Co mments :
MCS Time: Po ints: 1.00 Versi on : oI 23 4 5 6 7 8 9
Answer: BBD AAAA BAA Scramble Range : A * 0
Source: NEW Source If Bank
Cognitive Level : H IG HER Difficulty:
Job Position: RO Plant: SEQ UO YAH
Date : 4/2007 Last 2 NRC? : NO
(
Monday, May 07,20073:23:04 PM 75
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
38 . 028 K6.01 001
( Given the following plant conditions:
Unit 1 was at 100% power
A LOCA has occurred
W hich ONE ( 1) of th e following describes the effect on Containment if B train
Hydrogen Recombiner is lost afte r SI initiates?
Containment hydrogen concentration will _
A~ remain below 4%.
B. increase to greater than 4% but tess than 8%.
C. increase to greater than 8% UNLESS Containment Purge is placed in servi ce.
D. increase to greater than 8% UNLESS Hydrogen Igniters are placed in service .
A. Correct. A single recombiner is designed to maintain H2 < 4% during a design basis
LOCA.
B. Incorrect. 4% is as high as concentration will get with only 1 recombiner in service
C. Incorrect. Purge not required to maintain design basis
D. Incorrect. Ignfters not required to maintain design basis
(
Monday, May 07 . 2007 3:23:04 PM 76
QUESTIONS REPORT
fo r SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledge of the effect of a loss or m~bon m the ft*lwing win have on the HRPS: H)(Jrogen reccnbnes.
( Question No. 32
Tier 2 Group 2
Importan ce Rating: R0 2.6
Technical Reference: etmt Combustible Gas Control Handout
Proposed referen ces to be provided to applicants during examination: None
Learn ing Objective: OPT200.CGCS. Obj. 5.d
Question Source: Bank
Question History: SQN CTMT COM GAS B.15.A-1
Que stion Cogn itive Level: Lower
10 CFR Part 55 Content: 41.8
Commen ts: Removed 1A-A DG being OO S from stem base d on NRC comments
Mes Tim e : Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer: A D B D D DCA A D Scramb le Range: A - D
Source: BANK Source If Bank: SEQUOYAll BANK
Co gnitive Level: WWER Diffi culty:
Job Posi tion : RO Plant: SEQUOYAll
Date: 412007 Last 2 NRC? : NO
(
Monday. May 07, 2007 3:23:04 PM 77
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
39. 029 A4.01 00 1
( Given the following plant conditions:
Unit 1 is in Mode 6.
A Containment Purge is planned .
W hich ONE (1) of the following conditions requires a limit on the maximum fiow for
Containment Purge, and what is the maximum flow for the condition in accordance with
SO-30-3, Contai nment Purge System Operation?
A. Fuel Handling activities inside containment are in progress; 8,000 CFM
B~ Fuel Handl ing activities inside conta inment are in progress; 16,000 CFM.
C. SFP Fuel Transfer Tube is open ; 8,000 CFM
D. SFP Fuel Transfer Tube is open; 16,000 CFM.
A. Incorrect. Flow limit is too low by half
B. Correct. If Fuel Handling activities are in progress, 16,000 CFM is the limit.
C. Incorrect. SFP level may be affected on initial startup of Purge. Limit is too low
D. Incorrect. No limit on Purge flow based on Transfer Tube position. There are
concerns about level change s in the SFP when operating ventilation in containment,
but no minimum or maximum purge flow restrictions
(
Monday, May 07, 2007 3:23 :04 PM 78
QUESTIONS REPORT
for S EQUOYAH 2007 - NRC EXA M REV FINAL AS GIVEN 5-7-07
Ability to manually operate aldIormonitor in the control room: Contairment purgeflow rate.
( Question No. 33
Tier 2 Group 2
Importance Rating: R0 2.5
Technical Reference: 0-S O-30-3
Proposed references to be provided to applicants during examination: None
Leaming Objective: OPT200.CONTPURGE Objective 5
Question Source: New
Ques tion History:
Question Cognitive Level: Lower
10 CFR Part 55 Content: 41.10
Commen ts:
MCS Time: Points: 1.00 Version: o 1 23 4 5 6 7 8 9
Answer: BCC BD DACBC Scramble Range : A - D
Source: NEW Source If Bank:
Cognitive Level : LOWER Difficulty;
Job Position: RO Plant: SEQUOYAH
Date : 412007 Last 2 NRC?: NO
(
Monday, May 07.20073:23:04 PM 79
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
40. 029 02.2.25001
( W hich ONE (1) of the following describes the purpose of the AMSAC system during an
ATW S?
A. ONLY prevents exceeding the Reactor Core Safety Limit .
B. ONLY prevents exceedi ng the RCS Pressure Safety Limit .
C. ONLY maintains Fuel Integrity.
D~ Maintains Fuel Integrity AND prevents exceeding the RCS Pressure Safety Limits.
A. Incorrect. Maintains Fuel Integrity AND prevents exceeding the RCS Pressure
Safety Limits
B. Incorrect. Also maintains fuel integrity.
C. Inorrect. AMSAC operation also pre vents exceeding pressure safety limits.
D. Correct. AMSAC operates to prevent exceeding the overpressurization and fuel
integrity safety limits.
FSAR 7.7.1.12
The design of the AMSAC system shall comply with 10 CFR 50.62 "Requirements for Reduction of
( Risk from ATWS Events for light-Water-Cooled Nuclear Power Plants: The function of AMSAC is to
mitigate the effects of an ATWS by providing alternate means of tripping the main turbine and
actuating auxiliary feedwater (AFW ) flow independent from the reactor protection system (RPS).
AMSAC actuation will mitigate a common mode failure within RPS upon detection of low-low steam
ge nerator levels ex isting in three-out-of-f our steam ge nerators coincide nt with plant power lev els above
approximatel y 40 percent. This actuation will prevent reactor coolant system (Re S) overpressurizatio n,
ma intain fuel integ rity, and meet 10 C FR 100 radiation relea se requirements.
Monday, May 07, 2007 3:23:04 PM 80
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Equipment Control Knc:JwIedge of bases irl teetv1iCaI specifica\ic:l'ls for limiting conditions lor operations end safety limits.
( KA justificatia'l: The KA is met by the fact eat the AMSAC circuitry is relied on in Ted1 Specs to pl'eva'lt exceeding the TIS safety limits .
Question No. 46
Tier 1 Grou p 1
Importance Rating : R0 2.5
Te chnical Reference : T5 2.1.2
Proposed references to be provided to app licants during exa mination: None
Learning Objective :
Question Source: New
Que stion History:
Question Cognitive Level: Lower
10 CFR Part 55 Content: 43.2
Comments:
Mes Time: Po ints: 1.00 Vers ion: o I 23 4 S 6 7 8 9
Answer: DC ABBCDAB C Scramb le Range : A - 0
Source: NE W Sourc e If Bank :
Cognitive level: LOW ER Difficu lty:
Job Position: RO Plan t: SEQUO YAII
Date: 4/2007 Last 2 NR C?: NO
(
Monday. May 07, 2007 3:23:04 PM 81
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
41. 034 A3.0200 1
( Whi ch ONE (1) of the following describes the function of the Unit 1 Manipulator Crane
SENSOTEC load system interlock, SEN-8H, Light Assemb ly Overload Limit Switch?
A~ Stops upward motion of the hoist and illuminates the overload light.
B. Prevents gripper from disengaging.
c. Stops hoist travel in the down direction, if over the reactor core and the gripper is
not disengaged.
D. Stops bridge travel at the edge of the reactor until the trolley is alig ned with the
transfer system centerline.
A. Correct:
B. Incorrect: explanalion for SEN 6H gripper safely. If the readout shows 1200# or
more, fhe gripper air solenoid valve will nof operate fa allow gripper to
disengage .
C. Incorrect. Lima switch LS-9 is a GEMCO geared limit switch (GL-2). This limit
switch stops fhe hoist in the down direction, if over the reactgor core and the
gripper is not disengaged.
D. Incorre ct - LS-6 operates to open a contact to stop bridge travel at the edge of
the reactor until the trolley is aligned with the transfer system centerline.
(
Monday, May 07, 2007 3:23:04 PM 82
QUESTIO NS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability to monitor a utoma tic operation of th e Fuel Handling System, includin g: load limit s
(
Question No. 36
Tier 2 Grou p 2
Importance Rating : RO 2.5
Technical Reference :
Proposed references to be provided to ap plicants du ring examination: None
Learning Objective : OPT200.FH objective 8 .12.0
Question Source: Bank
Question History: SON Bank
Question Cognitive Level: Lower
10 CFR Part 55 Content: 41.11
Comm ents:
MCS Time: Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer: ABDe CADD0 C Scramble Range: A - 0
( Source:
Cognitive Level:
BANK
LOWER
Source If Bank: SQN BANK
Difficul ty:
Job Posit ion: RO Plant: SEQUOYAH
Dale: 4/2007 Last 2 NRC?: NO
Monday, May 07, 2007 3:23:05 PM 83
QU ESTIO NS REPORT
for SEQUOYAH 2007 - NRC EXA M REV FINAL AS GIVEN 5-7-07
42. 035 K5.03 001
( Wh ich ONE (1) of th e foll owing descr ibes the basis for prog rammed SG level
setpoi nts?
A. 33% level at low power is low enough to preve nt fio od ing of the moi sture
separators from a 10% step load increase.
B. 44% above 20% power is low enough to minimize water carryover from a
postulated stea m line break.
C~ 44 % above 20 % power is high eno ugh to minimize th e probability of a reactor trip
caused by shrink due to a load rejection at high pow er.
D. 33% at low power is high enough to keep th e SG feed ring cove red in th e eve nt of
an Inadvertent MSIV clo sure.
C is correct.
A is incorrect because it is part of the basis for 44 % at higher powe r
B is incorrect because it is part of the basis for 33%
D is incorre ct but credible beca use an MS/V closure will cause shrink. Just not part of
the consideration for programmed level
Knowledge of operational implications of the following concepts as the apply to the SlGS: Shrink and swell concept.
Question No. 34
( Tier 2 Group 2
Importa nce Rating: R0 2.8
Technical Reference : SQN.OO' D .SG P9 69-71
Proposed references to be provided to applicants during examination: None
Learning Objective: OPT200 .SG. Obj 13.c. 15.8
Question Source: New
Question History:
Questio n Cognitive Level: Lower
10 CFR Part 55 Content: 41.4
Comments:
MCS Time: Poin ts: 1.00 Version : oI 23 4 S6 7 89
Answer: C A A BCAC B A A Scramble Range: A - D
Source : NEW Source If Bank:
Cognitive Level : LOWE R D ifficulty:
( Job Positio n:
Date:
4/2007
Plant:
Last 2 NRC?:
SEQUOYAH
NO
Monday, May 07 , 2007 3:23:05 PM 84
QUESTIONS REPORT
for SEQUOYA H 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
43 . 038 EKJ.06 001
( W hen perfo rming E-3, Steam Generator Tube Rupture, why is it important to isolate
the ruptured steam ge nerato r from the intact steam generators?
A. Ensures that RCS pressure, during the RCS depressurization following the
cooldown, does not reach the RCP trip criteria .
B~ Ensures RCS SUbcooling is maintained when primary to secondary leakage is
terminated in subsequent steps .
C. Ensures that the subsequent cooldown will NOT result in a challenge to the PTS
Safety Function.
D. Ensures that the differenti al press ure between the intact and ruptured SGs remains
high enough to ens ure earl y detection of subsequent failures .
A. Incorrect. RCP trip criteria is not applicable following operator initiated cooldown.
B. Correct. Cooling down the ruptured SG by depressurizing it will cause a higher OP,
and more flow, from the RCS to the SG.
C. Incorrect. Challenge s to Integrity are controlled by C/O rate.
O. Incorrect. Having a OP between the ruptured and intact SGs does not ensure early
detection of additional failures. Applicant may confuse this with the step following
cooldown that checks delta P between ruptured and intact SGs to diagnos e a faulted
and ruptured SG.
(
Monday, May 07, 2007 3:23:05 PM 85
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5*7*07
Knowledge of the reasons for the following respcn ses as the apply to the SGTR; Actions contain ed in EOP for RCS water ~tory
balance, SIG tube rupture, ald pIalt shut<bNn pceeeoee
( Question No. 47
Tier 1 Group 1
Importance Rating: R04.2
Technical Reference : E-3 Basis
Proposed references to be provided to app licants duri ng examination: None
Learning Objective: OPL271 E-3 Objective 4
Question Source: Bank
Ques tion History : Callawa y 2005
Question Cognitive Level: Lower
10 CFR Part 55 Content: 41.10
Commen ts: mod ified A distractor based on NRC comme nt.
MCS Time: Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer: B CD 0 A C e B O D Scramble Range: A - D
Source : BANK Source If Bank: CALLAWA Y 200S NRC
Co gnitive Level: LOWER Difficu lty:
Job Position: RO Plant: SEQUOYAll
Date : 412007 Last 2 NRC?: NO
(
Monday. May 07, 2007 3:23:05 PM 86
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
44. 039 A2.04 OO J
( Given the following plant conditions:
Unit 2 is at 15% power during startup.
Steam Dumps are operating in the Steam Pressure mode.
Main Steam Header pressure instrument PT-1-33 fails high.
W hich ONE (1) of the following describes the effect on the unit, and the actions
requir ed to control RCS temperature?
A. Steam Dumps will fail closed .
Place and maintain the Steam Dump mode selector in OFF/RESET, then place the
controller in MANUAL and throttl e open the steam dumps .
B. Steam Dumps will fail open .
Place and maintain the Steam Dump mode selector in OFF/RESET, then place the
contro ller in MANUAL and throttle closed the steam dumps.
C. Steam Dumps will fail closed.
Place and maintain the steam dump controlle r in MANUAL and throttle open the
steam dumps.
D~ Steam Dumps will fail open.
Place and maintain the steam dump controller in MANUAL and thrott le closed the
steam dumps.
A. tncotrect. Dumps will open becau se they are already armed due to being in steam
presure mode. Credible because steam dump has arming and modulation signals in
Tave mode that could require this action
B. Incorrect. Dumps will open because they are armed from being in steam pressure
mode. Credible because steam dump has arming and modulation signals in Tave mode
that could require this action
C. Incorrect. Failure of dumps is opposite from what will actually occur
D. Correct. Operator will have to take manual control of the steam dump s in
accordance wah procedure GO-4 and AOP-S.05 to close the steam dump valves and
then control RCS tempera ture.
In Steam Pressure mode, the steam dump s have an arming signal already in.
Dumps must be placed in manual when the presure input fails, so they can be operated
(
Monday. May O?, 2007 3:23:05 PM 87
QUESTIONS REPORT
for SEOUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Ability to (a) predict the impacts of !he fol\olNing mal-func\ic:l'ls Of operations on the MRSS; and (b) based al pre:lictiol'ls, use procedures
to correct, CXlfltrol, or mitigate !he cons equences of those malfunctions or operations: Malfunctioning steam dump .
( Question No. 17
Tier 2 Group 1
Importance Rating: R03.4
Te chnical Referen ce : OPT200.S0S
Proposed refe rences to be provided to applicants du ring exa minatio n: None
Learning Objective : OPTZOO.S OCS Objective 5.d
Question Source: New
Question History :
Question Cognitive Level: Higher
10 CFR Part 55 Conlent: 41.4
Comments: Mod ified A and B distra ctors to read similar to C and D based on NRC co mment.
MCS Time: Points: 1.00 Version: o I 23 4 567 89
Answer: DB AD DCACAC Scramble Range: A - D
Source : NEW Source If Bank:
Cognitive Level: HIGH ER Difficul ty:
Job Position: RO Plant: SEQUOYAI I
Date: 4/2007 Las12 NRC? : NO
Monday, May 07, 2007 3:23:05 PM 88
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
45 . 0) 9 AJ.02 00 1
( Given the following plant conditions:
A plant cooldown is in progress.
RCS pressure is 1850 psig.
RCS temperature is SOS* F.
All required actions have been taken for the cooldown in accordance with plant
procedures.
An event occurs:
RCS pressure is 1700 psig and lowering at 10 psi per second.
SG pressures are 700 psig and lowering at2S psi per second.
Contai nment pressure is 1.2 psig and rising.
Assuming all equipment operates as designed , which ONE (1) of the following
describes the ESF actuation status?
A. Safety Injection has occurred ; Main Steam Line Isolation has occurred .
B. Safety Injection has occurred; Main Stea m Line Isolation has NOT occurred.
C~ Safety Injection has NOT occurred; Main Steam Line lsolatlon has occurred.
D. Safety Injection has NOT occurred ; Main Steam Isolation has NOT occurred .
A. Incorre ct. 51is blocked and has not occurred
B. Incorrect. Actuations are reversed from actual
C. Correc t.
D. Incorre ct. MSLI would actuate on rate. Si is blocked
Below P-l1 , Low Steam pressure 5 1is blocked. High negative rate MSLI at 100 psi per
50 seconds is reinstated. CNM T pre ssure is not yet high enough to cause 51
(
Monday, May 07,20073:23:05 PM 89
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Abi lity to monitor automaticoperation cI the MRSS , including: Isolation d the MRSS.
( Quest ion No. 16
Tier 2 Group 1
Importance Rating : R0 3.1
Proposed references to be pro vided to applicants during examina tion: Non e
Learning Objective: OPT200.RPS. B.4.g & h
Quest ion Source : New
Que stion History:
Question Cognitive Level: Higher
10 CFR Part 55 Content: 41.7
Comments: editorial re vision of answers to ma ke them read the sam e ba sed on NRC
comment.
MCS Time: Points: 1.00 Version: 0 I 2 3 4 5 6 7 8 9
Answer. C C A B A B BAD C Scramble Range: A - 0
Source : NEW Source If B ank:
Cognitive Level: HIGH ER Difficulty:
Job Position : RO Plant: SEQUOYAll
Date : 4/2007 Last 2 NRC?:
(
Monday. May 07, 2007 3:23:05 PM gO
QUESTIONS REPORT
fo r SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
4 6 . 039 G2.1.32 001
( Given the following plant conditions:
A reactor trip and safety injection has occurred .
Prior to the trip, #1 Main Steam Line radiation was in alarm.
The crew is preparing to tra nsition from E*O, Reactor Trip or Safety Injection.
The current conditions exist:
RCS pressure is 1550 psig and lowering slowly.
SG 1 pressure is 300 psig and lowering slowly.
SG 2, 3, and 4 pressures are 650 psig and stable .
Contai nment Pressure is 2.3 psig and rising slowly.
W hich ON E ( 1) of the following describes the procedure transition required from E-O,
and appropriate actio ns to be ta ken after the transition to mitigate the even t?
A~ E-2, Faulted SG Isolation; SG 1 will NOT be used for a controlled RCS cooldown.
B. E-2, Faulted SG Isolation; SG 1 MAY be used dUring a controlled RCS cooldown
until no longer required for seco ndary heat sink.
C. E-3, Steam Generator Tu be Rupture; TDAFW Pump steam suppiy will be isolated
from SG 1.
( D. E-3, Steam Gene rator Tube Rupture; TDAFW Pump steam supply may remain
aligned to SG 1 until no longer requi red for secondary heat sink.
A. Correct: Caution in E-2 alerts SRO to not unisolate a faulted SIG unless needed
for RCS cooldown. With 3 S/Gs intact, the faulted S/G should rema in
isolated.
B. Incorrect: the faulted S/G should not be considered for cooldown under given
conditions. This is the reverse of the caution in E-2, which state the
faulted SG should not be unisolated unless needed for RCS cooldown .
Applicant may may misinterpret the caution.
C. Incorrect E-2 transition is prior to the E-3 transition in E-O. E-3 will be entered after
addressing E-2, Faulted SI G Isolation, if conditions still exist. Could
potentialy enter ECA-3. 1 if the faulted SG is also ruptured. Correct
action for isolating the TDAFWP.
D. Incorrect: E-2 transition is prior to the E-3 transition in E-O. E-3 will be entered after
addressing E-2, Faulted S/G Isolation. Incorrect E-3 caution.
(
Monday, May 07, 2007 3:23:05 PM 91
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Conduct aI Operations : Ability to ID:Plain and apply all system limits and precautions.
( Question No. 89
Tier 2 Group 1
Importance Rating: SRO 3.8
Technical Reference: E-O, E-2, E-3
Proposed references to be provided to applicants during examination: None
Learning Objective:
Question Source: New
Question History: New
Question Cognitive Level: Higher
10 CFR Part 55 Conlent: 43.5
Com ments:
Mes Time: Points: 1.00 Vers ion: o12 3 4 5 6 7 8 9
( Source: NEW
An swer: ACDC DC CCAB
Source If Bank:
Sc ramble Range: A - D
Cognitive Level: HIGHER Difficu lty.
Job Position: SRO Plant: SEQUOYAH
Date: 4/2007 Las t 2 NRC! : NO
(
Monday, May 07, 2007 3:23:05 PM 92
QUESTIONS REPORT
for SEQUO YAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
47 . 04 1 A2.03 001
( Given the foll owing plant conditions:
Unit 1 is at 12% power during a plant startup.
A loss of Essential and Non-Essentia l Control Air has occurred.
The crew is attempting to restore Control Air in accordance with AOP-M.02,
Loss of Control Air.
RCS temperature is 559°F and risin g.
PZR level is 91% and rising.
Whi ch ONE (1) of th e followi ng describes the effect on the unit, and identifies the
procedure that will be used to control RCS temperature while performing EOPs?
Trip the reactor due to...
A~ pressurizer level approaching an RPS setpoint.
Manual actions to control RCS temperature are contained in EA-1-2, Local Control
of SIG PORVs .
B. pressurizer level approaching an RPS setpoi nt.
Manual actions to control RCS temperature are contained in AOP-M.02.
C. OT Delta T approac hing an RPS setpoi nt.
Manual actions to control RCS temperature are contai ned in EA-1-2, Local Control
of SIG PORVs.
D. OT Delta T approaching an RPS setpoint.
Manual actio ns to cont rol RCS temperatu re are contained in AOP-M.02.
A. Correct. Trip based on loss of PZR level control, with trip occurring automatically at
92%. SG PORV 1 and 4 have reached rods and may be contro lled manually, but
pro cedure calls for any or all PORVs. .
B. Incorrect. POR Vs 1 and 4 have reach rods, but all 4 POR Vs may be used
C. Incorrect. Loss of RCS temperature control is not the reason for the trip.
Subsequent temperature control is correct
D. Incorrect. POR Vs 1 and 4 have reach rods, but any POR Vs are used. RCS
temperature control is not the reason for the trip, although at 12% po wer wah steam
dump s ope n, it does cause problem s
92% PZR level is trip criteria in M.02
Monday, May 07 , 2007 3:23:05 PM 93
QUESTIONS REPORT
far SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Abil ity 10 (a) predict the impacts of the foll(;:,Mng matfunclions or operations on the 5 DS; aoo (b) based on those predictions or mitigate
( the consequences cA those ~nctions or cceceecos: Loss of lAS.
Question No. 92
Tier 2 Group 2
Importance Rating : SRO 3.1
Techn ical Reference: M.02
Proposed referen ces to be provided to applica nts during exa mination: None
Learning Objective: OPL271AOP-M.02, B.8.b
Qu estion Source: New
Question History:
Question Cognitive Level: Higher
10CFR Par1 55 Content: 41 .7, 41.10
Commen ts: Modified answers to eliminate 1 and 4 ONLY based on NRC co mment. Also took
out concurrent u se statement at end of each option, as it was redu ndant
MCS Time: Points : 1.00 Version: o12 3 4 56 7 8 9
Ans wer: AD BA CD C CA C Scramble Range: A * D
Sou rce: NEW Source If Bank:
Co gnitive Leve l: HIGHER Difficulty:
Job Position: SRO Plant SEQUOYAH
Dale: 412007 Lasl 2 NRC?: NO
(
Monday. May 07,2007 3:23:06 PM 94
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
48. 045 G2.4.30 00 1
( Power is at 56% when a Main Generator Differential relay actuation occurs.
Which ONE (1) of the following describes the MOST LIMITING NRC reportab ility
requirem ent, if any, for this event?
Reference Provided
A. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> notification
Bl" 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification
C. 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification
D. No reportability required
A. Incorrect. Generator trip does not require a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> report
B. Correct. 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> report is most limiting notifica tion requirement per 50.72(b)(2)(iv)(B)
C. Incorrect. 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> report also required per 50.72(b)(3)(iv)(A), but is not the most
. limiting
c D. Incrrect. Notification is required, but applicant may misinterpret reactor po wer and
not think a Main Genera tor differential will result in a reactor trip.
(
Monday, May 07, 2007 3:23:06 PM 95
QUESTIONS REPORT
fo r SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7 -07
Emergency Procedures I Plan KnO'Nledge of which events related to system operations/status should be reported to outside agen cies.
( Question No. 93
Tier 2 Group 2
Importance Rating: SRO 3.6
Techn ical Reference : SPP-3.5
Proposed references to be provided to applicants during examination: SPP-3.5. Appendix A
Learning Objective: OPL271C168 Objective 2
Question Source: New
Question History:
Question Cognitive Level: Higher
10 CFR Part 55 Content: 43.5
Comments : Modified answer to ask the most limiting notification requirement based on NRC
comment.
MCS Time: Points: 1.00 Version: oI 2 34 567 89
Answer: B D DB A A A C D C Scramble Range : A - D
Source : NEW Source If Bank :
Cogn itive Level: HIGH ER Difficulty:
Job Position: SRO Plant: SEQUOYAI I
Date: 412007 Last 2 NRC?: NO
(
Monday. May 07. 2007 3:23:06 PM 96
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
49 . 055 EK3.0 1 001
( Which ONE (1) of the follow ing describes the minimum amount of time and reason why
the station batteries (and load shedding instructions) are designed to ensure DC
power is available after a loss of all AC power?
Time Reason
A. 2 Hours station blackout rule
B. 2 Hours technical specification requirement
C~ 4 Hours station blackout rule
D. 4 Hours technical specification requirement
a. Incorrect, batteries are rated (with load shedding) for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, without chargers to
provide necessary DC po wer to ma intain BOTH reactors at hot shutdown after a
loss of ALL AC sources. Applicant may cofuse time with Tech Spec action time.
b. Incorrect, batteries are rated (with load shedding) for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, without chargers to
provide necessary DC powe r to maintain BOTH rea ctors at hot shutdown after a
c loss of ALL A C sources
c. Correct.
d. Incorrect, batteries are rated (with load shedding) for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, without chargers to
provide necessary DC power to maintain BOTH reactors at hot shutdown after a loss of
ALL AC sources
Monday, May 07, 2007 3:23:06 PM 97
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
Knowledge of the reasons for the following responses as the apply to the Station Blackout: Length of timefor which battery capacity is
(
designed
Question No. 48
Tier 1 Group 1
Importance Rating: R02 .7
Technical Reference: FSAR 8.0 Electric Power, 8.1.4 Design Basis
Proposed refer ences to be provided to applicants during examination :
Learn ing Objective: OPL271ECA-Q.O, Obj 3.a
OPL273C0527, Obj 5
Question Source: Bank
Question History: 2004 NRC Exam
Question Cognitive Level : Lowe r
10 CFR Part 55 Conten t: 41.8
Comments:
MCS Time: Points : 1.00 Version: 0 1 2 3 45678 9
Answer: C C A D D A C B B C Scramble Range: A - D
So urce : BANK Source IfB ank: SEQUOYAl l 2004 NRC EX
Cognitive Level: LOWER Difficulty:
Job Position: RO Plant: SEQUOYAl l
Date: 4/2007 Las t 2 NRC?: YES
(
Monday, May 07, 2007 3:23:06 PM 98
QUESTIONS REPORT
for SEQUOYAH 2007 - NRC EXAM REV FINAL AS GIVEN 5-7-07
50. 056 G2.4 .31 00""';;----,---_--,-----,---_ _= -,
( Given the following plant conditions:
Unit 1 is at 80 % power.
- The following alarm is received:
1-AR-M1-B, B3, 6900V UNIT BD 1C FAILURE OR UNDERVOLTAGE
Unit Board 1C has an 86-1 C relay, Unit Board Differential Lockout, actuated.
Which ONE (1) of the following describes the unit condi tion and the actions required in
accordance with the alarm response?
A~ A faul t on Unit Board 1C; The unit should have tripped ; Trip the reactor and enter
E-O, Reactor Trip or Safety Injection.
B. A fault on Unit Board 1C; The board should have transferred to the alternate
feeder; Ver ify the alternate feeder is closed and ope rate the normal feeder control
switch to clear the disagreement ligh t.
C. Loss of Off-Site power to Unit Board 1C; The unit should have tripped ; Trip the
reactor and enter E-O, Reactor Trip or Safety Inject ion .
D. Loss of Off-Site power to Unit Board 1C; The boa rd shou ld have transferred to the
S
alte rnate feede r; Verify the alternate feeder is closed and operate the normal
feeder control switch to clear the disagreement light.
--"7"""-=----:--~:;---;- -;-;-;------,-;-__;______;_-____;_;.~=;::o_;_;___c_-_;:__--__;.;___---.J
A. Correct. Unit should have tripped on loss of #3 RCP. If undervoltage was the
cause, the bus should have transferred and there will not be an 86 on it.
B. Incorrect. Transfer would only occur for undervoltage.
C. Incorrect. LOOP incorrect because of the red flag on the alternate feed, and the
presence of no other alarms.
D. Incorrect. LOOP incorrect due to red flag and no other alarms. If it was a loss of
off-site feed, bus would transfer.
(
Monday, May 07,20073 :23:06 PM 99