ML101590385
| ML101590385 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/28/2010 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML101590385 (201) | |
Text
TURKEY TURKE POINT NRC Y POINT NRC EXAM EXAM - 05109/0
- 05/09/07 7
Q#1 Q #1 Operators Opera are respo tors are responding nding to to aa main main steam steam line line break break inside inside Unit Unit 33 conta containm inmen t.
ent.
- Containm Conta inmen entt press pressure peakepeaked at 26 d at 26 psig psig and and is is now now 15 15 psig.
psig.
15% and and loweri lowering.ng.
- No charg No charging pumps ing pump are runnin s are runningg
- Step 10 Step 10 ofof 3-EOP 3-EOP-E- 1, "Loss
-E-1, Loss ofof React Reactor or Secon or or Secondar daryy Coola Coolant, nt," direct directss establishm estab lishmeent nt ofof maxim maximum um charg charging ing flow.
- Seal Water Seal Water Return Return tempe temperatu res rature are at s are at 245°F 245°F..
- The Unit Unit Super Supervisovisorr orders orders closur closure of the local seal injecti e of injection on valves valves,, 297 A/B/C, before AlBIC before startin startingg the first charg charging ing pump pump..
Which ONE of the follow followinging descr describes ibes why the local seal injectiinjection on valves valves are closed closed time?
at this time?
CCW flow to the thermal barrie barriersrs has:
A. been lost.
RCP seals alread alreadyy have elevatelevated ed tempe temperaturature s and initiati res initiation on of cold seal injection injecti on flow will causecause RCP seal dama damage. ge.
B. been lost.
RCP seal tempe temperaturatureress are still in the allowe allowed d range range..
Maximum charg charginging flow to the RCS loops loops via the normanormall charg charging ing path is required.
requir ed.
C. NOT been interru interrupte pted.
d.
injection Seal injecti on is NOT needeneededd to maint maintain ain seal integr integriity.
ty.
Maximum charg charginging flow to the RCS loops loops via the normnorma all char charg ing path is ging required.
requir ed.
D. NOT been interru interrupte pted.
d.
Seal injec injectition on is NOT need neede edd to maint maintain ain seal integr integrity ity and initiation of cold seal injec injectition on flow will caus cause e RCP damdama age.
ge.
Page 11 Page
TURKEYPOINT TURKEY POINTNRCNRCEXAM EXAM- 05109/07
- 05/09/07 QQ#1
- 1 ANSWER:
ANSWER: AA KA:
KA: 000026AK3.03 000026AK3.03 Knowledge for Knowledge for the the reasons reasons for for the the following following responses responses as as they they apply apply to to the the loss loss of of CCW: Guidance contained in CCW: Guidance contained in EOP EOP for for loss loss of of CCW.
COW. 4.0/4.2 4.0/4.2 IOCFR55:
10CFR55: 41.b.5, 41.b.10 41.b.5, 41.b.10
Reference:
Reference:
3-EOP-E-1, Step 3-EOP-E-1, Step 10 10 RNO RNO SD BD 5610T-L1, 561 Sheet 11 O-T-L 1, Sheet 11 5613-M-3030, Sheet 55 5613-M-3030, Cog Level: 11 Recall New Question Response Analysis:
A. Correct per the references.
B.
S. Incorrect because RCP seal temperatures are already heated up per the basis document. Plausible because CCW COW flow to the thermal barriers has been lost and because maximum charging flow to the RCS loops is required.
C. Incorrect because COW CCW flow to the thermal barriers has been lost. Plausible because maximum charging flow to the RCS ROS loops is required.
D. Incorrect because COW CCW flow to the thermal barriers has been lost. Plausible because initiation initiation of of cold seal injection flow will cause ROP RCP damage.
damage.
Page22 Page
TURKEY TURKE POINT NRC Y POINT NRC EXAM EXAM - 05/0910
- 05/09/077 Q#2 Unit 4 was at 100%
100% powe powerr with all system systems s in normal alignm alignmen entt when the follow following ing events event occurred:
s occur red:
- SIG faulte 4C S/G faulted outside d outsid containm e conta inmenent.
t.
- The reacto reactorr failed to trip automatically atically or manu manuaally.
lly.
- All other other safeguards uards system systemss actuated as requirrequire d.
ed.
Operators Opera tors are perfor perform ing Step 14 of 4-EOP ming 4-EOP-FR-FR-S-S.1,
.1, "Resp Respons onsee to Nucle Nucleaarr Powe Powerr Genera Gene tion/A ration TWS,
/ATW S," which direct directss them to "Verif Verify steam supplsupplyy aligne aligned d to both trains of AFW pump trains pumpss from intact S/G(s SIG(s))."
Which ONE of the followfollowing descr describes ibes the opera operator tor action action(s)
(s) that will ensur ensuree steam is suppli supplied ed to both trains trains of AFW while ensurensuring ing both trains trains remai remain separate?
n separ ate?
AFSS (Note: AFSS 006 and AFSS 006 AFSS 007 are AFW steam suppl 007 supplyy cross conne connectct valves valves.).)
Direct the NSO to locally:
A. AFSS open AFSS 006 only.
006 B. AFSS open AFSS 007 only.
007 C. AFSS close AFSS 007 and then open AFSS 007 AFSS 006..
006 D. AFSS open AFSS 007 and then close AFSS 007 AFSS 006..
006 Page 33
TURKEYPOINT TURKEY PONTNRC NRCEXAM EXAM- 05109/07
- 05/09/07 Q#2 Q#2 ANSWER:
ANSWER: 0D KA:
KA: 000029G2.1.30 000029G2.1.30 AsAs ititrelates relatestotothe theATWS ATWS event:
event: Able Abletoto locate locate and and operate operate components, components, including including local contro ls.
local controls. 3.9/4.0 3.9/4.0 IOCFR55:
10CFR55: 41.b.4, 41.b.7,41.b.10 41.bA, 41.b.7, 41.b.10
Reference:
Reference:
4-EOP-FR-S. 1, Step 4-EOP-FR-S.1, Step 14.d.RNO 1 4.d.RNO 561 4-M-3075, Sheet I 5614-M-3075,Sheet1 Cog Level:
Cog Level: Comprehension 22 Comprehension Level 22 because Level because the the operator operator must must recognize recognize thatthat the the goal goal isis to to restore restore steam steam supply supply from from two two intact intact steam steam generator generator trains trains and and to to maintain train separation maintain train separation and and maintain steam maintain steam supply supply during during the the process.
process. The The correct correct way to achieve achieve this this is to is to locally open locally open AFSS-4-007 AFSS-4-007 and and then close close AFSS-4-006.
AFSS-4-006.
New Question New Question Response Analysis:
Response Analysis:
A.
A. Incorre Incorrect ct because because the RD RO will direct the NSO to open AFSS- AFSS-4-007 and then 4-007 and then close AFSS- 4-006 lAW EOP-F close AFSS-4-006 lAW EOP-FR-S.1, Step 14.d.RR-S.1, 14.d.RNO. Plausible NO. Plausib because le becaus e the the proced procedure ure step step does does not specify the desired positio position of AFSS-n of AFSS-4-006.
4-006. ItIt merely merely directs directs operato operators rs to manip ulate AFSS4 manipulate AFSS-4-006.-006.
B.
B. Incorre Incorrect ct becaus because e the the RD RO will will direct direct the the NSO NSO to to open open AFSS-AFSS-4-007 and then 4-007 and then close AFSS- 4-006 close AFSS-4-006 lAW EDP-F lAW R-S.1, Step EOP-FR-S.1, Step 14.d.R 14.d.RNO. Plausible ND. Plausib because le becaus e itit isis correct correct (but (but not not comple complete)te) to to locally locally open open AFSS-AFSS-4-007.
4-007.
C.
C. Incorre Incorrect ct becaus because e the the RO RO will will direct direct the the NSD NSO to to open open AFSS-AFSS-4-007 and then 4-007 and then close AFSS- 4-006 lAW EDP-F close AFSS-4-006 lAW EOP-FR-S.1, Step R-S.1, Step 14.d.R 14.d.RNO. Plausible NO. Plausib because le becaus e the the proced procedure ure step step does does not not specify specify the the desired desired positio position ofAFSS-n of AFSS-4-006 4-006 or or AFSS- 4-006. ItIt merely AFSS-4-006. merely directs directs operato operators to manipulate AFSS-4-006 rs to manipulate AFSS-4-006 and and AFSS- 4-006.
AFSS-4-006.
D.
D. Correc Correct t per perthethe referen ces. The references. The RD RO will will direct directthe the NSD NSO toto open openAFSS-AFSS-4-007 4-007 and andthenthen close closeAFSS- 4-006 lAW AFSS-4-006 lAW EOP-F EOP-FR-S.1, R-S.1, StepStep 14.d.R 14.d.RNO.
NO.
Page4 4 Page
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09107
- 05/09/07 Q#3 0#3 Unit33 isis atat 100%
Unit 100% power powerwithwith all all systems systems inin normal normal alignment alignmentexcept exceptfor for3A 3A S/G SIG level transmitter, level transmitter, LLT-3-474T-3-474 (red(red channel) channel) which which has hasfailed failed HIGH.
HIGH.
Operators have Operators have tripped tripped associated associated bistables bistables inin accordance accordance withwith 3-0NOP-049.1, 3-ONOP-049.1, Deviation or "Deviation or Failure Failure of of Safety Safety Related Related or or Reactor Reactor Protection Protection Channels."
Channels.
Subsequently, 3A Subsequently, S/G feedwater 3A S/G feedwaterflow flow transmitter, transmitter, FT 477 (blue FT-3-477 (blue channel),
channel), fails fails LOW.
LOW.
Which ONE Which ONE of of the the following following describes describes the the correct correct operator operator response?
response?
A.
A. Perform 3-0NOP-049.1 Perform 3-ONOP-049.1 again again and and trip trip all all bistables bistables associated associated with with FT-3-477.
FT-3-477.
B.
B. Perform 3-0NOP-049.1 Perform 3-ONOP-049.1 again again and and trip trip all all bistables bistables associated associated with with FT-3-477 FT-3-477 except for the except the "FW FW to SF SF Mismatch Mismatch Logic" Logic bistable, BS-3-478B-1.
BS-3-478B-1.
C. Declare Unit 3 is in TS 3.0.3 and immediately initiate a shutdown to Hot Stand by.
Standby.
D. Trip the reactor and transition to 3-EOP-E-0, "Reactor Reactor Trip or Safety Injection Injection" Page5 5 Page
TURKEY POINT TURKEY POINT NRC EXAM - 05/09/07 NRC EXAM - 05/09/07 Q#3 Q#3 ANSWER:
ANSWER: DD KA: 000007EA2.02 KA: 000007EA2.02 Able to Able to determine determine or or interpret interpret following following asas they they apply apply to to reactor reactor trip:
trip: Proper Proper actions actions to be taken ifif the to be taken the automatic automatic safety safety functions functions have have not not taken taken place.
place. 4.3/4.6 4.3/4.6 100FR55:
10CFR55: 41.b.5, 41.b.7, 41.b.5, 41.b.7, 41.b.10 41.b.1O
Reference:
Reference:
561 O-T-L1, Sheet 2 5610-T-L1,Sheet2 5610-T-L1, 5610-T-L Sheet 19 1, Sheet 19 5610-T-D-17 ,
5610-T-D-17, Sheet 11 3-ONOP-049.1, Page~
3-0NOP-049.1, Pages 33 33 && 45 Cog Level: Comprehension 2 Comprehension Level 2 because the operator must recognize that a red (Channel 11)) S/G level transmitter with its bistables tripped includes a low level trip bistable. When the blue channel (Channel 3) feed flow transmitter fails, a steam flow/feed flow mismatch logic is made up that combines with the existing low level signal to generate a reactor trip signal.
New Question Response Analysis:
A. Incorrect because the reactor should have tripped. Operators should transition to EOP-E-O. Plausible, because this is the normal response to aa failure of FT-3-477 FT-3-477 if aa reactor trip signal had not been generated generated .
B.
B. Incorrect Incorrect because the reactor should should have have tripped. Operators Operators should should transition transition toto EOP-E-O.
EOP-E-O. Plausible, Plausible, because because thisthis is is the the response response to to aa failure failure ofof FT-3-477 FT-3-477 following aa failure failure of of LT-3-474 LT-3-474 ifif aa reactor trip trip signal signal had had notnot been been generated.
generated.
C.
C. Incorrect Incorrect because because the the reactor reactor should should have have tripped.
tripped. Operators Operators should should transition transition toto EOP-E-O.
EOP-E-O. Plausible, Plausible, because because the the unit unit would would be be in in TS TS 3.03 3.03 ifif the the reactor reactor hadhad not not tripped.
tripped.
D.
D. Correct Correct perper the the references.
references. The The reactor reactor should should havehave tripped tripped as as aa result result ofof the Low S/G level with the Low S/G level with steam steam flow/feed flow/feed flow flow mismatch mismatch signalsignal generated generated by by the FT-3-477 the FT-3-477 failure.
failure.
Page 66 Page
TURKEYPOINT TURKEY POINTNRC NRC EXAM EXAM- 05/09/07
- 05/09/07 Q#4 0#4 Following aa pressure Following pressure transient transient inin the the RCS, RCS, aa pressurizer pressurizer safety safety valve valve lifted lifted and and subsequently remained subsequently remained open.
open.
- Operators are Operators are performing performing 3-EOP-ES-1.2, 3-EOP-ES-1 .2, "Post Post LOCA LOCA Cooldown Cooldown and and Depressuriza tion.
Depressurization.
required.
pump.
ONE of the following Which ONE following describes the the basis basis for starting the RHR RHR pump pump and and stopping the HHSI pump?
stopping the HHSI pump?
A. Secondary heat sink will be improved by RHR flow collapsing reactor head voids after stopping the HHSI pump.
B. RCS subcooling will be maintained by the running RHR pump even after the HHSI pump is stopped.
C. Subsequent steam generator U-tube cooldown will be enhanced by the addition of RHR flow through the steam generators.
D. SI injection flow rate will increase resulting in earlier restoration of Sl pressurizer level and minimum RCS subcooling.
Page77 Page
TURKEY POINT TURKEY NRC EXAM POINT NRC EXAM - 05/09/07
- 05/09/07 Q#4 Q#4 ANSWER:
ANSWER: B B
KA:
KA: 000008AK3.05 00000SAK3.05 Knowledge for the reasons for the following responses responses as as they apply to the PRZ accident: ECCS vapor space accident: ECCS terminating terminating or or throttling throttling criteria.
criteria. 4.0/4.5 IOCFR55:
10CFR55: 41.b.8, 41.b.10 41.b.5, 41.b.7, 41.b.S,
Reference:
3-EOP-ES-1.2, Step 17 17 BO BD Cog Level: 2 Comprehension Comprehension Level 2 because the operator must analyze plant conditions and apply thermodynamic principles to determine the effect starting and stopping various thermodynamic injection flows has on subcooling and the effect that the HHSI pumps have on maintaining pressure higher and thus subcooling greater.
New Question Response Analysis:
A. Incorrect because the RHR pump is no more effective at collapsing head voids than the previously running HHSI pump and this is not the basis as stated by the reference. Plausible because head voids should be expected for a steam space LOCA and SI pumps do help collapse head voids.
B. Correct per the reference. With T-hot < 350°F, RCS pressure is low enough that an RHR pump can maintain pressure and RCS subcooling will be maintained by the running RHR pump even after the HHSI pump is stopped.
C. Incorrect because the addition of RHR flow will not significantly increase flow though the S/Gs and this is not the reason given by the reference.
Plausible because S/G U-tube cooldown would be enhanced by additional cooling flow.
D.
O. Incorrect because the SI flow rate is not expected to increase and this is not not the basis stated in the reference. Plausible because RHR pumps are basis as stated high flow/low high flOW/low pressure pressure pumps vs the HHSIHHSI pumps which are are low low flow/high pressure pressure pumps.
pumps.
Page 88 Page
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q#5 Q#5 Operators are Operators are responding responding to to aa large large break break LOCA LOCA on on Unit Unit 4.
4.
be reset.
- Operators have Operators have transitioned transitioned to 4-EOP-ES-1 .3, "Transfer to 4-EOP-E8-1.3, Transfer to to Cold Cold Leg Leg Recirculation.
Recirculation". .
- Piggy-back recirc "Piggy-back" alignment is recirc alignment is anticipated.
anticipated.
Which ONE Which ONE ofof the the following following describes describes the the effect effect of of being being unable unable toto reset reset 81?
SI?
A. RWST suction from RW8T RW8T RWST valves, MOV-4-862A and B, cannot cannot be be closed requiring closure of BOTH requiring BOTH RHR RHR PumpPump Inlet Inlet valves, 4-752A AND B. B.
B. RWST suction from RW8T RW8T RWST valves, MOV-4-862A and B, cannot be closed requiring closure of EITHER RHR Pump Inlet valves, 4-752A OR B.
C. RHR discharge to cold leg isolation valves, MOV-4-744A and B, can NOT be closed requiring local closure of BOTH RHR heat exchanger manual outlet valves, 4-759A AND B.
D. RHR discharge to cold leg isolation valves, MOV-4-744A and B, can NOT be closed requiring local closure of EITHER RHR heat exchanger manual outlet valve, 4-759A OR B.
Page 99 Page
TURKEYPOINT TURKEY POfNTNRCNRC EXAM EXAM- 05109/07
- 05/09/07 Q#5 Q#5 ANSWER:
ANSWER: C C
KA:
KA: 0000IIEA2.0 000011 EA2.022 Able to Able to determine determine and and interpret interpret thethe following following as as they they apply apply toto aa LBLOCA:
LBLOCA:
Consequences to Consequences to RHR RHR of of not not resetting resetting SI. 3.3/3.7 SI. 3.3/3.7 10CFR55: 41.b.7 10CFR55: 41.b.7
Reference:
Reference:
4-EOP-ES-1.3, Step 4-EOP-ES-1.3, Step 19 19 RNO RNO 5613-M-3050, Sht.
5613-M-3050, Sht. 1,1, 5610-T-L1, 5610-T-L1, Sht.11, Sht. 11, 5613-E-25, 561 3-E-25, ShtsShts 28F 28F & & 41 41 Cognitive Level:
Cognitive Level: 22 Comprehension Comprehension Level 2 because because the the operator must understand understand integrated plant plant operations, interlocks and interlocks and response response not not obtained obtained actions actions to recognize recognize the effect effect of of not not being being able to reset SI. Once recognized that the 744 valves cannot be closed and that the 862 valves can be closed, the operator must determine the correct response to close both RHR HX outlet valves per EOP-ES-1.3, EOP-ES-1 .3, Step 19.
New Question Response Analysis:
A. Incorrect because once energized (Step 10, EOP-ES-1.3), EOP-ES-1.3), MOV-862 A&B can be closed by placing their control switches in CLOSE (They are powered up and do not have aa continuous OPEN signal from SI Sllike like MOV-744A&B.).
MOV-744A&B.).
Plausible, because these valves must be closed as part of the process of going on cold leg recirculation and if they could not be closed, it would be correct to close both 752A&B.
B. Incorrect because once energized (Step 10, 10, EOP-ES-1 EOP-ES-1.3), .3), MOV-862 A&B can can bebe closed closed by by placing placing their control control switches in in CLOSE CLOSE (They (They are are powered powered up up and and do do not not have have aa continuous continuous OPEN OPEN signal from SI Silike MOV-744A&B.)
like MOV-744A& B.)
and and itit would would be be correct correct to to close close both both 752A&B..
752A&B.. Plausible, Plausible, because because these these valves valves must must be be closed closed as part of as part of the the process process of of going going onon cold cold leg leg recirculation recirculation. .
C.
C. Correct Correct per the references.
per the references. IfIf SI SI cannot cannot be be reset, reset, there there isis aa continuous continuous OPEN OPEN signal signal to to MOV-4-744A MOV-4-744A && B. B. IfIf the the valves valves cannot cannot be be closed, closed, EOP-ES EOP-ES-1.3, 1.3, Step Step 19 19 RNO RNO requires requires closure closure ofof both both RHR RHR heat heat exchanger exchanger outlet outlet valves.
valves.
D.
D. Incorrect Incorrect because because IfIf thethe valves valves cannot cannot be be closed, closed, EOP-ES-1.3, EOP-ES-1.3, Step Step 1919 RNO RNO requires requires closure closure of of both both RHR RHR heat heat exchanger exchanger outletoutlet valves, valves, notnot just just one.
one.
Plausible Plausible because because IfIf SI SI cannot cannot be be reset, reset, there there isis aa continuous continuous OPEN OPEN signal signal to MOV-4-744A to MOV-4-744A && B. B.
Page 10 Page 10
TURKEY POINT TURKEY POINTNRC EXAM- 05/09107 NRC EXAM - 05/09/07 Q#6 Q#6 Unit 33 isis at Unit at 100%
100% power power whenwhen annunciator annunciator 82/5, B 2/5, RCP RCP 8B OILOIL RESERVOIR RESERVOIR HIILO HI/LO LEVEL, alarms.
LEVEL, alarms.
Which ONE Which ONE ofof the the following following describes describes the the correct correct operator operator response?
response?
IfIf the the cause cause isis verified verified to be from to be from a:a:
A.
A. Low reservoir Low reservoir level, level, plot 3B RCP plot 38 RCP motor motor bearing bearing temperatures temperatures every every 15 15 minutes.
minutes.
B.
- 8. Low reservoir Low reservoir level, level, trip trip the the reactor, reactor, stop stop the the 38 3B RCP RCP and and isolate isolate CCW CCW flow flow to the oil coolers within 30 minutes.
minutes.
C. High reservoir level, plot 38 3B RCP motor and shaft vibration every 15 minutes.
D. High reservoir level, trip the reactor, stop the 38 3B RCP and increase CCW flow to the oil coolers within 30 minutes.
Page 11 Page 11
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09107
- 05/09/07 Q#6 Q#6 ANSWER:
ANSWER: AA KA:
KA: 000015/1 7AA1 .02 000015/17AA1.02 Able to Able to operate operate and/or and/or monitor monitor the the following following as as they they apply apply toto the the RCP RCP Malfunctions Malfunctions (Loss of RC flow): RCP Oil Reservoir level and (Loss of RC flow): RCP Oil Reservoir level and alarm alarm indicators.
indicators. 2.8/2.7 2.8/2.7 10CFR55:
10CFR55: 41.b.7 41.b.7
Reference:
Reference:
3-ARP-097.CR, Ann. B2/5 3-ARP-097.CR, B2/5 3-ONOP-041 3-0NOP-041.1, Steps 88 and
.1, Steps and 43 43 Cognitive Level: 11 Recall New Question Response Analysis:
A. 3-ONOP-041 .1, Step 43.
Correct per 3-0NOP-041.1, B. Incorrect because this is the action to be taken if high reservoir level is discovered, not low reservoir level as stated in the response. Plausible because this would be the correct action if the problem was discovered to be high reservoir level.
C. Incorrect because bearing temperatures should be plotted, not vibration.
Plausible because this is the correct frequency of monitoring.
D. Incorrect because this is the incorrect response for high reservoir level. CCW flow should be isolated, not increased Plausible because CCW flow to the oil coolers must be altered within 30 minutes in the event of high reservoir level.
Page 12 Page 12
TURKEY POINT TURKEY POINTNRC NRC EXAM EXAM- 05109/07
- 05/09/07 Q#7 0#7 Unit 33 isis at Unit at 100%
100% power power with with all all systems systems inin normal normal alignment.
alignment. 3A 3A Charging Charging pump pump isis operating.
operating.
3-267, 3A 3-267, 3A Chrg Chrg pump pump suct, suct, isolation isolation valve, valve, experiences experiences aa body-to-bonnet body-to-bonnet leak leak resulting in resulting in aa loss loss of of charging charging flow.
flow.
Which ONE Which ONE of of the the following following describes describes the the correct correct operator operator response response and and the the reason reason for that response?
for that response?
A. Verify allall charging charging pumps pumps are are stopped stopped and and then then close close valve valve 3-268, 3-268, Chrg Chrg Pump Suct Pump Suct Hdr X-Conn valve, Hdr X-Conn valve, because because no no charging charging pumps pumps can can deliver deliver flow flow to the the RCS.
RCS.
B.
- 8. Stop the 3A Charging pump and start the 38 3B Charging pump after closing valve 3-268, Chrg Pump Suct Hdr X-Conn valve, because only 38 3B Charging pump can deliver flow to the RCS.
C. Stop the 3A Charging pump and start 3C Charging pump after closing valve 3-268, Chrg Pump Suct Hdr X-Conn valve, because only the 3C Charging pump can deliver flow to the RCS.
D. Start either of the 38 3B or 3C Charging pump after closing valve 3-268, Chrg Pump Suet Suct Hdr X-Conn valve, because either 38 3B or 3C Charging pump can deliver flow to the RCS.
REFERENC REFERENCE E PROVIDED Page 13 Page 13
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q#7 Q#7 ANSWER:
ANSWER: CC KA:
KA: 000022AK3.07 000022AK3.07 Knowledge for Knowledge for the the reasons reasons forfor the the following following responses responses asas they they apply apply to to the the Loss Loss ofof Reactor Coolant Makeup:
Reactor Coolant Makeup: Isolating Isolating charging.
charging. 3.0/3.2 3.0/3.2 10CFR55:
10CFR55: 41.b.5, 41.b.10 41.b.5, 41.b.10
Reference:
Reference:
3-ONOP-047.1, Step 3-0NOP-047.1, Step 4.14.1 5613-M-3047, Sheet 2 5613-M-3047,Sheet2 NOTE: 5613-M-3047, Sheet 2 AS A REFERENCE PROVIDE 5613-M-3047, REFERENCE Comprehension Cog Level: 2 Comprehension Level 2 because the RO must evaluate the location of the leak and determine that the leak location disables both the 3A and 38 3B Charging pumps. The 3C Charging pump is still viable but valve 3-268 must be closed first.
New Question Response Analysis:
A. Incorrect because 3C Charging pump is still available once valve 3-268 is closed. Plausible because all charging should be stopped and because even if charging could not be recovered, valve 3-268 should be closed to isolate the leak.
B.
- 8. Incorrect because the 3B 38 Charging pump is disabled as well as the 3A Charging pump. Plausible because the 3A Charging pump needs to be stopped and valve 3-268 should be closed.
C. Correct because the 3A Charging pump pump needs needs to be stopped and only the 3C 3C Charging pump pump can deliver deliver flow but only after valve valve 3-268 is closed.
closed.
D.
D. Incorrect Incorrect because the the 3B 38 Charging pump is Charging pump is disabled disabled asas well as as the the 3A 3A Charging Charging pump.
pump. Plausible Plausible because because thethe 3C 3C Charging pump pump can can deliver deliver flow flow but but only only after valve 3-268 after valve 3-268 is is closed.
closed.
Page 14 Page 14
TURKEYPOINT TURKEY POfNTNRC NRCEXAM EXAM- 05/09/07
- 05/09/07 Q#8 Q#8 Unit44 isis inin Mode Unit Mode 44 andand on on RHR RHR cooling.
cooling.
(LOOP) occurs.
occurs.
- The The 4A 4A sequencer sequencerfailsfails to start its to start its components.
components.
Which ONE Which ONE of of the the following following describes describes the the correct correct operator operator response response (if (if any) any) inin accord ance accordance with with 4-0NOP-004, 4-ONOP-004, "Loss Loss of OFF-Site Power",
of OFF-Site Power, regarding regarding restoration restoration of of COW pump CCW pump and and RHR RHR pumppump operation?
operation?
The operator The operator will: will:
A.
A. NOT have NOT have toto start start any any CCW COW or RHR pumps.
or RHR pumps.
B.
B. start one start one RHR RHR pumppump only.
only.
C.
C. start one CCW start COW pumppump only.
only.
D.
D. have to start one CCW and one RHR pump.
have Page1515 Page
TURKEY POINT TURKEY POINT NRC EXAM - 05/09107 NRC EXAM - 05/09/07 Q#8 Q#8 ANSWER:
ANSWER: D D
KA:
KA: 000025AA1.04 000025AA1.04 Able to to operate operate and/or and/or monitor monitor the following following as as they they apply apply toto the the Loss Loss of of RHR RHR System: Closed System: Closed cooling cooling water water pumps.
pumps. 2.8/2.6 2.8/2.6 10CFR55:
10CFR55: 41.b.7 41.b..7
Reference:
Reference:
4-ONOP-004, Steps 7 and 8 4-0NOP-004, 5614-T-L1, 5614-T-L 12A &
1, Sheet 12A & 12B 12B Cog Level: 2 Comprehension Level 2 because the operator must evaluate the effect of the loss of the 4A sequencer on the final CCW and RHR pump configuration and then the operator must recall the CCW and RHR pump requirements of ONOP-004.
New Question Response Analysis:
A. Incorrect because the operator will have to start one CCW pump and start one RHR pump. Plausible because if the sequencer had operated properly, the operator would not have had to start any CCW pumps.
B. Incorrect because the operator will have to start one CCW pump and start one RHR pump. Plausible because if the sequencer had operated properly, the operator would not have had to start any CCW pumps and because the operator will have to start one RHR pump.
C. Incorrect because the operator will have to start one RHR pump. Plausible because the operator wHIwill have to start one CCW pump.
D. Correct because the operator will have to start one CCW pump and start one RHR pump to establish 22 CCW pumps and 11 RHR pump running lAW 4-ONOP-004.
4~ONOP-004.
Page 16 Page 16
TURKEY POINT TURKEY POINTNRCNRC EXAM EXAM - 05/09/07
- 05/09/07 Q#9 0#9 Unit 44 isis initially Unit initially at at 70% power with 70% power with all all systems systems inin automatic automatic except except the the master master pressurizer pressure pressurizer pressure controller, controller, PC-4-444J, PC-4-444J, which which isis in in manual manual due due to to an an instrument instrument failure.
failure.
- 4B Steam 4B Steam Generator Generator Feed Feed pump pump (SGFP)
(SGFP) breaker breaker subsequently subsequently trips.
trips.
Which ONE Which ONE of of the following describes the following describes thethe effect effect of of this this event event on on the the RCS RCS andand the the correct operator correct operator response?response?
RCS temperature RCS temperature wililNITIALL will INITIALLY:
Y:
A. increase.
The RO will drive the PC-4-444J controller output higher to stabilize pressure.
B. increase.
The RO will drive the PC-4-444J controller output lower to stabilize pressure.
C. decrease.
The RO will drive the PC-4-444J controller output higher to stabilize pressure.
D. decrease.
The RO will drive the PC-4-444J controller output lower to stabilize pressure.
Page 17 Page 17
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q#9 Q#9 ANSWER:
ANSWER: A A
KA:
KA: 000027AK1.02 Knowledge of the operational implications Knowledge implications of the following concepts as they apply to the pressurizer pressure control malfunctions: Expansion of liquids as temperature increases. 2.8/3.1 increases. 2.8/3.1 IOCFR55:
10CFR55: 41.b.5, 41.b.7, 41.b.10, 41.b.14
Reference:
Reference:
4-ONOP-041.5, Step 1.a 4-0NOP-041.5, l.a RNO RNO SD-009, Figure 22 Comprehension Cog Level: 2 Comprehension Level 2 because the operator must analyze that with turbine load reduced first, Tavg will initially increase and then be higher than Tref, and pressurizer level will increase raising pressure. The system will need more spray output to maintain programmed pressure. This requires an increase in controller output to open sprays.
New Question Response Analysis:
A. Correct per the references.
B. Incorrect because the RD RO will drive the PC-4-444J controller output higher (toward 100%) to stabilize pressure. Plausible because the resulting turbine runback will initially cause RCS temperature to increase resulting in expansion of reactor coolant into the pressurizer causing RCS pressure to increase.
C. Incorrect because the resulting turbine runback will initially cause RCS temperature to increase resulting in expansion of reactor coolant into the pressurizer causing RCS pressure to increase. Plausible because the RD RO will drive the PC-4-444J controller output higher higher (toward 100%)100%) to stabilize pressure D.
D. Incorrect Incorrect because the resulting turbine runback will initially initially cause RCS RCS temperature to to increase increase resulting inin expansion expansion of of reactor coolant coolant into into the pressurizer the pressurizer causing causing RCS RCS pressure pressure to to increase increase and and thethe RD RO will drive drive the the PC-4-444J controller output higher higher (toward 100%)100%) to stabilize pressure.
pressure.
Plausible Plausible thethe response response isis consistent consistent ifif the the operator operator does does notnot realize realize that that aa turbine runback turbine runback causes the RCS causes the RCS temperature temperature to to increase.
increase.
Page 18 Page 18
TURKEY POINT TURKEY POINT NRC EXAM - 05/09107 NRC EXAM - 05/09/07
- 10 Q #10 Q
Operators are Operators are performing performing 3-EOP-E-3, 3-EOP-E-3, "Steam Steam Generator Generator Tube Tube Rupture."
Rupture.
stopped.
After dumping After dumping steamsteam from from intact intact S/Gs S/Gs to increase subcooling, to increase subcooling, the the RO RD has has been been directed to directed open one to open pressurizer PORV.
one pressurizer PORV.
Which ONE Which ONE of of the following describes the following describes the the effect effect of of opening opening the the PORV PDRV on on pressurizer level, pressurizer level, RCS RCS subcooling and S/G tube break flow break flow rate?
rate?
Pressurizer level Pressurizer level RCS subcooling RCS subcooling SIG break S/G break flow flow A. Decreases Decreases Decreases Increases B. Increases Decreases Decreases C. Increases Increases Increases D. Decreases Increases Decreases Page 19 Page 19
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q#10 Q#10 ANSWER:
ANSWER: BB KA:
KA: 0000 38EK1 .02 000038EK1.02 Knowledge of Knowledge of the operational implications the operational implications of of the the following following concepts concepts as as they apply to they apply to the SGTR:
the SGTR: Leak Leak rate rate vs vs pressure pressure drop.
drop. 3.2/3.5 3.2/3.5 IOCFR55:
10CFR55: 41.b.5, 41.b.10, 41.b.5, 41.b.10, 41.b.14 41.b.14
Reference:
Reference:
3-EOP-E-3, NOTE NOTE prior prior to Step 25, Step 25 3-EOP-E-3, Step 3-EOP-E-3, Step 25 25 BD BD Cog Level: 11 recall New Question Response Analysis:
A. Incorrect because pressurizer level will increase, not decrease and break flow will decrease, not increase. Plausible because subcooling will decrease.
B. Correct per the references.
C. Incorrect because subcooling will decrease, not increase and break flow will decrease, not increase. Plausible because pressurizer level will increase.
D. Incorrect because pressurizer level will increase, not decrease and subcooling will decrease, not increase. Plausible because break flow will decrease Page 20 Page 20
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05109/07
- 05/09/07
- 11 QQ#11 Unit44isisatat50%
Unit 50%powerpowerwhenwhenaalarge largemain mainsteam steamline linebreak breakoutside outsidecontainment containment downs tream (turbin downstream (turbineeside) side)ofofthe the4B4BMSIV MSIVandand non-return non-returncheck checkvalve valveoccurs.
occurs.
Which ONE Which ONEof ofthe thefollowing following describes describesthe theresponse responseof ofthe the Unit Unit44 MSIVs MSIVs andand the the reason reason forforthat that response?
response?
A.
A. 4B MSIV 4B MSIVwill will automatically automatically closeclose due due toto high high steam steam flow flow o!l on the the 4B 4B S/G SIG with low 4B SIG with low 4B S/G pressure.pressu re.
4A and 4A and 4C 40 MSIVs MSIVs will will automatically automatically close close duedue to to high high differential differential pressure pressure betwee n each SIG and between each S/G and the main steamthe main steam header.
B.
B. 4B MSIV 4B MSIV willwill automatically automatically close close due due toto high high differential differential pressure pressure between between 4B SIG and 4B S/G and the mainthe main steam steam header.
4A and 4A and 4C4C MSIVs MSIVs will will automatically automatically close close due due to to high high steam steam flow flow on on the the 4A 4A and 4C SIGs with and 4C S/Gs with low Tavg. low Tavg.
C.
C. All of All of the the Unit Unit 44 MSIVs MSIVs willwill automatically automatically close close duedue toto high high steam steam flow with with low Tavg low Tavg OR OR lowlow SG SG pressure pressure sensed sensed on on all all S/Gs.
S/Gs.
D.
D. All of All of the the Unit Unit 4 MSIVs will automatically automatically close due to high differential differential pressu re betwee pressure between n each SIG S/G and the main steam header. header.
Page2121 Page
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05109/07 05/09/07 QQ#11
- 11 ANSWER:
ANSWER: CC KA:
KA: 000040AK2.O1 000040AK2.01 Knowledge of Knowledge ofthe the interrelations interrelations between between the the steam steam line line rupture rupture andand the the following:
following:
Valves . 2.6/2.5 Valves. 2.6/2.5 100FR55:
10CFR55: 41.b.4, 41.b.7, 41.bA, 41.b.7, 41.b.B 41.b.8
Reference:
Reference:
5610-T-L1, 5610-T-L Sheet 11 1, Sheet 11 5610-T 561 O-T-L -L1, Sheet 19 1, Sheet 19 5614-M -3072, 5614-M-3072,Sheet11 Sheet Cog Level:
Cog Level: 22 Comprehension Comprehension Level 22 because Level because the the operator operator must must recognize recognize that that the the location location of of the the break break determ ines determines the respon response se of the MSIV5. Because MSIVs. Because the break break is is downstream downstream of of the the MSIV/non-return check valve, itit does not matter MSIV/non-return matter that it is is located on the 4B header.
4B header.
All S/Gs All S/Cs will will feed the break and all MSIVs will close.
New Question New Question Response Analysis:
Response Analysis:
A.
A. Incorre Incorrect ct becaus because e 4A and 4C MSIVs will autom automatically atically close due to high high steam steam flow with low Tavg OR low SG pressu pressurere sensed on all S/Cs. S/Gs.
Plausib Plausible le becaus because e 4B4B MSIV MSIV will autom atically close due automatically due toto high high steam steam flow flow on the 4B on the 4B S/G S/C with low low 4B 4B S/C S/G pressu pressure.re.
B.
B. Incorre Incorrect ct becaus because e 4B 4B MSIV MSIV will will autom automatically close due atically close due toto high high steam steam flow flow with with low low Tavg Tavg OR OR low low SGSG pressu pressure re sensed sensed on on allall S/Cs.
S/Gs. Plausib Plausible because le because 4A 4A and and 4C 4C MSIVs MSIVs willwill automa tically close automatically close due due toto high high steam steam flow flow onon the the 4A4A and and 4C4C S/CsS/Gs with with low low Tavg.
Tavg.
C.
C. Correc Correct t per per the the referen ces. All references. All of ofthe the Unit Unit 44 MSIVs MSIVs will will automa automatically close tically close due due toto high high steam steam flow flow with with low low Tavg Tavg OR OR low low SCSG pressu pressure sensed on re sensed on all all S/Cs.
S/Gs.
D.
D. Incorre Incorrect ct becaus because e high high steam steam lineline // S/C S/G pressu pressure differential re differe does not ntial does not close close MSIV5 MSIVs. . Plausib Plausiblele becaus because e all all of ofthe the MSIV5 MSIVswillwill automa automatically close tically close Page2222 Page
TURKEY POINT TURKEY POINT NRC EXAM - 05/09107 NRC EXAM - 05/09/07 Q#12 Q#12 With Unit With Unit 33 critical critical at 1O88 amps at 10- amps IIR R power, power, 3A 3A main main feedwater feedwater header header sheared sheared immediately outside immediately outside Unit Unit 33 containment.
containment.
Which ONE Which ONE of of the the following following describes describes the the effect effect on Unit 3?
on Unit 3?
low pressurizer A low pressurizer pressure pressure reactor reactor trip signal signal will:
A. trip the reactor.
SI will NOT actuate.
B.
B. trip the reactor.
SI will actuate.
c.
C. NOT trip the reactor.
SI will NOT actuate.
D. NOT trip the reactor.
SI will actuate.
Page 23 Page 23
TURKEY POINT TURKEY POINT NRC EXAM - 05/09/07 NRC EXAM - 05/09/07 Q #12 Q #12 ANSWER:
ANSWER: DD KA:
KA: 000054AK1.O1 000054AK1.01 Knowledge of Knowledge of the operational implications the operational implications of the following of the following concepts concepts as as they they apply apply toto the Loss the Loss of of Main Main FW:
FW: MFW MEW lineline break break depressurizes depressurizes the the S/G S/G (similar (similar to to aa steam steam line break) line break) 4.1/4.3 4.1/4.3 100ER55:
10CFR55: 41.b.4, 41.b.7, 41.b.8
Reference:
Reference:
5610-T-L1, Sheet 5610-T-L1, Sheet 11 11 5610-T-L1, 5610-T-L 1, Sheet 19 19 5613-M-3074, Sheet 3 5613-M-3074,Sheet3 Comprehension Cog Level: 2 Comprehension Level 2 because the operator must recognize that a feedwater header break at that location will depressurize the 3A S/G and the depressurizationdepressurization will be sensed on the 3A steam header which will result in the High steamline LlP AP logic (1/3 S/Gs) being initiated which is not blocked at low power levels. Additionally the operator must recognize that low pressurizer pressure reactor trip is an "At-Power" At-Power trip which is blocked at 10-1088 amps.
New Question Response Analysis:
A. Incorrect because a low pressurizer pressure reactor trip signal will not trip the reactor and SI will actuate. Plausible because if the unit was at normal power level, level, aa low pressurizer pressure reactor trip signal would trip the reactor based on these conditions.
B.
B. Incorrect because aa low low pressurizer pressurizer pressure pressure reactor trip signal will not not trip trip the reactor. Plausible Plausible because because SI SI will actuate andand ifif the unit unit was atat normal normal power power level, level, aa low low pressurizer pressure pressure reactor trip signal would trip trip the reactor reactor based based onon these these conditions.
conditions.
C.
C. Incorrect Incorrect because because SI will actuate.
SI will actuate. Plausible Plausible because because aa low low pressurizer pressure pressure reactor trip signal reactor trip signal will will not trip the not trip the reactor reactor atat this this power power level.
level.
D.
D. Correct Correct per the references.
per the references. A A low low pressurizer pressurizer pressure pressure reactor reactor trip trip signal signal will will not not trip the reactor trip the reactor and and SISI will will actuate.
actuate.
Page 24 Page 24
TURKEY POINT TURKEY PONT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q#13 Q#13 Operators are Operators are performing performing 4-EOP-ECA-0.0, 4-EOP-ECA-0.0, "LossLoss of of All All AC AC Power" Power and and are are in in the the process of process of depressurizing depressurizing all all intact intact S/Gs S/Gs to to 180 180 psig.
psig.
What is the consequence ifif the SG depressurization depressurization is NOT NOT stopped until until 70 psig?
psig?
A. reactor vessel head A reactor head void void will become become large large enough enough to partially partially uncover uncover the core.
B. RED path on the Integrity status tree will occur resulting in a challenge to A RED the reactor vessel pressure boundary.
C. A RED path on the Heat Sink status tree will occur resulting in a loss of subcooling.
D. SIG U-tubes potentially disrupting natural circulation.
Nitrogen will enter the S/G Page 25 Page 25
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05109107
- 05/09/07
- 13 Q #13 Q
ANSWER:
ANSWER: 0D KA:
KA: 000055 EKI .02 000055EK1.02 Knowledge of the operational implications Knowledge implications of the following concepts concepts as as they apply to the station blackout: Natural Circulation Cooling. 4.1/4.4 IOCFR55:
10CFR55: 41.b.3, 41.b.4, 41.b.7
Reference:
3-EOP-ECA-0.0 SO, BD, CAUTION before Step 26 Cog Level: 1I Recall New Question Response Analysis:
A. Incorrect because there is too little nitrogen to be released to cause core uncovery and a head void may occur but will not uncover the core and this is not the reason given by the reference. Plausible because nitrogen is expected to accumulate in the reactor vessel head and the rapid depressurization will cause a head void.
depressurization B.
S. Incorrect because a red path on Integrity will not occur if the operators stop depressurization at 70 psig. Saturation temperature for 70 psig (85 psia) the depressurization is approximately 316°F. Plausible because the cooldown will be enough to result in an orange path on Integrity.
C. Incorrect because a red path on Heat sink will not occur because operators are not permitted to continue the depressurization depressurization if all S/G SIG levels drop below 6% and this depressurizat ion is not expected to impair the ability of the AFW depressurization pumps to supply adequate AFW flow. Plausible because if aa loss of heat sink event did occur, aa loss of subcooling would ultimately result.
D.
O. Correct per the references. Nitrogen will enter the S/G U-tubes disrupting natural circulation.
Page 26 Page 26
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q#14 0#14 CVCS auto-makeup CVCS auto-makeup is is occurring occurring on on Unit Unit 33 when when the the following foflowing events events occur:
occur:
- Unit 3 reactor Unit reactor automatically automatically trips.
trips.
out.
- Auto-makeup Auto-makeup stopsstops asas aa result result FCV-3-113B FCV-3-1 1 3B closure.
closure.
- Unit Unit 3 annunciators go dark.
Which ONE of the following identifies the procedure operators will implement after 3-EOP-ES-O.1, "Reactor the unit is stabilized using 3-EOP-ES-0.1, Reactor Trip Response"?
Response?
A. 3-ONOP-005.4, "4KV 3-0NOP-005.4, 4KV Bus 3A, 3B or 3D Ground"Ground B. 3-ONOP-003.9, "Loss 3-0NOP-003.9, Loss of 120 VAC Vital Instrument Pane13P09" Panel 3P09 C. 3-ONOP-003.5, "Loss 3-0NOP-003.5, Loss of DC Buses 3D23 and 3D23A (3B)
D. 3-ONOP-003.4, "Loss 3-0NOP-003.4, Loss of DC Bus 3D01 and 3D01A 3DO1A (3A)
Page 27 Page 27
TURKEY POINT TURKEY POINTNRC EXAM- 05/09/07 NRC EXAM - 05/09/07 Q#14 Q#14 ANSWER:
ANSWER: 0D KA:
KA: 000058G2.4.4 000058G2.4.4 As it relates to As it relates to the the loss loss of of DC DC power power event:
event: Able Able to to recognize recognize abnormal abnormal indications indications for system for system operating operating parameters parameters which which are are entry entry level level conditions conditions for emergency for emergency and abnormal and abnormal operating operating procedures.
procedures. 4.0/4.3 4.0/4.3 10CFR55:
10CFR55: 41.b.7, 41.b.10 41.b.7,41.b.10
Reference:
Reference:
3-ONOP-003.4, Step 3-0NOP-003.4, Step 1.1 1.1 &
& 2.1, 2.1, 2.2 2.2 && 3.5 3.5 Cog Level:
Cog Level: 11 Recall Recall New Question Response Analysis:
A. Incorrect because operators are directed to enter ONOP-003.4 immediately following EOP-ES-0.1. Plausible because a reactor trip, MSIV closure, loss of AFW white light or loss of annunciators could be related to various grounds.
B. Incorrect because operators are directed to enter ONOP-003.4 immediately following EOP-ES-0.1. Plausible because the first step of QNOP-003.9 ONOP-003.9 procedure checks for aa reactor trip and analyzes if one is needed and loss of 3P09 previously required a reactor trip.
C. Incorrect Incorrect because all of the symptoms listed are indicative of aa loss of 3D01, 3001, not 3D23.
3023. Plausible because the reactor will automatically trip and MSIVs will automatically close close upon upon aa loss of 3D23 loss of 3023 D.
O. Correct Correct per the references per the references Page28 Page 28
TURKEYPOINT TURKEY POINT NRC EXAM - 05/09107 NRC EXAM - 05/09/07 Q #15 Q #15 Operators are Operators are responding responding to to aa line line break break in in the the Instrument Instrument AirAir (IA)
(IA) system.
system.
(VPA) is is 91 91 psig psig and and lowering.
lowering.
- All available All available IAIA compressors compressors are are running running andand crossties crossties are are open.
open.
The NSO The NSO is sent to is sent investigate and to investigate and reports reports the the following following 10caiiA local IA pressure pressure indications:
indications:
P1-3-1516, Turbine PI-3-1516, Turbine Area:
Area: 91 91 psig psig and and lowering lowering P1-3-1517, Containment PI-3-1517, Containment Area: 80 80 psig psig and and lowering lowering P1-3-I 518, Aux Bldg, Intake Area, Control PI-3-1518, Control Room: 92 psig and lowering Which ONE of the following describes the correct operator response?
A. Isolate IA to the Containment.
Containment. Trip the reactor and perform 3-EOP-E-O, 3-EOP-E-0, Reactor Trip or Safety Injection."
"Reactor Injection.
B. Containment. If IA pressure stabilizes above 65 pSig, Isolate IA to the Containment. psig, then maintain reactor power stable until IA system repairs are complete.
C. Containment. Trip the reactor and perform Do NOT isolate IA to the Containment.
3-EOP-E-0, "Reactor 3-EOP-E-O, Reactor Trip or Safety Injection".
Injection.
D. Do NOT isolate IA to the Containment.
Containment. If IA pressure continues to decrease, then trip the reactor and perform 3-EOP-E-0, "Reactor Reactor Trip or Safety Injection.
Injection".
Page 29 Page 29
TURKEYPOINT TURKEY POINTNRC EXAM- 05/09/07 NRC EXAM 05/09/07
- 15 QQ #15 ANSWER:
ANSWER: AA KA:
KA: 000065G2.1.23 000065G2.1.23 As itit relates As relates to to the the loss loss of of instrument instrument air air event:
event: Able Able to to perform perform specific specific system system andand integrated plant integrated plant procedures procedures during during all all modes modes of of plant plant operation. 3.9/4.0 operation. 3.9/4.0 10CFR55:
10CFR55: 41.b.4, 41.b.10, 41.bA, 41.b.10, 45.2 45.2
Reference:
Reference:
0-ONOP-013:
0-ONOP-013: CAUTION before CAUTION before Step Step 16, 16, NOTE before NOTE before Step Step 16, 16, Step 1717 RNO, RNO, FO Page FO Page Unit Unit Trip Trip Criteria Criteria Cog Level: 2 Comprehension Comprehension Level 2 because the operator must compare the indicated containment IA pressure to IA system pressure and calculate the difference to determine if the pressure drop exceeds 10 psig and then apply procedure actions as required.
New Question Response Analysis:
A. Correct per the references.
B. Incorrect because the reactor must be tripped when IA is isolated to containment regardless of subsequent air pressure. Plausible because the reactor normally does not have to be tripped if IA pressure stabilizes above 65 65 psig.
psig.
C.
C. Incorrect Incorrect because because IA IA must be isolated must be isolated to to containment containment whenwhen its its pressure pressure drop drop exceeds 10 exceeds 10 psi. psi. Plausible Plausible because because thethe reactor must must be be tripped under under these these conditions.
conditions.
D.
D. Incorrect Incorrect because because IA IA must be isolated must be isolated to to containment containment whenwhen its its pressure pressure drop drop exceeds 10 psi. Plausible because exceeds 10 psi. Plausible because the the reactor reactor must must be be tripped tripped under under these these conditions.
conditions.
Page 30 Page 30
TURKEY POINT TURKEY POINTNRC NRC EXAM EXAM - 05/09107
- 05/09/07 Q #16 Q #16 Unit 33 operators Unit operators are performing 3-EOP-ECA-1.2, are performing 3-EOP-ECA-1.2, "LOCALOCA Outside Outside Containment".
Containment.
increasing.
Which ONE Which ONE ofof the the following following describes describes the the correct correct operator operator response response and and the the reason reason for the response?
for the response?
Transition to:
A. 3-EOP-ECA-1 .1, "Loss 3-EOP-ECA-1.1, Loss of Emergency Coolant of Emergency Coolant Recirculation" Recirculation as as the the steps steps in in ECA-1 .2 have been successful.
ECA-1.2 successful.
B.
B. Loss of Reactor or Secondary Coolant" 3-EOP-E-1, "Loss Coolant as the steps in ECA-1.2 ECA-1 .2 have NOT been successful.
C. 3-EOP-ECA-1 .1, "Loss 3-EOP-ECA-1.1, Loss of Emergency Coolant Recirculation" Recirculation as the steps in ECA-1 ECA-1.2 .2 have NOT been successful.
D. 3-EOP-E-1, "Loss Loss of Reactor or Secondary Coolant" Coolant as the steps in ECA-1.2 ECA-1 .2 have been successful.
Page 31 Page 31
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07 05/09/07 Q#16 Q#16 ANSWER:
ANSWER: DD KA:
KA: W/EO4EA2.1 W/E04EA2.1 interpret the following as they apply to the LOCA Able to determine and interpret LOCA OC:
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
emergency operations. 3.4/4.3 IOCFR55:
10CFR55: 41.b.5, 41.b.1O 41.b.5,41.b.10
Reference:
3-EOP-ECA-1 .2:
3-EOP-ECA-1.2: Step 3.b Cog Level: 1I Recall New Question Response Analysis:
A. Incorrect because the correct transition is to go to EOP-E-1 EOP-El if pressure is increasing. Plausible because RCS pressure increasing is an indication that EOPECA-1 .2 have been successful and ECA-1.1 the steps in EOP-ECA-1.2 ECA-1 .1 is the correct procedure to transition to in that instance.
B. Incorrect because RCS pressure increasing is an indication that the steps in EOP-ECA-1 .2 have been successful. Plausible because the correct EOP-ECA-1.2 transition is to EOP-E-1.
C. Incorrect because the correct transition is to go to EOP-E-1 EOP-E-l if pressure is increasing and because RCS pressure increasing is an indication that the EOP-ECA-I .2 have been successful. Plausible because EOP-ECA-steps in EOP-ECA-1.2 EOP-ECA 1.1 is one of only two procedures to exit to from ECA-l ECA-1.2.2 and it is the correct transition if efforts have not been successful as stated in the response.
D. Correct per the references. The correct transition is to EOP-E-I EOP-E-1 and RCS pressure increasing is an indication that the steps in EOP-ECA-I EOP-ECA-1.2 .2 have been successful.
Page 32 Page 32
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q#17 Q#17 Upon entry Upon into 4-EOP-ECA-1.1, entry into 4-EOP-ECA-1 .1, "Loss Loss of Emergency Coolant of Emergency Coolant Recirculation",
Recirculation, the the RO reports RO reports Unit Unit 44 RWST RWST levellevel has has decreased decreased to to 59,000 59,000 gallons.
gallons.
Which ONE Which ONE of of the following describes the following describes the the correct correct operator operator response?
response?
A.
A. Depressurize all Depressurize all intact intact S/Gs S/Gs to to atmospheric atmospheric pressure pressure atat aa rate rate NOT NOT to to exceed an exceed an RCS RCS cooldown cooldown raterate of of 100°F/hour 100°F/hour to to ensure ensure the the Unit Unit 44 Accumulators fully Accumulators fully inject.
inject.
B.
B. Stop the running Stop running UnitUnit 44 HHSI, HHSI, RHR RHR and and CS CS pumps.
pumps.
and start Align and start one Unit Unit 33 HHSI HHSI pump deliver flow from Unit pump to deliver Unit 33 RWST.
RWST.
C. Stop the running Unit 4 RHR and CS pumps.
Continue to run one Unit 4 HHSI pump for as long as it will deliver flow from the Unit 4 RWST.
D. Establish minimum charging to deliver flow from Unit 4 RWST.
When minimum charging flow has been established, stop the running HHSI RHR and CS pumps.
Page 33 Page 33
TURKEY POINT TURKEY POiNT NRC EXAM - 05/09107 NRC EXAM 05/09/07 Q #17 Q#17 ANSWER:
ANSWER: BB KA:
KA: WIEI1EK2.2 W/E11EK2.2 Knowledge Knowledge of theof the interrelations interrelations between between thethe loss loss of of emergency emergency coolant coolant recirc recirc and and the following:
the following: facility's facilitys heat heat removal removal systems systems incl mci primary primary coolant, coolant, emergency emergency coolant, the coolant, the decay heat removal decay heat removal systems, systems, andand relations relations between between the the proper proper operation of operation of these these systems systems toto the the operation operation of the facility.
of the facility. 3.9/4.3 3.9/4.3 IOCFR55:
10CFR55: 41.b.7, 41.b.10
Reference:
Reference:
4-EOP-ECA-1.1:
4-EOP-ECA-1.1: Steps 11 RNO, Steps RNO, 30, 31,32 30,31,32 Cog Level: Comprehension 2 Comprehension Level 2 because the operator must link the knowledge that RWST level <<60,000 60,000 gallons requires stopping the safety pumps. The 60,000 criteria is provided in Step 11 of the procedure and stopping the pumps is in Step 31. Additionally the operator must realize that stopping the safety pumps stops safety injection flow to the core and an alternate method of core cooling (opposite unit HHSI flow) is immediately required.
New Question Response Analysis:
A. Incorrect because the correct response is to stop all safety pumps pulling from that RWST and align the opposite units unit's HHSI pump. Plausible because depressurizin depressurizing g S/Gs is aa subsequent procedure step but if done it will be performed at the maximum rate.
B. Correct per the references C. Incorrect because all all safety pumps are stopped, including HHSI HHSI pumps.
pumps.
Plausible because the RHR and CS pumps are stopped and continuing to run HHSI HHSI pumps would continue to provide provide core cooling flow.
D.
D. Incorrect Incorrect because the the safety safety pumps pumps need need to be stopped to be stopped now.
now. Plausible because because the the charging pumps pumps are are probably probably already running (but (but at at maximum maximum speed) and will be allowed speed) and will be allowed to runto run until until RWST RWST levellevel drops drops toto 20,000 20,000 gallons.
gallons.
Page 34 Page 34
TURKEYPOINT TURKEY POINTNRCNRC EXAM EXAM- 05/09107
- 05/09/07
- 18 QQ #18 Unit 33 operators Unit operators are are performing performing 3-EOP-FR-H.1, 3-EOP-FR-H.1, "Response Response to to Loss Loss of of Secondary Secondary Heat Sink."
Heat Sink.
The BOP The BOP isis attempting attempting toto restore restore AFW AFW flow flow when when the the RO RD reports reports the the following following S/G SJG levels:
levels:
- 3A SIG:
3A S/G: 35% Wide 35% Wide Range Range and and lowering lowering
- 3B SIG:
3B S/G: 25% Narrow 25% Narrow Range Range and and lowering lowering
- 3C SIG:
3C S/G: 30% Narrow 30% Narrow Range Range and and lowering lowering The BOP The BOP isis unable unable to immediately restore to immediately restore secondary secondary heat heat sink.
sink.
The STA The STA reports reports containment containment temperature temperature hashas increased increased toto 190°F.
190°F.
Which ONE of the following describes the correct operator response? response?
A. Maintain RCPs running. Continue to perform procedure steps to restore AFW flow.
AFWflow.
B. Maintain RCPs running. Continue to perform procedure steps to restore Main Feedwater flow.
C. RCP5. Do NOT initiate bleed and feed at this time. Continue to perform Stop RCPs.
procedure steps to restore secondary heat sink.
D. Stop RCPs. Immediately initiate bleed and feed.
Page35 Page 35
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07 05/09/07 Q#18 Q#18 ANSWER:
ANSWER: 0D KA:
KA: W/EO5EK1 .2 W/E05EK1.2 Knowledge Knowledge of of the the operational operational implications implications of of the the following following concepts concepts asas they they apply apply to to the Loss of the Loss of secondary secondary heat heat sink:
sink: Normal, Normal, abnormal abnormal andand emergency operating emergency operating procedures associated procedures associated with with the the loss loss of of secondary secondary heat heat sink.
sink. 3.9/4.5 3.9/4.5 10CFR55:
10CFR55: 41.b.4, 41.b.8, 41.bA, 41.b.8, 41.b.1 41.b.10 0
Reference:
Reference:
3-EOP-FR-H.1:
3-EOP-FR-H.1: CAUTION priorprior to Step 2, 2, Step 12 12 Level: 2 Comprehension Cog Level: Comprehension Level 2 because the operator must evaluate the S/G levels provided based on adverse containment conditions (>180°F). The operator must also recognize that 35% WR S/G level is < 32% NR level and bleed and feed criteria are met.
New Question Response Analysis:
A. Incorrect because RCPs need to be tripped immediately.
immediately. Plausible because operators will continue efforts to restore AFW flow.
B. RCP5 need to be tripped immediately.
Incorrect because RCPs immediately. Plausible because operators will continue efforts to restore main feedwater flow.
C. Incorrect because bleed and feed needs to be established immediately immediately..
Plausible because RCPs need need to be stopped.
D. Correct per the references. RCPs need need to be stopped and bleed and feed needs be immediately needs to be immediately initiated.
initiated.
Page 36 Page 36
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05109107
- 05/09/07
- 19 Q #19 Q
Unit is inin Mode Unit 33 is Mode 66 when when the the RO RD isis notified notified that that aa spent spent fuel fuel element element has has dropped dropped onto the onto Region IIII fuel the Region fuel racks.
racks.
Which ONE Which ONE of of the the following following identifies identifies control control room room indications indications that can be that can be used used toto determine if the fuel element cladding determine if the fuel element cladding has been has been breached?
breached?
A.
A. CVCS Letdown Process Process Radiation Radiation monitor, R-3-20, R-3-20, alarms B.
B. Spent Fuel Spent Fuel Pit Pit North North Wall Area Radiation Radiation monitor, monitor, RI-3-1421 Rl-3-1421B,B, alarms alarms C. Plant Vent Process Radiation monitor, R-14, alarms D.
D.' Plant Vent SPING monitor, RAD-6304, alarms Page 37 Page 37
TURKEY POINT TURKEY POINT NRC EXAM - 05/09/07 NRC EXAM - 05/09/07 Q#19 Q#19 ANSWER:
ANSWER: BB KA:
KA: 000036AA2.O1 000036AA2.01 Able to Able to determine determine andand interpret interpret the the following following as as they they apply apply toto the the fuel fuel handling handling incidents: ARM incidents: ARM system system indications.
indications. 3.2/3.9 3.2/3.9 IOCFR55:
10CFR55: 41.b.1O, 41.b.11 41.b.10, 41.b.11
Reference:
Reference:
4-ONOP-033.3:
4-0NOP-033.3: 2.2 Section 2.2 Cog Level:
Cog Level: Recall 11 Recall New Question Response Analysis:
A. Incorrect because the letdown monitor alarming is not identified as an indication of a dropped rod and this dropped rod is in the SFP, not the containment. Plausible because there is an indirect path from the SFP SEP to the letdown monitor (through the keyway, transfer canal and RHR system)
B. Correct per the reference. Unit 3 Spent Fuel Euel Pit North Wall Area Radiation monitor, RI-3-1421 Rl-3-1421B,B, alarms.
C. Incorrect because the event did not occur on Unit 4. Plausible because PRMS-R-1 4 would alarm if the event had happened on Unit 4.
PRMS-R-14 D. Incorrect because the event did not occur on Unit 4. Plausible because RAD-6304 would alarm if the event had happened on Unit 4.
Page 38 Page 38
TURKEY POIISTTNRC TURKEYPOINT NRC EXAM EXAM- 05/09/07
- 05/09/07 Q#20 0#20 Unit 44 isis at Unit at 100%
100% power power with with all all systems systems inin normal normal operation operation when when aa tube tube leak leak occurs inin the occurs the 4A 4A S/G.
SIG.
The tube The tube leak leak increases increases toto 250 250 gpm over aa period gpm over period ofof 55 minutes.
minutes.
Which ONE Which ONE of the following of the following describes describes thethe effect effect on on charging charging and and letdown letdown flow flow rates rates as the leak as the leak starts starts (before (before operator operator response) response) andand IMMEDIATELY AFTER IMMEDIATELY AFTER operators operators have performed have performed the prompt actions the prompt actions of 4-EOP-E-0, "Reactor of 4-EOP-E-0, Reactor Trip Trip or or Safety Safety Injection?
Injection"?
Early in Early in S/G Tube LeakLeak Event Event After Prompt Prompt Actions Actions Complete Complete Chqinq Flow Chging Ltdwn Flow Flow Chging Chqinq Flow Flow Ltdwn Flow A.
A. Increasing Unchanged Zero Unchanged B. Increasing Decreasing Maximum Zero C. Increasing Unchanged Zero Zero D. Increasing Unchanged Maximum Unchanged Page 39 Page 39
TURKEY POINT TURKEY POINT NRCNRC EXAM EXAM - 05/09107
- 05/09/07 Q #20 Q#20 ANSWER: C ANSWER: C KA:
KA: 000037AK3.
000037 AK3.0303 Knowledge for the reasons Knowledge for the reasons for for the the following following responses responses as as they they apply apply to to the the SGTL:
SGTL:
comparison of comparison of makeup makeup flow flow and and letdown letdown flowflow for for various various modes modes ofof operation.
operation.
3.1/3.3 3.1/3.3 IOCFR55: 41.b.7 10CFR55: 41.b.7
Reference:
Reference:
4-ONOP-071.2, FO 4-0NOP-071.2, EQ Page Page Item Item 1.b, 1.b, 5610-T-L1, 5610-T-L1, Sheet32A Sheet 32A SD-009, Page SO-009, Page 37, 37, SO-013, SD-013, PagePage 18 18 Cog Level:
Cog Level: 22 Comprehension Comprehension Level 2 because the operator must evaluate the size of the SGTL. Before SI actuation, Charging pump speed will increase in response to lowering pressurizer level and letdown flow rate will be constant. SI actuation will result in Phase A actuation which will isolate letdown. Charging pumps will be tripped directly by the SI actuation.
New Question Response Analysis:
A. Incorrect because letdown will isolate following SI actuation as a result of Phase A isolation. Plausible because letdown flow and charging flow will be unchanged initially and charging flow will go to zero after SI actuation.
B. Incorrect because letdown flow will initially be unaffected and charging flow will go to zero after SI actuation. Plausible because charging flow will be unchanged initially and charging pump speed will increase before operators respond and letdown flow will isolate following Phase A actuation.
C. Correct because charging pump speed will increase before operators respond and and charging pumps will trip when SI actuates. Letdown flow will initially be unaffected unaffected and and letdown letdown flow will isolate following Phase A actuation.
D.
O. Incorrect Incorrect because because charging flow flow will gogo to to zero zero after after SI SI actuation actuation and and letdown letdown will isolate isolate following SI SI actuation actuation as as aa result ofof Phase Phase A A isolation.
isolation. Plausible because because Letdown Letdown flow flow will will initially initially be be unaffected unaffected andand because because charging charging pump pump speed speed willwill increase increase before before operators operators respond.
respond.
Page 40 Page 40
TURKEYPOINT TURKEY POiNTNRCNRCEXAM EXAM- 05109107
- 05/09/07
- 21 QQ #21 Operators are Operators are performing performing 3-0NOP-1 3-ONOP-100 00,, "Fast Fast Load Load Reduction" Reduction inin response response toto rapidlydropping rapidly dropping condenser condenservacuum.vacuum.
Unable to
- Unable to recover recover vacuum, vacuum, operators operators trip trip the the unit unit and and enter enter the the EOPs.
EOPs.
- C 8/3, STEAM
- C 8/3, STEAM DUMP ARMED DUMP ARMED /I ACTUATED, ACTUATED, alarmed.alarmed.
- Tavg Tavg initially initially dropped dropped to to 543°F.
543°F.
- Two minutes after the
- Two minutes after the unit trip unit trip Tavg Tavg stabilizes stabilizes atat 545°F.
545°F.
Annunciator CC 8/3
- Annunciator 8/3 has has cleared.
cleared.
Which ONE Which ONE ofof the the following following describes describes thethe reason reason whywhy annunciator annunciator C C 8/3 8/3 isis clear clear AND the AND the status status of the Steam of the Steam DumpDump to to Condenser Condenser (SDTC)(SDTC) System?
System?
The SDTC The SDTC arming arming signal signal is is clear clear because:
because:
A.
A. vacuum dropped vacuum dropped below below 20".
20.
The SDTC SDTC System System is is disabled.
B.
B. vacuum dropped below 20". 20.
The SDTC System remains fully functional.
C.
C. Tavg dropped to 543°F.
The SDTC System is disabled.
D.
D. Tavg dropped to 543°F The SDTC System remains fully functional.
Page4141 Page
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09/07
- 05/09/07
- 21 QQ #21 ANSWER:
ANSWER: AA KA:
KA: 000051AK3.01 000051AK3.01 Knowledge for Knowledge for the the reasons reasons for for the the following following responses responses as as they they apply apply toto the loss of the loss of condenser vacuum:
condenser vacuum: loss loss of of steam steam dumpdump capability capability upon upon loss of condenser vacuum.
2.8/3.1 2.8/3.1 10CFR55:
10CFR55: 41.b.4, 41.b.5 41.bA,41.b.5
Reference:
Reference:
5610-T-L1, 561 Sheet 22A O-T-L 1, Sheet 22A Cog Level:
Cog Level: 22 Comprehension Comprehension Level 22 because Level because the operator operator must must recognize recognize that 20" 20 is is aa condition condition that that may may bebe expected expected for this situation and is this situation and is aa signal signal that that disables disables the the SDTC SDTC while the the 545°F Tavg is aa condition Tavg condition that could also also be expected for this situation but but does does not disable the SDTC. Additionally the operator must recognize that the alarm being extinguished under these circumstances extinguished circumstances implies the system is disabled.
New Question New Response Analysis:
Response
A. Correct per the references The SDTC arming signal is clear because vacuum dropped below 20 20" and the SDTC System is disabled.
B. Incorrect because the SDTC system has become disabled. Plausible because it became disabled when vacuum dropped below 20. 20".
C.
C. Incorrect Incorrect because because even even though though Tavg Tavg may may have have dropped dropped below below 543°F, 543°F, itit isis now now above 543°F 543°F andand the system system isis not not disabled disabled because of of previously previously dropping dropping below below 543° 543°F.F. Plausible Plausible because because the the system system is is disabled disabled butbut itit is is due to the due to the low low vacuum.
vacuum.
D.
D. Incorrect Incorrect because because thethe SDTC SDTC system system hashas been been disabled.
disabled. Plausible Plausible because because Tavg Tavg may may have have dropped dropped below below 543°F 543°F following following the the trip.
trip.
Page42 Page 42
TURKEY POINT TURKEY PO1NT NRC NRC EXAM EXAM - 05109/07
- 05/09/07 Q #22 0#22 The Shift The Shift Manager Manager directs directs evacuation evacuation ofof the control room the control room perper 0-ONOP-1 O-ONOP-1 05,05, Control Room "Control Room Evacuation."
Evacuation.
- At the At the Alternate Alternate Shutdown Shutdown Panel Panel (ASP),
(ASP), the the RO RD inserts inserts handles handles into into the the yellow bordered yellow bordered switches switches and and places places them them in in the the LOCAL LOCAL position.
position.
Which ONE Which ONE of of the the following following describes describes the the purpose purpose ofof the the transfer transfer switches switches associated with associated with the the AFW AFW flow control valves flow control valves (FCVs)?
(FCVs)?
A.
A. transfers control transfers control of Train 22 FCVs of Train FCVs toto the the ASP ASP B. enables local control of of Train 2 FCVs at the valves C. transfers control of Train 1I FCVs to the ASP D. enables local control of Train 11 FCVs at the valves Page 43 Page 43
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q #22 Q#22 ANSWER:
ANSWER: AA KA:
KA: 000068G2.i.28 000068G2.1.28 As itit relates As relates to to the control room the control room evacuation evacuation event:
event: Knowledge Knowledge of of the the purpose purpose and and function of function major system of major system components components andand controls.
controls. 3.2/3.3 3.2/3.3 IOCFR55:
10CFR55: 41.b.4, 41.b.7, 41.bA, 41.b.7, 41.b.8 41.b.8
Reference:
Reference:
O-ONOP-l 05, Attachment 3, O-ONOP-1 3, NOTE NOTE prior prior to Step 6, Step 6 SD-i 53, Page SO-153, Page 41, 41, Figure Figure 4C, 40, 40 4D Cog Level: 11 Recall New Question Response Analysis:
A. Correct per the reference. The transfer switches transfer control of Train 2 FCVs to the ASP B. Incorrect because local hand control of the AFW valves at the valves is independent of the transfer switch. Plausible because these are the same Train 2 FCVs that are controlled from the ASP when the transfer switches are in place.
C. Incorrect because the affected valves are Train 2 not Train 1. Plausible because the transfer switches transfer FCVs to the ASP, but it is Train 22 FCVs, not Train 1 1 FCVs.
D.
O. Incorrect because the affected affected valves are Train 22 not not Train 1.
- 1. Plausible because local control of AFW valves at the valves is possible, but it is Train 22 FCVs, notnot Train I1 FCVs Page 44 Page 44
TURKEY POINT TURKEY POINTNRCNRC EXAM EXAM- 05/09107 05/09/07 Q #23 0#23 The crew The crew isis performing performing aa post LOCA cooldown post LOCA cooldown and and depressurization depressurization inin accordance accordance with 4-EOP-ES-1.2, with 4-EOP-ES-1 .2, "Post Post LOCA LOCA Cooldown Cooldown and and Depressurization."
Depressurization.
control.
- Two Two Emergency Emergency Containment Containment Coolers Coolers (ECCs)
(ECCs) are are running.
running.
- All All Normal Normal Containment Containment Coolers Coolers (NCCs)
(NCCs) areare operating.
operating.
Containment pressure Containment pressure just just increased increased from from 1919 psig to 22 psig to 22 psig.
psig.
ONE of Which ONE of the following describes the following describes actions actions associated associated withwith operation operation of of the the NCCs NCCs AND the bases the bases for for those those actions?
actions?
A. Continue Operation Continue Operation of of the NCCs NCCs to to maintain maintain RCP RCP operation and and to assist assist in in containment pressure reduction.
B. Continue operation of the NCCs to maximize containment cooling and atmosphere circulation to prevent stratification and eliminate pockets of hydrogen.
C. Stop all NCCs to allow starting the 3rd Emergency Containment Cooler without violating CCW System load requirements.requirements.
D. Stop all NCCs to prevent violating CCW System load requirements. requirements.
Page45 Page 45
TURKEY POINT TURKEY POThTTNRCNRC EXAM EXAM - 05/09107
- 05/09/07 Q #23 Q#23 ANSWER:
ANSWER: D D
KA:
KA: WIEI4EK3.3 W/E14EK3.3 Knowledge for Knowledge for the the reasons reasons for for the following responses the following responses as as they they apply apply to to the the high high containment pressure: manipulation of controls containment pressure: manipulation of controls required required toto obtain obtain desired desired operating operating results during results during abnormal abnormal andand emergency emergency situations.
situations. 3.5/3.5 3.5/3.5 10CFR55:
10CFR55: 41.b.7, 41.b.8, 41.b.7, 41.b.8, 41.b.10 41.b.1O
Reference:
Reference:
4-EOP-FO, Enclosure 4-EOP-F-O, Enclosure 55 4-EOP-FR-Z.1,, Step 4-EOP-FR-Z.1 Step 1I 4-EOPFR-Z.
4-EOP-FR-Z.1, 1, Step 1I BD Cog Level: Comprehensive 2 Comprehensive Level 2 because the operator must recognize that that the conditions have changed requiring transition to EOP-FR-Z.1 which will direct securing of the RCPs which in turn allows the NCCs to be secured.
New Question Response Analysis:
A. Incorrect because the NCCs NCC5 and RCPs have to be stopped per EOP-FR-Z.1. EOP-FR-Z.1.
Plausible because running NCCs would help to maximize containment pressure reduction and cool the RCP if it was left running.
B. Incorrect because the NCCs have to be stopped per EOP-FR-Z.I. EOP-FR-Z.1. Plausible because running NCCs would help to maximize containment air circulation.
C. Incorrect because procedural limitations restrict operators from running three ECCs.
ECCs. Plausible Plausible because an additional ECC would help with the containment pressure reduction.
D.
D. Correct, the NCCs Correct, the are required NCCs are required to to be be stopped stopped lAW lAW FR-Z.1 FR-Z.1 guidance.
guidance.
Page 46 Page 46
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09107
- 05/09/07 Q #24 Q#24 3-EOP-FR-C.2, "Response 3-EOP-FR-C.2, Responsetoto Degraded Degraded Core CoreCooling,"
Cooling,directs directsoperators operatorstoto depres surize the RCS depressurize the RCS toto inject injectthe theaccumulators accumulators intointothe the RCS.
RCS.
Which ONE Which ONE ofofthe thefollowing following describes describes how howthethe RCS will be RCS will be depressurized depressurized toto inject inject the accumulators the accumulators andand how howoperators operators will will prevent preventaccumulator accumulator nitrogen injection?
nitrogen injection?
A.
A. Open one Open one pressurizer pressurizer PORV PORV until until RCS RCS pressure pressure isis less less than than 80 80 psig.
psig.
Isolate accum ulators when Isolate accumulators when RCS RCS CETCET subcooling subcooling isis less less than than 30°F.
30°F.
B.
B. Open one Open one pressurizer pressurizer PORV PORV until until RCS RCS pressure pressure isis less less than than 180 180 psig.
psig.
Isolate accumulators when Isolate accumulators when RCS RCS hot hot leg leg temperatures temperatures are are less less than than 340°F.
340°F.
C.
C. Dump steam Dump steam from from intact intact S/Gs S/Gs until until SG SG Pressure Pressure isis less less than than 180 180 psig.
psig.
Isolate accumulators Isolate accumulators when when RCS RCS CET CET subcooling subcooling isis less than 30°F.
less than 30° F.
D.
D. Dump steam Dump steam from from intact intact S/Gs SIGs until until S/G S/G pressure pressure is is less less than than 80 80 psig.
psig.
Isolate accum ulators Isolate accumulators when RCS RCS hot hot leg leg temperatures temperatures are are less less than than 340°F.
340°F.
Page4747 Page
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM 05/09/07
- 05/09/07 Q #24 Q#24 ANSWER:
ANSWER: 0D KA:
KA: W/EO6EK1.1 W/E06EK1.1 Knowledge Knowledge of the operational of the operational implications implications of of the the following following concepts concepts asas they they apply apply to to the degraded core cooling: components, the degraded core cooling: components, capacity capacity and and function function of of emergency emergency systems. 3.6/4.0 systems. 3.6/4.0 10CFR55:
10CFR55: 41.b.3, 41.bA, 41.b.3, 41.b.4, 41.b.5, 41.b.5, 41.b.7 41.b.7
Reference:
Reference:
3-EOP-FR-C.2, Steps 3-EOP-FR-C.2, Steps 1313 and and 15 15 SD-021, Page SO-021, Page 1818 Cog Level:
Cog Level: 1I Recall Recall New Question New Question Response Analysis:
Response
A.
A. Incorrect because RCS pressure is reduced by dumping steam from intact S/Gs and Thot < 340°F is the criteria for isolating accumulators.
accumulators. Plausible because opening a PORV is a method often used during EOP implementation to depressurize the RCS.
implementation B. Incorrect because RCS pressure is reduced by dumping steam from intact S/Gs. Plausible because opening pressurizer PORVs is aa method often used during EOP implementat implementationion to depressurize the RCS and Thot << 340°F is the criteria for stopping the depressurizat depressurization.ion.
C. Incorrect because the parameter used used to judge when to stop dumping dumping steam is S/G is S/G pressure. The The stopping stopping criteria inin ECA-0.0 ECA-O.O is is S/G Pressure at at 180 180 psig.
psig. Plausible Plausible because because reducing reducing subcooling subcooling implies implies reducing reducing RCS RCS pressure pressure also also o.
D. Correct Correct perper the the reference.
reference. Operators Operators will will dump dump steam steam from from intact intact S/Gs S/Gs until until S/G S/G pressure pressure isis less less than than 8080 psig psig and and isolate isolate accumulators accumulators whenwhen RCS RCS hothot leg temperatures leg temperatures are are less less than than 340°F.
340°F.
Page48 Page 48
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05109107
- 05/09/07 Q#25 Q#25 In accordance In accordance withwith 3-EOP-ES-1.1, 3-EOP-ES-1 .1, "SI SI Termination,"
Termination, Which ONE Which ONE of of the the following following describes describes thethe basis basis for for restoring restoring seal seal return return flow flow to to the the VCT AND VCT AND whywhy RCSRCS pressure pressure must must be be greater greater than than 100 100 psi psi above above VCT VCT pressure pressure before opening before opening MOV-3-381 MOV-3-381 and and MOV-3-6386?
MOV-3-6386?
Seal return Seal return is is restored restored to the VCT to the VCT to:to:
A. stop #1 sealleakoff stop seal leakoff flow flow from flowing to PRT.
to the PRT.
RCS pressure RCS pressure must must bebe higher higher than VCT pressure pressure to prevent prevent Hydrogen Hydrogen intrusion from intrusion from the VCT into the VCT into the the RCS.
RCS.
B. stop #1 seal leakoff flow from flowing to the PRT.
RCS pressure RCS pressure must must be higher higher than VCT pressure pressure to prevent prevent reverse reverse flow from the VCT into the RCS.
C. re-establish #1 seal leakoff flow.
RCS pressure must be higher than VCT pressure to prevent Hydrogen intrusion from the VCT into the RCS.
D. re-establish #1 seal leakoff flow.
RCS pressure must be higher than VCT pressure to prevent reverse flow from the VCT into the RCS .
Page 49 Page 49
TURKEYPOINT TURKEY POINTNRC NRC EXAM EXAM- 05/09107
- 05/09/07 Q#25 Q#25 ANSWER:
ANSWER: BB KA:
KA: W/E02EK3.1 W/E02EK3.1 Knowledge for Knowledge for the the reasons reasons for for the the following following responses responses as as they they apply apply to the SI to the SI termination: Facility termination: Facility operating operating characteristics characteristics duringduring transient transient conditions, conditions, including including coolant chemistry coolant chemistry and and the the effects effects ofof temperature, temperature, pressure, pressure, andand reactivity reactivity changes changes and operating and operating limitations limitations and and reasons reasons for for these these operating operating characteristics.
characteristics. 3.3/3.6 3.3/3.6 I OCFR55:
10CFR55: 41 .b.2, 41.b.3, 41.b.2, 41 .b.3, 41.b.10 41 .b.10
Reference:
Reference:
3-EOP-ES-1 .1, Step 3-EOP-ES-1.1, Step 20 20 BO BD 5613-M-3047, Sheet 3 5613-M-3047,Sheet3 Cog Level: 1I Recall New Question New Response Analysis:
A. Incorrect because the stated reason for the required 100 psi differential in the Basis document is to prevent backflow from VCT to RCS, not to prevent Hydrogen intrusion from the VCT into the RCS. Plausible because stopping seal return flow to the PRT is the reason for restoring normal seal return.
B. Correct per the references. Seal return is restored to the VCT to stop #1 #1 seal leakoff flow from flowing to the PRT and RCS pressure must be higher than VCT pressure to prevent reverse flow from the VCT into the RCS.
C. Incorrect because stopping seal return flow to the PRT is the reason for restoring normal seal return. Note Note that even though seal return was isolated, isolated,
- 1 seal leakoff leakoff still existed to the PRT. Plausible because Hydrogen is is present present in in the the VCT VCT which which can find find its its way way toto the the RCS RCS ifif aa flow flow path path is is established.
D.
O. Incorrect Incorrect because because stopping stopping seal seal return return flow flow to to the the PRT PRT is is the the reason reason forfor restoring restoring normal normal seal seal return.
return. Note Note thatthat even even though though seal seal return return was was isolated, isolated,
- 1 seal
- 1 leakoff still sealleakoff still existed existed to to the the PRT.
PRT. Plausible Plausible because because the the stated stated reason reason for for the the required required 100 100 psipsi differential differential in in the the Basis Basis document document is is to to prevent prevent backflow backflow fromfrom VCT VCT to to RCS, RCS, Page50 Page 50
TURKEY POINT TURKEY POP4T NRC EXAM - 05/09107 NRC EXAM - 05/09/07 Q #26 0#26 AA RCS RCS leak leak has has occurred occurred that that required required aa manual manual reactor reactor trip trip based based onon the the inability inability to maintain to maintain Pressurizer Pressurizer level.
level.
Operators are Operators are performing performing 4-EOP-ES-1.2, 4-EOP-ES-1 .2, "Post Post LOCA LOCA Cooldown Cooldown and and Depressuriza tion.
Depressurization."
The US The US directs directs the the RO RO to depressurize the to "depressurize the RCS RCS toto refill refill the the pressurizer."
pressurizer.
ONE of Which ONE of the following identifies identifies the method method the RORO will use use to depressurize depressurize the RCS, in the RCS, in order order ofof preference, preference, as directed by as directed 4-EOP-ES-1 .2?
by 4-EOP-ES-1.2?
A. 1) Normal Spray
- 1) 2) PRZ PORV 3) Aux Spray B. 1) Normal Spray
- 1) 2) Aux Spray 3) PRZ PORV C. 1) Aux Spray 2) PRZ PORV 3) Steam Dump D. 1) Aux Spray 2) Normal Spray 3) PRZ PORV Page 51 Page 51
TURKEY POINT TURKEY POINTNRC NRC EXAM EXAM- 05/09/07
- 05/09/07 Q#26 Q#26 ANSWER:
ANSWER: AA KA:
KA: W/EO3EK1 .3 W/E03EK1.3 Knowledge of Knowledge of the the operational operational implications implications of of the the following following concepts concepts as as they they apply apply to to LOCA Cooldown and Depressuriza tion: annunciators LOCA Cooldown and Depressurization: annunciators and and conditions, conditions, indicating indicating signals and signals and remedial remedial actions actions associated associated with with the the (LOCA (LOCA cooldown cooldown and and depressurization. 3.5/3.8 depressurization. 3.5/3.8 IOCFR55:
10CFR55: 41.b.7, 41.b.10 41.b.3, 41.b.7,
Reference:
Reference:
4-EOP-ES-1.2, Step 4-EOP-ES-1.2, Step 10 10 Cog Level: 1I Recall Bank Question Response Analysis:
A. Correct per the reference B. Incorrect because a pressurizer PORV is preferred over Aux Spray Spray....
Plausible because normal spray is the preferred first method to reduce pressure.
C. Incorrect because steam dump is not a method directed by ES-1.2 ES-i .2 and a pressurizer PORV is preferred over Aux Spray. Plausible because all three methods listed are effective methods of RCS pressure reduction under these conditions.
D. Incorrect because Normal spray is the first choice directed by ES-i ES-1.2.
.2.
Plausible because all three methods listed are effective methods of RCS pressure reduction under these conditions and all are methods directed by ES-i .2.
Page 52 Page 52
TURKEY POINT TURKEY POINTNRC EXAM- 05/09107 NRC EXAM - 05/09/07 Q #27 Q#27 In accordance In accordance withwith 4-EOP-FR-P.1, 4-EOP-FR-P.1, "Response Response to to Imminent Imminent Pressurized Pressurized Thermal Thermal Shock Condition,"
Shock Condition, which which ONEONE of of the the following following describes describes the the BASIS BASIS forfor starting starting anan RCP?
RCP?
An RCP An RCP isis started started to:
to:
A.
A. minimize the minimize the time time toto reach reach Mode Mode 55 byby allowing allowing aa faster faster cooldown cooldown with with forced forced cooling than cooling than with with natural natural circulation circulation andand decrease decrease the the likelihood likelihood of of aa Pressurized Thermal Pressurized Thermal ShockShock condition.
condition.
B.
B. restore normal restore normal pressurizer pressurizer sprayspray capability capability toto subsequently subsequently reduce reduce RCSRCS pressure pressure to the right of the 60° right 60°/hr Ihr cooldown curve.
C. mix cold SI water with warm RCS water and decrease the likelihood likelihood of a Pressurized Thermal Shock condition.
D. mix the water in the vessel and loops to ensure boron concentration is equal throughout the reactor coolant system.
Page 53 Page 53
TURKEY POINT TURKEY NRC EXAM POINT NRC EXAM - 05/09107
- 05/09/07 Q #27 Q#27 ANSWER:
ANSWER: C C KA:
KA: W W/E08G2.1 IE08G2.1.28.28 RCS overcooling - PTS, RCS overcooling PTS, As As itit relates relates to to the the PTS PTS event:
event: Knowledge Knowledge of of the the purpose purpose and function of major system and function of major system components components and and controls.
controls. 3.2/3.3 3.2/3.3 IOCFR55:
10CFR55: 41.b.2, 41.b.3, 41.b.2, 41.b.3, 41.b.7, 41.b.7, 41.b.10 41.b.10
Reference:
Reference:
3-EOP-FR-P.1 SD, 3-EOP-FR-P.1 BD, Step Step 2727 Cog Level: 11 Recall New Question New Response Analysis:
A. Incorrect because starting an RCP does not allow a faster cooldown rate in FRP.1. Plausible because the normal cooldown rate limit with RCPs is FR-P.1.
1100°F/hr OO°F/hr and without RCPs is 25°F/hr.
B.
S. Incorrect because RCS pressure will be subsequently maintained within a band between the minimum subcooling curve and the 200°F subcooling curve. Plausible because even though EOP-FR-P.1 does not specify which RCP should be started, operators will normally start an RCP with pressurizer spray capability.
C. Correct per the reference. An RCP is started to mix the cold SI water with warm RCS water and decrease the likelihood of aa PTS condition.
D. Incorrect because mixing of boron in the loops is not aa basis described in the EOP-FR-P.1 basis document. Plausible because running aa RCP provides this desirable desirable benefit.
Page 54 Page 54
TURKEY POINT TURKEY PONT NRCNRC EXAM EXAM - 05/09/07
- 05/09/07 Q#28 0#28 Operators are Operators are cooling cooling down down the the plant plant in in accordance accordance withwith 3-GOP-305, 3-GOP-305, "HotHot Standby Standby to Cold to Cold Shutdown."
Shutdown.
- 33 A,B, A,B, && C C RCP RCP pump pump bearing bearing temperatures temperatures have have slowly slowly increased increased
- annunciator H9/6, "RCP annunciator H9/6, RCP A/B/C A/B/C PUMP/MOTOR PUMP/MOTOR HI HI TEMP" TEMP has has just just alarmed alarmed
psid.
- 3A, B, & C RCP seal injection flow is 10 10 gpm.
- 3B RCP #1 seal leakoff flow is 0.7 gpm.
- 3B RCP RCP # 11 sealleakoff seal leakoff isol isol valve, CV-3-303B, CV-3-303B, is is open.
- RCS pressure is 450 psig.
Which ONE of the following describes the correct operator response?
A. Increase seal injection flow to the 3B RCP to greater than 13 gpm.
B. Open the RCP Seal Bypass Valve, CV-3-307.
C. Close the 3B Rep RCP #1 sealleakoff seal leakoff isol valve, CV-3-303B.
D. Increase CCW flow through the 3B RCP thermal barrier.
Page 55 Page 55
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/0 7 Q #28 Q#28 ANSWER:
ANSWER: BB KA:
KA: 003A4.07 003A4.07 Ability to Ability manually operate to manually operate and/or and/or monitor monitor in in the the control control room room RCP RCP seal seal bypass.
bypass.
2.6/2.6 2.6/2.6 100FR55:
10CFR55: 41.b.5, 41.b.1O 41.b.5,41.b.10
Reference:
3-GOP3O5, Step 5.3.5.9.d 3-GOP-305, 3-ONOP-041.1, Step 35 3-0NOP-041.1, Cog Level: 2 Comprehension Level 2 because the operators must evaluate plant conditions and determine that opening the bypass valve would improve the RCP pump bearing temperature conditions. Many plant conditions must be met in order to use the bypass valve and the operator must analyze the current conditions to determine that it is appropriate and desired in this situation.
New Question Response Analysis:
A. Incorrect because the required procedural response is to open the RCP Seal Bypass Valve, CV-3-307. Plausible because the RCP seal sealleakoff leakoff flow rate is low and the RCP bearing temperature is increasing.
B. Correct per the reference. With these conditions, operators will open the RCP Seal Bypass Valve, CV-3-307.
C. Incorrect because the required procedural response is to open the RCP Seal Bypass Valve, CV-3-307. Plausible because CV-303B will be closed in aa subsequent step in the same procedure (GOP-305, Step 5.19.14,9.b) and would terminate the flow of hot water to the VCT D. Incorrect because the required procedural response is to open the RCP Seal Bypass Valve, CV-3-307. Plausible because increasing CCW through the thermal barrier would be beneficial to pump bearing cooling if seal injection flow was lost.
Page 56 Page 56
TURKEY POINT TURKEY POiNT NRC NRC EXAM EXAM - 05/09/07 05/09/07 Q #29 Q#29 Unit 33 isis at Unit at 100%
100% power power when when VCT VCT level level transmitter, transmitter, LLT-3-1 T 115, 15, fails fails high.
high.
Which ONE Which ONE of of the the following following describes describes the the effect effect on on the the plant plant assuming assuming NO NO operator operator action?
action?
VCT level will:
VCT level will:
A.
A. decrease.
decrease.
Auto-makeup will NOT NOT occur.
occur.
Auto-swap Auto-swap to the RWST to the RWST will will occur.
occur.
B. decrease.
Auto-makeup will NOT occur.
Auto-swap to the RWST will NOT occur.
C. increase.
automatically.
Auto-makeup will start and stop automatically.
LCV-3-1 1 5A will auto-divert to the CVCS HUT.
LCV-3-115A D. increase.
Auto-makeup will start but NOT stop automatically.
automatically.
LCV-3-1 1 5A will auto-divert to the CVCS HUT.
LCV-3-115A Page 57 Page 57
TURKEY POINT TURKEY POINT NRC EXAM - 05/09/07 NRC EXAM - 05/09/07 Q#29 Q#29 ANSWER:
ANSWER: BB KA:
KA: 004K1 .23 004K1.23 Knowledge of the physical Knowledge physical connection and/or cause-effect relationships between between the CVCS and and the RWST. 3.4/3.7 IOCFR55:
10CFR55: 41.b.6, 41.b.7 41.b.6,41.b.7
Reference:
3-ONOP-046.4, Step 28, CAUTION and NOTE prior to Step 29 3-0NOP-046.4, Cog Level: 1I Recall New Question Response Analysis:
A. Incorrect because auto-swap to the RWST will not occur (2 of 2 low levels required). Plausible because VCT level will decrease and auto-makeup will not occur.
B. Correct per the reference. VCT level will decrease. Auto-makeup will NOT occur. Auto-swap to the RWST will NOT occur.
C. Incorrect because VCT level will decrease and auto-makeup will not occur.
Plausible because LCV-115A LCV-I I 5A will auto-divert to the CVCS HUT.
D. Incorrect because VCT level will decrease and auto-makeup will not occur.
LCV-l 1 5A will auto-divert to the CVCS HUT.
Plausible because LCV-115A Page 58 Page 58
TURKEYPOINT TURKEY POINTNRCNRCEXAM EXAM- 05/09/07
- 05/09/07 Q #30 0#30 Unit33isisoperating Unit operatingatat10- I 08 8 amps Interm amps Intermediate ediateRange Rangepowerpowerwhenwhenan anInstrument InstrumentAir Air (IA) System leak reduce (IA) System leak reducessthe theIA IApressure pressuretoto60 60psig psigon onboth both units.
units.
Operatoractions Operator actionsare are unsuccessful unsuccessful inin restoring restoring IAIA pressure.
pressure.
Which ONE Which ONEof ofthe thefollowing following describes describes thethe effect effect of ofthis this event eventon on Unit Unit33 pressurizer pressurizer level and the level and the correct correct operator operatorresponse?
response?
Pressurizer level Pressurizer level will:
will:
A.
A. decrease.
decrease.
Trip the Trip the reactor reactor andand perform perform EOP-E-O, EOP-E-0, "Reactor Reactor TripTrip or or Safety Safety Injection."
Injection.
Start and stop charging pumps Start and stop charging pumps as as necessary necessary to to restore restore Pressurizer Pressurizer level level to to between 22 between 22 - 50%
50% using using 3-0NOP-013, 3-ONOP-013, "Loss of Instrument Loss of Instrument Air. Air".
BB decrease.
decrease.
Locally close Locally close the the Letdown Letdown orifice orifice isolation isolation valves.
valves.
Start additional Start additional charging charging pumps pumps andand increase increase speed speed in Manual using 3-0P-in Manual 3-OP-047, CVCS 047, "cvcs ChargingChargi ng and Letdown.
Letdown."
C C increase.
increase.
Trip the reactor Trip the reactor and perform EOP-E-O,EOP-E-0, "Reactor Reactor Trip or Safety Injection."
Injection.
Start and Start and stop chargin charging g pumps as necessary to mainta necessary maintain in Pressurizer Pressurizer levellevel betwee between n 22 22 - 50% using 3-ONO P-013, Loss 3-0NOP-013, Instrument "Loss of Instrum Air".
ent Air.
D.
D. increas increase. e.
Place Place excess excess Letdow Letdown n in in service using using 3-OP-0 3-0P-047, "cvcs Chargi 47, CVCS Charging and ng and Letdow n. Place the Letdown." Place the runnin running g chargin charging g pump pump speed speed contro controller in Manua ller in Manuall and and reduce reduce chargin charging g pump pump speed speed to to minim minimumum using using 3-OP-0 3-0P-047, "cvcs Charging 47, CVCS Charging and and Letdow Letdown." n.
Page5959 Page
TURKEYPOINT TURKEY POINTNRC NRC EXAM EXAM- 05109107 05/09/07 Q #30 Q#30 ANSWER:
ANSWER: CC KA:
KA: 004A2.11 004A2.11 Ability to Ability to (a) predict (a) predict the the impacts impacts of of the the following following malfunctions malfunctions or or operations operations on on the the CVCS; and CVCS; and (b) based on (b) based on those those predictions, predictions, use use procedures procedures to correct, control, to correct, control, or or mitigate the consequence mitigate the consequencess of of those those malfunctions malfunctions or or operations:
operations: lossloss of of lAS.
lAS.
3.6/4.2 3.6/4.2 10CFR55:
10CFR55: 41.b.4, 41.b.5, 41.b.4, 41.b.5, 41.b.10 41.b.10
Reference:
Reference:
0-ONOP-013, FO 0-ONOP-013, EQ Page, Page, StepStep 13 13 RNO RNO 2.g. 2.g.
Cog Level:
Cog Level: 22 Comprehension Comprehension Level 2 because the operator must recognize that the loss of IA will result in the running charging pump(s) going to full speed and the letdown valves closing resulting in increasing pressurizer level. The operator must also relate the plant conditions and system responses to the need for a reactor must be tripped when IA pressure drops to <65 psig.
New Question Response Analysis:
A. Incorrect because pressurizer level will increase. Plausible because the correct response to IA pressure at 60 psig is to trip the reactor and enter EOP-E-0 EOP-E-O and ONOP-13 directs starting and stopping charging pumps to control Prz level.
B.
B. Incorrect Incorrect because because pressurizer level level will will increase.
increase. Plausible Plausible because because ifif level level were to decrease, decrease, starting additional charging pumps pumps and and isolating letdown letdown would would be be the the appropriate appropriate operator operator response.
response.
C.
C. Correct Correct per the reference.
per the reference. Pressurizer Pressurizer levellevel will will increase.
increase. Operators Operators will will trip trip the the reactor reactor andand perform perform EOP-E-0, EOP-E-O, Reactor "Reactor TripTrip or or Safety Safety Injection.
Injection."
They will subsequently They will subsequently start start and and stop stop charging charging pumpspumps as as necessary necessary to to maintain maintain Pressurizer Pressurizer level level between between 22 22 - 50%
50% using using 3-ONOP-013 3-0NOP-013,, Loss"Loss of of Instrument Instrument Air.Air".
D.
D. Incorrect Incorrect because because placing placing excess excess letdown letdown in in service service isis not not possible possible due due toto the loss of IA and the charging the loss of IA and the charging pumps will pumps will run run at at maximum maximum speedspeed only only in in Manual.
Manual. Plausible Plausible because because pressurizer pressurizer level level will will increase.
increase.
Page 60 Page 60
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09107
- 05/09/07 Q#31 0#31 Unit 44 is Unit is in in Mode Mode 44 with with RHR RHR cooling cooling inin service.
service.
The automatic The automatic controller controller circuit circuit for for RHR RHR Heat Heat Exchanger Exchanger Bypass Bypass Flow Flow control control valve, valve, FCV-4605 has FCV-4-605 has failed resulting in failed resulting in the the FCV FCV going going closed.
closed.
Which ONE Which ONE of of the following describes the following describes thethe correct correct operator operator response response in in accordance accordance with 4-ONOP-050 , Loss with 4-0NOP-050, "Loss of RHR?" of RHRT Place FCV-4-605 Place FCV-4-605 controller controller in in Manual Manual andand raise raise flow flow to:
to:
A.
A. between 3000 between 3000 andand 3750 3750 gpm.
gpm.
If manual control is NOT possible, direct the NSO NSO to locally control FCV-4-605 to raise flow to between 3000 and 3750 gpm.
B. >3750gpm.
> 3750 gpm.
If manual control is NOT possible, direct the NSO to locally control FCV-4-605 to raise flow to > 3750 gpm.
C. between 3000 and 3750 gpm.
If manual control is NOT possible, open RHR Heat Exchanger Outlet Flow control valve, HCV-4-758 to raise flow to between 3000 and 3750 gpm.
D. >3750gpm.
> 3750 gpm.
If manual control is NOT possible, open RHR Heat Exchanger Outlet Flow control valve, HCV-4-758 to raise flow to > > 3750 gpm.
Page 61 Page 61
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q#31 Q#31 ANSWER:
ANSWER: A A
KA:
KA: 005G2.1.30 As itit relates to RHR, RHR, ability to locate locate and operate components, including including local local controls. 3.9/3.4 10CFR55:
10CFR55: 41.b.4, 41.b.7, 41.b.4, 41.b.7, 41.b.8, 41.b.10 41.b.1O
Reference:
4-ONOP-050, Step 7 4-0NOP-050, 4-ONOP-041 .8, Attachment 1, Step 8.c, 9.d 4-0NOP-041.8, Cog Level: 1I Recall New Question Response Analysis:
A. Correct per the reference. Operators will place FCV-4-605 controller in Manual and raise flow to between 3000 and 3750 gpm.
If manual control is NOT possible, operators will direct the NSO to locally control FCV-4-605 to raise flow to between 3000 and 3750 gpm.
B. Incorrect because flow should be increased to between 3000 and 3750 gpm.
Plausible because if control room control is not possible, the NSO will be directed to locally control FCV-605.
C. Incorrect because operators are directed to use FCV-605, not HCV-758 to locally control flow. Plausible because flow should be increased to between 3000 and 3750 gpm and opening HCV-758 more would increase flowrate and can be done by the RO from the control room.
D. Incorrect because flow should be increased to between 3000 and 3750 gpm and operators are directed to use FCV-605, not HCV-758 to locally control flow. Plausible because opening HCV-758 HCV-758 more more would increase increase flowrate and and can be be done done by by the RO from the control room.
Page 62 Page 62
TURKEY POINT TURKEY POfNT NRC EXAM - 05/09/07 NRC EXAM - 05/09/07 Q #32 0#32 With Unit With Unit 33 at at 100% power, the 100% power, the following following events events occurred:
occurred:
pressure.
- An automatic An automatic SI SI occurred occurred on on the the trip trip depressurization.
depressurization.
lowering.
Which ONE of the following describes the response of the safety injection system?
A. SI immediately resets when the reset pushbuttons are depressed.
B. SI reset occurs one minute after the reset pushbuttons are depressed.
C. SI reset occurs two minutes after the reset pushbuttons are depressed.
D. SI will NOT reset.
Page 63 Page 63
TURKEYPOINT TURKEY POINTNRC NRC EXAM EXAM- 05/09107
- 05/09/07 Q #32 Q#32 ANSWER:
ANSWER: BB KA:
KA: 006A4.08 006A4.0B ECCS - Ability ECCS - Ability toto manually manually operate operate and/or and/or monitor monitor in in the the control control room, room, 4.2/4.3 4.2/4.3 10CFR55:
10CFR55: 41.b.7, 41.b.8 41.b.7,41.b.B
Reference:
Reference:
561 O-T-L1, 5610-T Sheet 11
-L 1 , Sheet 11 Cog Level:
Cog Level: 22 Comprehension Comprehension Level 22 because Level because the the operator operator must must recognize recognize that that the the SISI reset reset logic logic isis different different ifif the the initiating event initiating event was SI due to automatic SI due automatic actuation actuation or or manual manual actuation.
actuation. There There is is also aa difference also difference in in reset reset operation operation ifif thethe automatic automatic initiating initiating signal signal is is still still present present or or has cleared, in in this case the initiating initiating signal is is still present. The SI signal signal automatically actuated and is is still present, present, therefore the system "remembers" remembers the reset attempt and SI will reset after an additional minute (2 minutes total). The operator must relate that even though RCS pressure is below the automatic SI setpoint, the system will allow manual reset in two minutes. If the SI Signal signal was manually actuated, the system does not remember the reset attempt within the first 2 minutes and SI will not reset until another reset attempt is made after the 2 minute timer times*
times out.
New Question Response Analysis:
A. Incorrect because SI did not reset in this situation. Plausible because SI normally resets immediately when operators push the manual reset pushbuttons as it is normally more than two minutes after the initiation signal.
SI SI will reset after after one one more more minute, B.
B. Correct.
Correct. There There is is aa two minute minute delay delay soso SISI will reset within one one minute.
minute.
C.
C. Incorrect Incorrect because because SI SI was was already already reset.
reset. ItIt reset reset oneone minute minute earlier earlier as as the the 22 minute minute timer timer isis from from initiation initiation signal signal and and not not the the reset reset signal.
signal. Plausible Plausible because because the the reset reset logic logic does does use use aa 22 minute minute timertimer and and this this would would be be aa correct correct response response ifif the the RD RO attempted attempted to to reset reset immediately immediately or or ifif the the initiating initiating signal signal had had cleared.
cleared.
D.
D. Incorrect Incorrect because because the the auto auto SISI signal signal isis still still present present and and SISI reset reset will will occur.
occur.
Plausible because this Plausible because this would would apply apply ifif SI SI was was manually manually initiated initiated or or ifif the the initiating initiating auto auto SI SI signal Signal had had cleared.
cleared.
Page 64 Page 64
TURKEYPOINT TURKEY POINTNRCNRC EXAM EXAM- 05/09107 05/09/07 Q #33 Q#33 The NSO The NSO reports reports that that the the in-service in-service local local seal seal water water return return filter filter differential differential pressure pressure indicator isis off-scale indicator off-scale high.
high.
Subsequent investigation Subsequent investigation reveals reveals the the in-service in-service seal seal water water return return filter filter has has become become completely clogged.
completely clogged.
Which ONE Which ONE of of the the following following describes describes the the effect effect this this will will have have onon PRT PRT pressure pressure and and the correct actions the correct actions to to respond respond to to the the change change in in PRT PRT pressure?
pressure?
PRT pressure will:
PRT pressure will:
A. increase increase Verify the Verify the PRT PRT nitrogen nitrogen regulator, regulator, PCV-3-473, PCV-3-473, is is aligned aligned to thethe PRT.
PRT.
Start a waste gas compressor. Open the PRT PRT vent valve, CV-3-549.
When PRT pressure reaches 6 psig to 8 psig, then close close CV-3-549.
B. increase Verify the PRT nitrogen regulator, PCV-3-473, is aligned to the PRT.
Start a waste gas compressor. Open the PRT vent valve, CV-3-549.
When PRT pressure reaches vent header pressure, then close CV-3-549.
C. not be affected Verify the PRT nitrogen regulator, PCV-3-473, is aligned to the PRT and controlling PRT pressure in the normal range.
D. not be affected Verify the PRT vent valve, CV-3-549 is open.
When PRT pressure reaches vent header pressure, then close CV-3-549.
Page65 Page 65
TURKEY POINT TURKEY POINTNRCNRC EXAM EXAM- 05/09107 05/09/07 Q #33 Q#33 ANSWER:
ANSWER: AA KA:
KA: 007A1.02 007A1.02 Ability to Ability predict and/or to predict and/or monitor monitor changes changes in in parameters parameters (to (to prevent prevent exceeding exceeding design limits) design limits) associated associated withwith operating operating the the PRT PRT controls controls including maintaining PRT including maintaining PRT pressure. 2.7/2.9 pressure. 2.7/2.9 IOCFR55:
10CFR55: 41.b.3, 41.b.4, 41.b.3, 41.b.4, 41.b.1 41.b.1O 0
Reference:
Reference:
3-ARP-097.CR - A7/1, 3-ARP-097.CR A711, 3-OP-041 .3, Section 3-0P-041.3, Section 7.3.2 7.3.2 5613-M-304 7, Sheet 5613-M-3047,Sheet33 Cog Level: 2, Comprehension Comprehension The operator must realize that clogging the seal water return filter will result in lifting relief valve, RV-382, which relieves to the PRT. This will cause PRT level and pressure to increase. The operator must then recall the correct guidance provided by the ARP and OP.
New Question Response Analysis:
A. Correct per the reference. PRT pressure will increase. Operators will verify the PRT nitrogen regulator, PCV-3-473, is aligned to the PRT.
Start aa waste gas compressor. Open the PRT vent valve, CV-3-549.
When PRT pressure reaches 66 psig to 88 psig, then close CV-3-549.
B. Incorrect because PRT pressure must reach 66 to 88 psig before closing CV-549.
CV-549. Plausible Plausible because because PRT PRT pressure pressure will increase increase and and the the PRT PRT nitrogen nitrogen regulator, PCV-3-473, is is aligned aligned to the PRT.PRT.
C.
C. Incorrect Incorrect because because PRT PRT pressure pressure will increase increase andand thethe PRT PRT nitrogen nitrogen regulator, PCV-3-473, is aligned regulator, PCV-3-473, is aligned to to the the PRT.
PRT. Plausible Plausible because because when when PRT PRT pressure pressure reaches reaches 66 psig psig to to 88 psig, psig, then then CV-3-549 CV-3-549 is is closed.
closed.
D.
D. Incorrect Incorrect because because PRT PRT pressure pressure willwill increase increase andand thethe PRT PRT nitrogen nitrogen regulator, regulator, PCV-3-473, PCV-3-473, isis aligned aligned to to the the PRT PRT andand because because PRT PRT pressure pressure must must reach reach 66 to to 88 psig psig before before closing closing CV-549.
CV-549. Plausible Plausible because because vent vent header header pressure pressure isis lower lower than than 66 to to 88 psig psig and and would would represent represent aa greater greater pressure pressure reduction reduction than than that that provided provided by by the the procedure procedure instructions.
instructions.
Page 66 Page 66
TURKEY POINT TURKEY POINTNRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q #34 0#34 Unit 33 is Unit is at at 100%
100% power power with with all all systems systems inin normal normal alignment alignment whenwhen aa Loss Loss of of All All AC AC Power (LOAAC)
Power (LOAAC) occurs.
occurs.
Power, to restore the 3A 4KV to restore the 3A 4KV Bus Bus which which failed failed to to load load onto onto its its EDG EDG because because of of aa failure of failure of the the 3A sequencer.
3A sequencer.
indication.
position.
Which ONE of the following describes the response response of the 3A 3A CCW CCW pump pump breaker breaker light indication on VPB after the BOP places its its control switch in the STOP position?
The 3A CCW pump green light will:
A. remain on. Its red light will remain off.
B. immediately go off. Its red light will energize and remain on.
C. remain on for 10 seconds at which time it will go off and the red light will go on.
D. remain on for 30 seconds at which time it will go off and the red light will go on.
Page 67 Page 67
TURKEY POINT TURKEY POINT NRC EXAM - 05109107 NRC EXAM - 05/09/07 Q #34 Q#34 ANSWER:
ANSWER: C C
KA:
KA: 008A4.08 008A4.08 Ability to manually Ability manually operate and/or monitor monitor in the control room:
room: CCW COW pump pump control switch. 3.1/3.8 IOCFR55:
10CFR55: 41.b.4, 41.b.7 41.b.4,41.b.7
Reference:
5610-T-L1, 5610-T-L 1, Sheet 24D Cog Level: 3 Analysis/Application Level 3 because the operator must recognize that the 3A sequencer failure includes the bus stripping portion of the sequencer as evidenced by the operator's operators observation that the 3A Bus loads that were running before the LOAAC still have red breaker light indication. Bus stripping failed to work and bus stripping is the signal that blocks the timed low pressure auto-start of CCW COW pumps. When the operator takes the 3A CCW COW pump to off, the breaker opens but 10 seconds later it closes in because bus stripping did not block the low pressure auto-start.
New Question Response Analysis:
A. Incorrect because its green light will remain on for only 10 seconds at which time it will go out and the red light will come on. Plausible because this is the way the system would respond if the sequencer/bu sequencer/bus s stripping had not failed.
B. Incorrect because its green light will remain on for only 10 seconds at which time it will go out and the red light will come on. Plausible because more than ten seconds has elapsed and aa common misconception is that the breaker will immediately close.
C. Correct per the reference D. Incorrect because its its green light light will remain on for only 1010 seconds at which time itit will go out and the red light will come on. Plausible because this is the way 303C COWCCW pump indication would respond under these conditions and this is is the same same train pump.
pump.
Page 68 Page 68
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q #35 Q#35 Operators are Operators are responding responding to small-break LOCA to aa small-break LOCA onon Unit Unit 3.
3.
ONE of the following describes the steps performed Which ONE performed by by operators to restore restore pressurizer heaters the pressurizer heaters while responding responding to a small-break LOCA LOCA in accordance with 3-EOP-ES-1 .2, "Post 3-EOP-E8-1.2, Post LOCA Cooldown and Depressurization"?
Depressurization?
A. To restore BU BU Group Group "AA ", reset 81.
, SI.
To restore BU Group "B B ", place the Pressurizer Back-up Heater 3B key switch to EMERGENCY.
B. To restore BU Group "A A ", reset 81.
, SI.
To restore BU Group "B , SI, then reset the lock-out relay in the West B ", reset 81, Electrical Penetration Room.
C. To restore BU Group "B B ", place the Pressurizer Back-up Heater 3B key switch to EMERGENCY.
To restore BU Group "A A ", reset 81,
, SI, then reset the lock-out relay in the West Electrical Penetration Room.
D. To restore BU Group "B B ", reset 81.
, SI.
To restore BU Group "A A ", reset 81,
, SI, then reset the lock-out relay in the West Electrical Penetration Room.
Page 69 Page 69
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q #35 Q#35 ANSWER:
ANSWER: D D
KA: 01 KA: 01 OA2.01-0A2.01 Ability
- Ability to to (a) predict the (a) predict the impacts impacts ofof the the following following malfunctions malfunctions or or operations on operations on the PRZ PCS; the PRZ PCS; and and (b)
(b) based based onon those those predictions, predictions, use use procedures procedures to to correct, control, or mitigate the consequence correct, control, or mitigate the consequencess of of those those malfunctions malfunctions or or operations:
operations:
Heater failures.
Heater failures. 3.3/3.6 3.3/3.6 10CFR55:
10CFR55: 41.b.3, 41.bA, 41.b.3, 41.b.4, 41.b.7 41.b.7
Reference:
Reference:
3-EOP-ES-1 .2, Step 3-EOP-ES-1.2, Step 33 5610-T-L1, 5610-T-L Sheet 23 1, Sheet 23 Level:
Cog Level: Comprehension 2 Comprehension Level 2 because the operator must recognize that the response to a SBLOCA implies response to SI actuation. SI actuation is the signal that caused trip of all pressurizer heaters.
New Question Response Analysis:
A. Incorrect because to restore BU Group "B B, ", reset SI only, does not require a key-lock switch for SI reset, this is needed for LOOP only. To restore BU Group "AA ", reset SI, AND reset the lock-out relay in the West Electrical Penetration Room.
B. Incorrect because to restore BU Group B "B ", reset SI only, does not require aa lockout relay reset. To restore BU Group A "A ", reset SI, AND reset the lock
, lock-out relay in the West Electrical Penetration Room.
C. Incorrect because to restore BU Group B "B ", reset SI only, does not require aa key-lock switch for SI reset, this is needed for LOOP only. only. To restore BU Group A"A ", reset SI, AND reset the lock-out relay in the West Electrical
, Electrical Penetration Penetration Room D.
D. Correct Correct perper the the references references Page 70 Page 70
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09107
- 05/09/07 Q #36 Q#36 Operators are Operators are performing performing aa shutdown shutdown of of Unit Unit 44 in in accordance accordance with with 4-GOP-103, 4-GOP-i 03, Power Operations "Power Operations to to Hot Hot Standby".
Standby.
- Power isis currently Power currently 50%.
50%.
- First stage First stage pressure pressure transmitter, transmitter, PT-4-447, PT-4-447, failsfails HIGH.
HIGH.
Which ONE Which ONE of of the the following following describes describes the the effect effect of of this this failure failure on on the the normal normal operation of operation of the the reactor reactor protection protection system system during during thethe plant plant shutdown?
shutdown?
At the current power power level, level, a reactor reactor trip will:
A. result from a turbine trip AND when power is less than 10%, 10%, a reactor reactor trip will result from a turbine trip.
B. result from a turbine trip AND when power is less than 10%, a reactor trip will reactortrip NOT result from a turbine trip.
C. NOT result from a turbine trip AND when power is less than 10%, a reactor trip will result from a turbine trip.
D. NOT result from a turbine trip AND when power is less than 10%, a reactor trip will NOT result from a turbine trip.
Page 71 Page 71
TURKEY POINT TURKEY POINT NRCNRC EXAM EXAM - 05/09107 05/09/07 Q #36 Q#36 ANSWER:
ANSWER: A A
KA:
KA: 012K4.06 012K4.06 Knowledge of Knowledge of the the RPS RPS design design feature(
feature(s) and/or interlock(
s) and/or interlock(s)s) which which provide provide for for automatic or manual enable/disabl automatic or manual enable/disable of e of RPS RPS trips.
trips. 3.2/3.5 3.2/3.5 10CFR55:
10CFR55: 41.b.7 41.b.7
Reference:
Reference:
561 0-T-L1, Sheet 2, Sheet 17 5610-T-L1, 17 Cog Level:
Cog Level: Comprehension 2 Comprehension Level 2 because the operator must recognize that PT-447 failing high has no immediate affect on the RPS system but results in the inability to clear permissive P-7. Normally when turbine power reduces below 10%, the "At-Power" At-Power trips which include the turbine tripping the reactor are cleared. The clearing logic requires both PT-447 and PT-446 to be below 10%. With PT-447 failed high it cannot clear and At-Power trips remain instated at all power levels.
the "At-Power" New Question Response Analysis:
A. Correct per the reference. At the current power level, aa reactor trip will result from a turbine trip. When power is less than 10%, 10%, aa reactor trip will also result from aa turbine trip.
B. Incorrect because when power is <10%, turbine trip will be able to cause aa reactor trip. Plausible because aa turbine trip signal can presently presently cause aa reactor trip C. Incorrect Incorrect because aa turbine triptrip signal can presently presently cause aa reactor trip.
Plausible because when power is is <10%,
<10%, turbine trip will be be able to cause aa reactor trip.
trip.
D.
D. Incorrect Incorrect because because aa turbine trip signal turbine trip can presently signal can presently cause cause aa reactor trip trip and and because when power because when power is <10%,
is <10%, turbine trip will turbine trip will be be able able to to cause aa reactor reactor trip.
Plausible Plausible because the turbine because the turbine trip trip is is not not normally normally able able to to cause cause aa reactor reactor trip trip below 10% power.
below 10% power.
Page 72 Page 72
TURKEY POINT TURKEY POINT NRCNRC EXAM EXAM - 05/09107
- 05/09/07 Q#37 0#37 Unit 33 reactor Unit reactor power power isis at at 40%
40% with with all all systems systems in in normal normal alignment alignment except except for for NIS NIS power range power range channel channel N-41 N-41 which which isis OOS OOS withwith bistables bistables tripped tripped in in accordance accordance with with 3-ONOP-059.8, "Power 3-0NOP-059.8, Power Range Range Nuclear Nuclear Instrumentation Instrumentation Malfunction".
Malfunction.
Subsequently power Subsequently power range range channel channel N-42 fails low.
N-42 fails low.
Which ONE Which ONE ofof the the following following describes describes the the immediate immediate effect effect of of the the N-42 N-42 failure failure on on the RCS the RCS LoopLoop Low Low Flow Flow reactor reactor trip trip logic?
logic?
The RCS The RCS Loop Loop Low Low Flow Flow reactor reactor trip trip logic:
logic:
A. has NOT been changed by N-42 N-42 failing low and still requires low flow in 2 of 33 loops loops to trip the reactor.
reactor.
B. has NOT been changed by N-42 failing low and still requires low flow in 1I of 3 loops to trip the reactor.
C. has been changed by N-42 failing low to require low flow in 2 of 3 loops to trip the reactor.
D. has been changed by N-42 failing low to require low flow in 1I of 3 loops to trip the reactor.
Page 73 Page 73
TURKEY POINT TURKEY NRC EXAM POINT NRC EXAM - 05/09107
- 05/09/07 Q#37 Q#37 ANSWER:
ANSWER: AA KA:
KA: 012K6.02 Knowledge of the effect of a loss or malfunction Knowledge malfunction of the following will will have on the RPS: Redundant RPS: Redundant Channels. 2.9/3.1 IOCFR55:
10CFR55: 41.b.7 41.b.7
Reference:
0-T-L1, 561 O-T-L 1, Sheet 2, Sheet 17,17, Sheet 20 Cog Level: 2 Comprehension Level 2 because the operator must recognize that the throwing of N-41 bistables inserted a "power power above P-8" P-8 signal to the logic. When N-42 failed low it could not power above P-8" generate a "power P-8 signal, effectively disabling its input to the logic.
However the logic still recognizes inputs from N-43 and N-44 at 40% power and the loop low flow trip logic remains the same even though N-42 input has been disabled.
New Question Response Analysis:
A. Correct per the reference. the RCS Loop Low Flow reactor trip logic is NOT affected by N-42 failing low and is still 2 of 3 loops low flow to trip the reactor.
B. Incorrect because the RCS Loop Low Flow reactor trip logic was not affected by this N-42 failure. Plausible because the N-42 N42 input to the RCS Loop Low Flow reactor trip logic is disabled.
C. Incorrect because the RCS Loop Low Flow reactor trip logic was not affected by this N-42 failure. Plausible because the trip logic from N-41 was initially changed when the N-41 N-41 bistables were originally thrown but but that alone was not enough still not enough to change the overall logic from the original 22 of of 33 loops loops low low flow to trip.
D.
D. Incorrect because the P-8 loop low flow trips require 33 of 44 power range channels channels be be below below 10%
10% to be disabled.
to be disabled. Plausible because the reactor trip trip logic does disable logic does disable the the P-8 P-8 loop loop low low trips trips when << 45%
45% power.
power.
Page 74 Page 74
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07 05/09/07 Q #38 0#38 Operators are Operators are responding responding to to aa main main steam steam line line break break inside inside containment.
containment.
- - All safety systems functioned as designed.
- SI has been reset.
- Containment pressure peaked at 21 psig and is at 21 is now now 1717 psig.
- CNTMT ISOLATION H 5/2, "CNTMT ISOLATION ACTIVATED",
ACTIVATED, is in alarm
- As directed directed by Step Step 7 of 3-EOP-E-1, 3-EOP-E-1, "Loss Loss of Reactor Reactor or Secondary Secondary Coolant, the BOP resets Containment Isolation Coolant", Isolation Signals.
Which ONE of the following correctly describes the status of annunciator H 5/2 after the BOP resets Containment Isolation Signals?
Annunciator H 5/2 is:
A. still in alarm because Phase B relays cannot be reset under these conditions.
B. still in alarm because Containment Ventilation Isolation relays are still tripped.
C. NOT in alarm because the Phase A, and Phase B B relays are reset.
D. NOT in alarm because the Containment Ventilation, Phase A, and Phase B B relays are reset.
Page 75 Page 75
TURKEY POINT TURKEY POINT NRC EXAM - 05109107 NRC EXAM - 05/09/07 Q #38 Q#38 ANSWER:
ANSWER: BB KA:
KA: 013A4.02 013A4.02 Ability to Ability to manually manually operate operate and/or and/or monitor monitor in the control in the control room room reset reset of of ESFAS ESFAS channels. 4.3/4.4 channels. 4.3/4.4 IOCFR55:
10CFR55: 41.b.7, 41.b.9 41.b.7,41.b.9
Reference:
Reference:
4-EOP-E-1, Step 7 4-ARP-097.CR, H H 5/2 5/2 5610-T-L1, 5610-T-L Sht. 11 1, Sht. 11 Cog Level: Comprehension 2 Comprehension Level 2 because the operator must recognize that a steamline break inside containment will trigger Phase A & & B and Containment Ventilation Isolation.
Additionally the operator must recognize that the alarm is active when any of the 3 signals are present (not reset). It takes the reset of all 3 signals to clear the alarm.
New Question Response Analysis:
A. Incorrect because Phase B relays can be reset under these conditions.
Plausible because Annunciator H H 5/2 is still in alarm and procedures direct resetting Phase A & B.
B. Correct per the reference. Annunciator H H 5/2 is still in alarm because Containment Ventilation Isolation relays are still tripped.
C. Incorrect because Annunciator H H 5/2 is still in alarm. Plausible because both Phase A relays and Phase BB relays are reset.
D.
D. Incorrect Incorrect because Annunciator H H 5/2 is still in 5/2 is in alarm andand Containment Containment Ventilation relays are are not not reset. Plausible Plausible because both both Phase Phase A relays and and Phase B relays are reset.
Phase B relays are reset.
Page 76 Page 76
TURKEYPOINT TURKEY PONTNRCNRC EXAM EXAM 05/09107
- 05/09/07 Q #39 0#39 Operators are Operators are responding responding to to aa simultaneous simultaneous LOOP/LOCA LOOP/LOCA event. event.
to start.
Which ONE Which ONE of the following of the following describes describes the the status status of of the the Emergency Emergency Containment Containment Coolers (ECCs) after sequencing Coolers (ECCs) after sequencing isis complete?
complete?
3A ECC 3AECC 3B ECC 3B ECC 3C ECC 3CECC A.
A. de-energized de-energized running running running running B.
B. de-energized stopped running running C. running stopped de-energized D. running running running de-energized Page77 Page 77
TURKEY POINT TURKEY POINTNRC EXAM- 05109/07 NRC EXAM - 05/09/07 Q #39 Q#39 ANSWER:
ANSWER: C C
KA:
KA: 022K2.01 022K2.01 Knowledge of Knowledge of the power supplies the power supplies to to the the containment containment cooling cooling fans.
fans. 3.0/3.1 3.0/3.1 IOCFR55:
10CFR55: 41.b.8, 41.b.10 41.b.8,41.b.10
Reference:
Reference:
SD-029, Page SO-029, Page 15 15 5610-T-E-1 561 591, Sheet 0-T-E-1591, Sheet 1I 5613-T-L1, Sheet 12B 5613-T-L 1, Sheet 12B Cog Level:
Level: 2 Comprehension Comprehension Level 2 because the operator must recognize that the sequencers will auto-start their respective ECCsECCs if power to the bus is available. 3A ECC is powered from the B
"B" train (3B MCC, bkr 30650). 3C ECC is powered from the "A" A train 3C 30 MCC, bkr 30729). 3B ECC is powered from either train (swing bus) but does not get an auto start by the sequencer even though the bus will energize.
New Question Response Analysis:
A. Incorrect because 3C ECC is de-energized and 3B does not auto-start.
Plausible because 3A safeguards equipment is normally powered from 3A Train which is de-energized de-energized..
B. Incorrect because 3C ECC is de-energized de-energized.. Plausible because 3A safeguards equipment is normally normally powered from 3A Train which is de de-energized.
energized.
C.
C. Correct Correct per per the the references. 3A3A ECC ECC is is running, running, 3B 3B ECC ECC is is stopped, stopped, and and 30 3C ECC ECC is is de-energized de-energized..
D.
O. Incorrect Incorrect because because 3B3B ECC ECC does does notnot auto-start.
auto-start. Plausible Plausible because because 3A 3A ECC ECC is running is running and and 3C3C ECC is de-energized ECC is de-energized..
Page78 Page 78
TURKEYPOINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q #40 Q#40 Following aa large Following large break break LOCA, LOCA, operators operators have have transitioned transitioned to to 3-EOP-ES-1.3, 3-EOP-ES-1 .3, Transfer to
Transfer Cold Leg to Cold Leg Recirculation,"
Recirculation, and are at and are at Step Step 18 18 which which states, states, "Determine Determine SI system Piggy-Back Recirculation Requirements.
SI system Piggy-Back Recirculation Requirements."
The RO The RO reports reports the following plant the following conditions:
plant conditions:
- Containment pressure Containment pressure isis 12 psig.
12 psig.
- Containment temperature Containment temperature is 178°F.
is 178°F.
closed.
Which ONE of the following is correct regarding regarding subsequent Containment Containment Spray Pump (CSP) operation?
Operators will run:
A. No CSPs.
B. One CSP with suction provided directly from the RWST.
C. One CSP with suction provided from the discharge of the running RHR pump(s).
D. Two CSPs with suction provided from the discharge of the running RHR pump(s).
Page 79 Page 79
TURKEY POINT TURKEY POINT NRC EXAM - 05/09107 NRC EXAM - 05/09/07 Q #40 Q#40 ANSWER:
ANSWER: CC KA:
KA: 026K4.01 Knowledge of the CSS design feature(s) and/or interlock(s) which provide Knowledge provide for:
source source of water for CSS, including recirculation phase after LOCA 4.2/4.3 recirculation 10CFR55:
10CFR55: 41.b.7, 41.b.8 41.b.7,41.b.8
Reference:
3-EOP-ES-1.3, Steps 18, 3-EOP-ES-1.3, 21, 23, 25, 26 18,21,23,25,2 6 Cog Level: Comprehension 2 Comprehension Level 2 because the operator must recognize that one of the four criteria to discontinue CSP operation is not satisfied. Additionally the operator must recall pull-to-lock in Step 2 of EOP-ES-1.3 that one CSP was put in pull-to-Iock EOP-ES-1 .3 and must remain in pull-to-lock subsequently pull-to-Iock subsequently. . Finally the operator must recognize that subsequent procedure steps change the CSP suction source from the RWST to the discharge of the RHR pumps.
New Question Response Analysis:
A. Incorrect because 1 1 CSP must be run under these conditions. Plausible because 3 of the 4 listed parameters support not starting a CSP.
B. Incorrect because when a a CSP is subsequently started, cold leg recirculation will have been aligned. Plausible because up to this time the running CSP has been aligned to the RWST.
C. Correct per the reference D. Incorrect because one CSP was put in pull-to-lock pull-to-Iock earlier in EOP-ES-1 EOP-ES-1.3 .3 and it will remain in pull-to-lock.
pull-to-Iock. Plausible because the running CSP will have its suction provided from the discharge of the running RHR pump(s).
Page 80 Page 80
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 QQ#41
- 41 Operators are Operators are performing performing 3-EOP-E-1, 3-EOP-E-1, "Loss Loss of Reactor or of Reactor or Secondary Secondary Coolant" Coolant and and the following the following plant conditions exist:
plant conditions exist:
- Containment Temperature Containment Temperature is is 220°F 220°F
- Containment Pressure Containment Pressure is is 19 19 psig psig and and rising rising
- All Available Charging Pumps are running All Available Charging Pumps are running
- level is RWST level RWST is 220,000 gallons Containment Pressure has just increased to 21 psig. The operators entered 3-EOP-FR-Z.1, "Response 3-EOP-FR-Z.1, Response to High Containment Pressure" Pressure and and are are assessing Containment Spray pumps Containment pumps (CSPs)
(CSPs) status.
Which one of the following describes the correct plant and operator response?
A. Neither CSP auto-started.
Manually start both CSPs.
B. Neither CSP auto-started.
Manually start one CSP and place the other CSP in Pull-To-Lock.
Pull-To-Lock.
C. Both CSPs auto-started.
Verify both CSPs auto-started.
D. Both CSPs auto-started.
Manually stop one CSP and place it in Standby.
Page 81 Page 81
TURKEY POINT TURKEY POiNT NRC NRC EXAM EXAM - 05109/07
- 05/09/07 Q#41 Q #41 ANSWER:
ANSWER: AA KA:
KA: 026A1.O1 026A 1.01 Ability to predict Ability to predict and/or and/or monitor monitor changes changes inin parameters parameters (to(to prevent prevent exceeding exceeding design limits) design limits) associated associated with with operating operating the the CSS CSS controls controls including containment including containment pressure 3.9/4.2 pressure 3.9/4.2 IOCFR55:
10CFR55: 41.b.7, 41.b.8 41.b.7,41.b.8
Reference:
Reference:
5610-T-L1, 5610-T -L 1, Sheet 11 11 5613-T-L1, 5613-T-L Sheet 12A 1, Sheet 12A 3OEOP-E-O, Attachment 3, Step 12 30EOP-E-0, 12 3-EOP-FR-Z.1, Step 8 3-EOP-FR-Z.1, Cog Level: Comprehension 2 Comprehension Level 2 because the operator must analyze plant conditions and determine that both CSPs are needed but neither auto-started based on the sequencers having been reset when SI was reset in EOP-E-O as indicated by charging pumps running.
New Question Response Analysis:
A. Correct because neither CSP auto started because the sequencer was reset when the operators reset SI in E-O and both CSPs are needed lAW 3-EOP-FR-Z.1, Step 8 guidance.
B. Incorrect because both CSPs are needed lAW 3-EOP-FR-Z 3-EOP-FR-Z.1, .1, Step 88 guidance. Plausible because neither CSP auto-started because the sequencer was reset when the operators reset SI in E-O.
C. Incorrect because neither CSP auto-started. Plausible because operators are directed directed to verify both CSPs CSPs are running lAW 3-EOP-FR-Z 3-EOP-FR-Z.1, .1, Step 88 guidance.
D.
D. Incorrect Incorrect because because neither neither CSP CSP auto-started. Plausible Plausible because because operators operators are are directed directed to to manually stop one manually stop CSP and one CSP and place in Standby place itit in Standby ifif containment containment pressure pressure is is << 14 14 psig.
psig.
Page 82 Page 82
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09107
- 05/09/07 Q #42 0#42 Operators have Operators have responded responded to to aa small small break break LOCA LOCA with with aa LOOP LOOP onon Unit Unit 33 and and are are performing 3-EOP-ES-1.2, performing 3-EOP-ES-1 .2, Post-LOCA Post-LOCA Cooldown Cooldown and and Depressurization."
Depressurization.
The RO The RO is is preparing preparing to initiate an to initiate an RCS RCS cooldown cooldown to to Cold Cold Shutdown Shutdown by by dumping dumping steam from steam from intact intact steam steam generators.
generators.
Which ONE Which ONE of of the the following following describes describes the the BASIS BASIS for for the the step step that that directs directs the the RO RO to to limit steam flow limit steam flow rate rate to maintain the to maintain the allowable allowable cool cool down down rate rate below below 100°F/hr?
100°FIhr?
Excessive steam Excessive steam flow rate may may result result in:
in:
A. prolonged loss of RCS natural circulation flow.
B. challenging the integrity status tree for pressurized thermal shock limits.
C. automatic closure of the MSIVs which isolates the condenser steam dumps.
D. exceeding the capability of the AFW system to maintain S/G levels above 6% which will require stopping the cooldown.
Page 83 Page 83
TURKEYPOINT TURKEY POINTNRCNRCEXAM EXAM- 05109/07
- 05/09/07 Q #42 Q#42 ANSWER:
ANSWER: BB KA:
KA: 039K5.05 039K5.05 Knowledge Knowledge of of the the operational operational implications implicaUons of the following of the following concept concept as as itit applies applies to to the MRSS: Basis for the RCS cooldown limits the MRSS: Basis for the RCS cooldown limits 2.7/3.1 2.7/3.1 10CFR55:
10CFR55: 41.b.3, 41.bA, 41.b.3, 41.b.4, 41.b.5, 41.b.5, 41.b.10 41.b.1O
Reference:
Reference:
3-EOP-ES-1 .2 BO, 3-EOP-ES-1.2 BD, Step Step 6, 6,
Cog Level:
Cog Level: 11 Recall Recall New Question New Question Response Analysis:
Response
A.
A. Incorrect because excessive steam flow will not terminate RCS NC flow.
Plausible because excessive steam flow may temporarily impede NC flow.
B. Correct per the reference. Excessive steam flow rate may result in challenging the integrity status tree for pressurized thermal shock limits.
C. Incorrect because a LOOP is present and operators will be utilizing SOTA SDTA system instead of SOTC SDTC system and the setpoint to close the MSIVs is 40%
of full power steam flow rate which is higher than can be obtained with SOTA SDTA or SDTC SOTC systems. Plausible because the procedure warns against the possibility of inadvertently closing MSIV5MSIVs when dumping steam.
D.
O. Incorrect because this procedure does not require operators to stop dumping dumping steam ifif S/G S/G level level drops drops below 6%. Plausible below 6%. Plausible because because another another procedure procedure (Ex.
(Ex. ECA-0.0)
ECA-O.O) doesdoes require require stopping stopping thethe cooldown cooldown rate rate ifif SG SG levels levels drop drop below 6%.
below 6%.
Page84 Page 84
TURKEYPOINT TURKEY POllTNRCNRC EXAM EXAM - 05/09/07
- 05/09/07 Q #43 0#43 Unit 44 iss at Unit at 80%
80% power power with with all all systems systems inin auto.
auto. The The 4A 4A S/G SIG pressure pressure transmitter, transmitter, associated with associated with the the controlling controlling S/G steam flow S/G steam flow transmitter, transmitter, failed failed LOW.
LOW.
Which ONE Which ONE of of the the following following describes describes the the immediate immediate effect effect on on the:
the:
1)
- 1) 4A4A S/G S/G steam steam flow signal to flow signal to the the. feed feed regulating regulating valve valve controller controller AND AND 2)
- 2) 4A feed regulating 4A feed regulating valve valve AND AND 3)
- 3) 4A SIG level?
4A S/G level?
A. 1) steam
- 1) steam flowflow signal signal decreases decreases
- 2) feed regulating valve
- 2) feed regulating valve opens opens level increases
- 3) S/G level increases B.
B. 11)) steam flow signal decreases
- 2) feed regulating valve closes
- 3) S/GSIG level decreases C. 1) steam flow signal increases
- 2) feed regulating valve opens SIG level increases
- 3) S/G D. 1) steam flow signal increases
- 2) feed regulating valve closes
- 3) S/G level decreases Page 85 Page 85
TURKEY POINT TURKEY NRC EXAM POllJT NRC EXAM - 05/09107
- 05/09/07 Q #43 Q#43 ANSWER:
ANSWER: BB KA:
KA: 059K1 .03 059K1.03 Knowledge of Knowledge of the the physical physical connection connection and/or and/or cause-effect cause-effect relationships relationships between between the main feedwater and the S/Gs.
the main feedwater and the S/Gs. 3.1/3.3 3.1/3.3 10CFR55:
10CFR55: 41.b.4, 41.b.7 41.bA, 41.b.7
Reference:
Reference:
5610-T-D-17, Sheet 5610-T-0-17, Sheet 11 5610-T-D-18B, Sheet I 5610-T-0-18B,Sheet1 SD-Il, Page SO-11, Page 3232 Cog Level:
Cog Comprehension 2 Comprehension Level 2 because the operator must realize that when the pressure density compensation input to the steam flow signal fails low, the result is the steam flow compensation signal to the feed reg valve controller also goes low. Steam flow is compared to feed flow and the resulting imbalance causes the feed reg valve to go closed with a resulting drop in S/G level.
New Question Response Analysis:
A. Incorrect because for this failure the steam flow signal decreases, the feed reg valve closes and the S/G level decreases. Plausible because the steam flow signal will decrease.
B. Correct per the references. 4A S/G steam flow signal decreases, feed reg valve closes and S/G level decreases.
C. Incorrect because for this failure the steam flow signal decreases, decreases, the feed reg valve closes and the S/G level decreases. Plausible because this response provides provides an accurate description description ofof the effect of the pressure pressure input input failing high D.
O. Incorrect Incorrect because because for this this failure the the steam steam flow signal signal decreases, decreases, the the feed reg valve reg valve closes closes and and the the S/G S/G level level decreases.
decreases. Plausible Plausible because because the the feed reg valve reg valve will will close close and and the the S/G S/G level level will will decrease.
decrease.
Page 86 Page 86
TURKEYPOINT TURKEY POINTNRC EXAM- 05/09/07 NRC EXAM - 05/09/07 Q #44 0#44 Unit 44 isis operating Unit operating at at 40%
40% power power with with all all systems systems inin automatic automatic operation.
operation.
- TheThe sensing sensing line for first line for first stage stage pressure pressure transmitter, transmitter, PT-4-446, PT-4-446, which which isis selected for selected for control, control, shears shears off off at at the connection to the connection to the the pressure pressure transmitter.
transmitter.
- Several Several minutes minutes later, later, the the BOP BOP selects selects PT-4-447 PT-4-447 as as the the controlling controlling channel channel as directed by the procedure.
as directed by the procedure.
Which ONE Which ONE of of the the following following describes describes the response of the response of S/G SIG levels levels assuming assuming S/GSIG level control level control is is maintained maintained in in automatic automatic throughout throughout the the entire entire evolution?
evolution?
levels will lower All S/G levels lower from:
A. 50% and stabilize at 40% and then return to 50%.
B. 60% and stabilize at 50% and then return to 60%.
c.
C. 50% continuously until PT-4-447 PT4-447 is selected and then rise to 40%
D. 60% continuously until PT-4-447 is selected and then rise to 50%
Page 87 Page 87
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q #44 Q#44 ANSWER:
ANSWER: B B
KA:
KA: 059A3.02 monitor automatic operation of the MFW, Ability to monitor MFW, including including programmed programmed levelslevels of of the S/G.
the S/C. 2.9/3.1 2.9/3.1 IOCFR55:
10CFR55: 41.b.4, 41.b.7 41.b.4,41.b.7
Reference:
5610-T-D-17 Sheet 11 5610-T-D-18A Sheet 11 Cog Level: 3 Analysis Level 3 because the operator must recognize that when PT-446 is selected for control, it is providing programmed level input to the S/G S/C level control program. A sheared sensing line will cause the pressure transmitter to call for a 0% power S/G level of 50%. At 40% power, the desired programmed level has just increased to 60%. When PT-446 fails low, the programmed level input changes to 50% and not o0 %. Feed reg valves respond and level drops to 50% on all S/Gs. Operator must know that even though failed low, the control loop is limited at 50% level or the level would continue to decrease. They then must realize that when PT-4-447 is selected, the SG SC level control system will return level back to 60%.
New Question Response Analysis:
A. Incorrect because S/G S/C levels will lower from 60% when at 40% power and will stabilize at 50% and then return to 60% when PT-4-447 is selected.
Plausible because at lower power the levels program level is 50%.
B. Correct per the reference. S/C S/G levels will lower from 60% and stabilize stabilize'at at 50% and then return to 60%.
C. Incorrect because S/G levels will lower from 60% and will stabilize at 50%
which is the low level limit, itit will not not continuously decrease, decrease, and it will return to 60%
60% when PT-4-447 is selected selected not not 40%.
40%. Plausible because other instrument failures could cause S/C S/G levels to rise continuously until aa turbine trip occurs.
D.
D. Incorrect Incorrect because because S/CS/G levels levels will lowerlower from 60%60% and and will stabilize stabilize at at 50%
50%
which is the low level limit, itit will is the low level limit, will not not continuously continuously decrease, decrease, and and then then return to 60% 50%) when PT-4-447 60% (not 50%) PT-4-447 is is selected. Plausible because other instrument instrument failures failures (ie. Level faililing (ie. Level faililing high) high) could could cause cause S/C S/G levels levels to to lower lower continuously continuously until until aa reactor trip trip occurs.
occurs.
Page 88 Page 88
TURKEY POINT TURKEY POiNT NRC NRC EXAMEXAM - 05/09/07
- 05/09/07 Q #45 0#45 With Unit With Unit 44 at at 30% power during 30% power during aa plant plant startup, startup, the the RO RO discovers discovers the the running running Steam Generator Steam Generator Feed Feed Pump Pump (SGFP)
(SGFP) start/stop start/stop handhand switch switch in in the the green-flagged green-flagged position.
position.
Which ONE Which ONE of of the the following following describes describes the the consequences consequences of of this this condition?
condition?
A.
A. An auto-start An auto-start signal signal for for the the AFW AFW system system is is disabled.
disabled.
B.
B. auto-start signal An auto-start signal for the standby standby condensate condensate pump pump is is disabled.
disabled.
C.
C. The idle The idle SGFP SGFP will will NOT NOT auto-start auto-start ifif the the running running SGFP SGFP trips.
trips.
D. The SGFP recirculation valves will NOT auto-open if the running SGFP trips.
Page 89 Page 89
TURKEYPOINT TURKEY POINTNRC EXAM- 05/09107 NRC EXAM - 05/09/07 Q #45 Q#45 ANSWER:
ANSWER: AA KA:
KA: 061K4.02 061K4.02 Knowledge of Knowledge of the the AFW AFW design design feature(s) feature(s) and/or and/or interlock(s) interlock(s) which which provide provide for:
for: AFW AFW automatic start upon loss of MEW pump, automatic start upon loss of MFW pump, S/G S/G level, level, blackout or SI.
blackout or SI. 4.5/4.6 4.5/4.6 10CFR55:
10CFR55: 41.b.4, 41.b.7 41.bA, 41.b.7
Reference:
Reference:
5610-T-L1, Sheet 5610-T-L1, Sheet 15, 15, Notes Notes 1I and and 55 Cog Level:
Cog Level: 1I Recall Recall New Question New Response Analysis:
A. Correct per the reference. An auto-start signal for the trip of the last running MFPt0 the AFW system has been disabled.
MFPto B. Incorrect because the Condensate pump auto-start feature is unaffected by this event. Plausible because Condensate pumps do have auto-start features but they are affected by the status of other Condensate pumps, not SGFPs.
C. Incorrect because the idle SGFP not starting is not aa consequence of the green-flag condition. Plausible because the idle SGFP will not auto-start if the running SGFP trips D.
D. Incorrect Incorrect because the SGFP SGFP recirc valves will auto-open auto-open ifif the running SGFP SGFP trips. Plausible because at slightly slightly lower power levels, the recirc valves will have have auto-opened even even with the the SGFP SGFP running.
running.
Page90 Page 90
TURKEY POINT TURKEY POINTNRC NRC EXAM EXAM - 05109/07
- 05/09/0 7 Q #46 0#46 Unit 33 isis at Unit at 100%
100% power power with with all all systems systems in in normal normal alignment.
alignment.
The 3C The main steam 30 main steam line non-return check line non-return check valve valve body body ruptures ruptures resulting resulting in in aa large large Main Steam Main Steam Line Line Break Break (MSLB)
(MSLB) at at the the 3C 3C non-return non-return check check valve.
valve.
Which ONE Which ONE of of the following describes the following describes the the automatic automatic response response of of the the AFW AFW system?
system?
A.
A. Only 3A Only 3A and and 3B 3B AFW AFW pumps pumps startstart and deliver flow.
and deliver flow.
390 gpm total AFW flow will be 390 be delivered to to all S/Gs.
S/Gs.
B.
B. Only 3A Only 3A and and 3C 3C AFW pumps pumps startstart and and deliver deliver flow.
780 gpm total AFW flow will be delivered to all S/Gs. SIGs.
C. Only 3B and 3C 30 AFW pumps start and deliver flow.
390 gpm total AFW flow will be delivered to all S/Gs. SIG5.
D. All AFW pumps start and deliver flow.
780 gpm total AFW flow will be delivered to all S/Gs.
Page 91 Page 91
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09107
- 05/09/07 Q#46 Q#46 ANSWER:
ANSWER: 0D KA:
KA: 061A3.01 monitor automatic operation of the AFW, including:
Ability to monitor including: AFW startup and flows. 4.2/4.2 IOCFR55: 41.bA, 10CFR55: 41.b.4, 41.b.7, 41.b.8
Reference:
Reference:
5613-M-3072, Sheet 11 5610-T-L11 Sheet 11 5610-T-L 5610-T-L1 561 O-T-L 1 Sheet 1515 SD-117, Pages, 10, SO-117, 10, 1717 & 18 Cog Level: 3 Analysis/Application Level 3 because the operator must analyze the following to come to the correct conclusion. A steam line break at the 3C non-return valve will not cause the 3C S/G to blow dry because the 3C MSIV will close. SI actuates due to Hi steamline flow with low Tavg/ low SG pressure when all 3 S/Gs feed the break at the 3C non-return valve. This SI signal closes all 3 MSIVs. Both trains of AFW get a start signal due to SI. With all 3 S/Gs pressurized, all AFW pumps auto start and provide flow to all S/Gs. The AFW flow controllers are preset at 130 gpm each. 130 gpm X 6 AFW reg valves = = 780 gpm.
New Question Response Analysis:
A. Incorrect because all AFW pumps start and deliver flow. 780 gpm total AFW flow will be delivered to all S/Gs. Plausible if the operator assumes the faulted 3C S/G blows down and 3C S/G is providing steam supply to the 3C AFW pump.
B. Incorrect because all AFW pumps start and deliver flow. Plausible if the operator recognizes 3A and 3C AFW pumps are in different different trains. In In that case 780 gpm total AFW flow will be delivered to all S/Gs.
C. Incorrect because all AFW pumps start and deliver flow. 780 gpm total AFW flow will be delivered to all S/Gs.
S/Gs. Plausible if the operator assumes the 3C SIG faulted 3C S/G blows blows down.
down. 3A 3A AFW pump pump would lose lose its its steam steam supply supply and and 390 gpm 390 total AFW flow would gpm total would be be delivered delivered toto all all S/Gs.
S/Gs.
D.
O. Correct per the references. All AFW Correct per AFW pumps startstart and and deliver deliver flow.
780 gpm 780 gpm total total AFW AFW flow flow will will be be delivered delivered to to all all SIGs.
S/Gs.
Page 92 Page 92
TURKEY POINT TURKEY POINTNRCNRC EXAMEXAM - 05/09107
- 05/09/07 Q #47 Q#47 Tech Spec Tech Spec 3.8.1.1, 3.8.1 .1, AC AC Power Power Sources, Sources, allows allows aa unit unit to to continue continue power power operation operation at at less than less than 30% power for 30% power for up up to to 30 days ifif its 30 days its Startup Startup Transformer Transformer becomes becomes iperable.
Which ONE Which ONE of of the following describes the following describes the the BASI.S BASI.S for for allowing allowing continued continued operation operation at less at less than than 30% power?
30% power?
At 30%
At power:
30% power:
A. the two the two loop low flow loop low flow /I two two RCP RCP breaker breaker open open reactor reactor trip trip logic logic has has been been instated providing instated providing additional additional reactor reactor protection protection in in the the event event of of aa LOOP.
LOOP.
B. SIG pressure is S/G is greater than full power S/G pressure providing additional motive force to the steam driven AFW pumps in the event of AFW actuation.
C. fewer components are loaded onto the 4KV Buses and Load Centers resulting in lower bus and load center operating temperatures. temperatures.
D. decay heat has been reduced, automatic feedwater control can be maintained and the RCPs continue to run.
Page 93 Page 93
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05109/07
- 05/09/07 Q #47 Q#47 ANSWER:
ANSWER: DD KA:
KA: 062G2.2.25 062G2.2.25 As As itit relates relates to to the the AC AC Electrical Electrical Distribution:
Distribution: Knowledge Knowledge of of the bases in the bases in Tech Tech Specs for Specs for LCOs LCOs and and safety safety limits.
limits. 2.5/3.7 2.5/3.7 100FR55:
10CFR55: 41.b.1, 41.b.5, 41.b.7, 41.b.l, 41.b.5, 41.b.7, 41.b.8 41.b.8
Reference:
Reference:
0-ADM-536, Page Page 94; Section 3/4.8.1 3/4.8.1 Cog Level:
Cog Level: 1I Recall Recall Bank Question Response Analysis:
A. Incorrect because the basis for allowing continued operation at 30% power is decay heat has been reduced, automatic feedwater control can be maintained and natural natural. circulation conditions are avoided by staying at power and not shutting down. Plausible because at 30% power, the two loop low flow 1 / two RCP RCP breaker open reactor trip logic has been instated.
B. Incorrect because the basis for allowing continued operation at 30% power is decay heat has been reduced, automatic feedwater control can be maintained and natural circulation conditions are avoided by staying at power and not shutting down. Plausible because at 30% power, S/G pressure is greater than full power S/G pressure.
C. Incorrect because the basis for allowing continued operation at 30% power is decay heat has been reduced, automatic feedwater control can be maintained and natural natural circulation conditions are avoided by staying at power and not shutting down. down. Plausible because at 30% power, power, fewer components are loadedloaded onto the 4KV4KV Buses and and Load Centers.
Centers.
D.
D. Correct Correct per per the reference Page 94 Page 94
TURKEYPOINT TURKEY POINTNRC EXAM- 05/09107 NRC EXAM - 05/09/07 Q #48 0#48 Both Units are Both Units are at at 100%
100% power power with with normal normal system system alignments alignments except for 40 except for 4D MCC MOO which isis out which out of of service.
service.
Subsequently the Subsequently feeder breaker the feeder breaker toto 3C 30 MCC MOO trips trips open, open, de-energizing de-energizing 3C 30 MCC.
MOO.
Which ONE Which ONE ofof the the following following describes describes the the effect effect on on the the Vital Vital DC DO electrical electrical system?
system?
A.
A. 3A DC 3A DO Bus Bus can can only only be expected to be expected maintain voltage to maintain voltage to to shutdown shutdown loads loads above 120 above volts for 120 volts for four four hours.
hours.
B.
B. 3A DC 3A DO Bus Bus can can only only be be expected expected to maintain voltage to maintain voltage to to shutdown shutdown loads loads above 105 105 volts for two hours.
0.
C. 3B DCDO Bus can only be expected to maintain voltage to shutdown loads above 120 volts for four hours.
D. DO Bus can only be expected to maintain voltage to shutdown loads 3B DC above 105 volts for two hours.
Page95 Page 95
TURKEYPOINT TURKEY POINTNRC NRC EXAM EXAM- 05/09107
- 05/09/07 Q #48 Q#48 ANSWER:
ANSWER: BB KA:
KA: 063K1.03 063K1.03 Knowledge of Knowledge of the the physical physical connection connection and/or and/or cause-effect cause-effect relationships relationships between between the DC Electrical Distribution the DC Electrical Distribution and theand the battery battery charger charger and and battery.
battery. 2.9/3.5 2.9/3.5 10CFR55:
10CFR55: 41.b.4, 41.b.7, 41.bA, 41.b.7, 41.b.8 41.b.8
Reference:
Reference:
5610-T-E-1 561 592 Sheet 0-T-E-1592 Sheet 1I SD-i 44, Page SD-144, Page 99 Cog Level:
Cog Level: 22 Comprehension Comprehension Level 2 because the operator must recognize that 4D MCC is the power supply supply to battery charger and 3C MCC the 3A2 battery MCC is is the power power supply to the 3A 3A11 battery battery charger. Loss of both results in no battery chargers for the 3A DC Bus. The operator must then recall that the 3A battery is sized to maintain voltage to shutdown loads above 105 volts for two hours.
New Question Response Analysis:
A. Incorrect because 3A DC Bus can only be expected to maintain voltage to shutdown loads only above 105 volts for only two hours. Plausible because it is the 3A DC Bus which is affected.
B. Correct per the reference C.
C. Incorrect Incorrect because the 3A DC DC Bus Bus is is the affected bus. Plausible Plausible because 120 120 volts is the approximate normal voltage for all DC DC buses.
D.
D. Incorrect Incorrect because the 3A 3A DC DC Bus Bus is is the affected bus.
bus. Plausible Plausible because because 3A 3A DC Bus DC Bus can can only only be be expected expected to to maintain maintain voltage voltage toto shutdown shutdown loads loads above above 105 105 volts for two volts for two hours.
hours.
Page 96 Page 96
TURKEY POINT TURKEY POINT NRC EXAM - 05/09/07 NRC EXAM - 05/09/07 Q #49 0#49 Unit 33 isis in Unit Mode 33 when in Mode when the the input input breakers breakers to vital DC to vital DC buses buses 3023 3D23 and and 3D23A 3D23A trip trip open deenergizing open deenergizing the the DC DC buses.
buses.
Which ONE Which ONE of of the following describes the following describes thethe effect effect on on the Unit 33 EDG(s)?
the Unit EDG(s)?
A.
A. 3A EDG 3A EDG has has lost lost control control and and field field flashing flashing power.
power.
3A EDG 3A EDG does does NOT NOT have have black black start start capability.
capability.
B.
B. 3B EDG 3B EDG has has lost lost control control and and field flashing power.
power.
3B EDG does NOT NOT have have black black start start capability.
C. 3A EDGEDG has lost control and field flashing power.
3A EDG is still black start capable.
D. 3B EDG has lost control and field flashing power.
3B EDG is still black start capable.
Page 97 Page 97
TURKEY POINT TURKEY POINT NRC EXAM - 05/09107 NRC EXAM - 05/09/07 Q #49 Q#49 ANSWER:
ANSWER: BB KA:
KA: 064K2.03 064K2.03 EDGs - Knowledge EDGs - Knowledge of the power of the power supplies supplies to to the the control control power.
power. 2.9/3.3 2.9/3.3 100FR55:
10CFR55: 41.b.4, 41.b.7, 41.b.4, 41.b.7, 41.b.8 41.b.8
Reference:
Reference:
3-ONOP-003.5, Step 3-0NOP-003.5, Step 3.5 3.5 &
& Attachment Attachment 3, 3, Bkr Bkr 3D23A-28 3D23A-28 Cog Level:
Cog Level: 1I Recall Recall New Question Response Analysis:
A. Incorrect because 3B EDG has lost control and field flashing power.
Plausible because 3A EDG does not have black start capability.
B. Correct per the reference C. Incorrect because 3B EDG has lost control and field flashing power and because 3A EDG does not have black start capability. Plausible because both Unit 4 EDGs have black start capability.
D. Incorrect because 3B EDG does not have black start capability. Plausible because 3B EDG has lost control and field flashing power.
Page 98 Page 98
TURKEY POINT TURKEY POiNT NRC EXAM - 05/09107 NRC EXAM 05/09/07 Q #50 0#50 Operators are Operators are performing performing the the monthly monthly test test run run of of the the 3A 3A EDG EDG using using 3-0SP-023.1 3-OSP-023.1,,
Diesel Generator "Diesel Generator Operability Operability Test."
Test.
The BOP The SOP isis attempting attempting to verify 3A to verify 3A EDG EDG isis in in LAG.
LAG.
He momentarily He momentarily positions positions the the diesel diesel generator generator voltage regulator in voltage regulator in RAISE.
RAISE.
Assuming the 3A EDG is in the LAG, which ONE of the following describes the EDG response and subsequent operator actions required to verify the EDG is in LAG?
LAG?
3A EDG amps:
A. increased.
Slowly lower EDG voltage until amps stop decreasing and start to increase.
Then slowly raise EDG voltage until amps increase.
B. increased.
Slowly raise EDG voltage until amps stop increasing and start to decrease.
Then slowly lower EDG voltage until amps increase.
c.
C. decreased.
Slowly lower EDG voltage until amps stop decreasing and start to increase.
Then slowly raise EDG voltage until amps decrease.
D. decreased.
Slowly raise EDG voltage until amps stop decreasing and start to increase.
Then slowly lower EDG voltage until amps decrease.
Page 99 Page 99
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q #50 Q#50 ANSWER:
ANSWER: A A KA:
KA: 064G2.1.23 064G2.1.23 As it relates As relates to the EDG, EDG, ability to perform specific system and integrated integrated plant plant modes of plant operation.
procedures during all modes operation. 3.9/4.0 IOCFR55:
10CFR55: 41.b.4, 41.b.7 41.bA,41.b.7
Reference:
3-OSP-023.1, Step 7.1.2.29.k 3-0SP-023.1, Cog Level: 11 Recall New Question Response Analysis:
A. Correct per the reference B. Incorrect because the operator should subsequently slowly lower EDG voltage until amps stop decreasing. Plausible because 3A EDG amps increased.
C. Incorrect because 3A EDG amps increased. Plausible because the operator should slowly lower EDG voltage until amps stops decreasing.
D. Incorrect because 3A EDG amps increased and because the operator should slowly lower EDG voltage until amps stop decreasing. Plausible because if the EDG is in the LEAD, the subsequent operator action would be to subsequently raise the EDG voltage.
Page 100 Page 100
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM 05/09/07
- 05/09/07 Q#51 0#51 Unit 33 is Unit is at at 100% power with 100% power with all all systems systems in normal alignment in normal alignment when when the the following following occur; occur;
- Annunciator H Annunciator H 1/4, 1/4, PRMS PRMS HI HI RADIATION, RADIATION, alarms.
alarms.
- Annunciator H Annunciator H 1/6, 1/6, PRMS PRMS CHANNEL CHANNEL FAILURE, FAILURE, alarms.
alarms.
- Steam Generator Liquid Sample Monitor, R-3-19, Steam Generator Liquid Sample Monitor, R-3-19, fail lamp lamp on on the PRMS PRMS drawer isis illuminated illuminated
- R-3-1 9 display and recorder reading are failed HIGH R-3-19
- R-3-19 WARN lamp is ON and HIGH ALARM lamp is ON.
Which ONE of the following describes the plant response and the correct initial initial operator response?
A. S/G blowdown does NOT automatically isolate.
Manually secure Blowdown.
B. S/G blowdown does NOT automatically isolate.
Re-align the discharge to the main condenser.
C. S/G blowdown has automatically isolated.
Verify S/G blowdown flow control valves, FCV-6278 A, B, & C and blowdown LCV-3-6265B are closed.
tank to canal level control valve, LCV-3-6265B D. S/G blowdown has automatically isolated.
Verify S/G blowdown isolation valves, MOV-6275 A, B, & & C and S/G liquid sample valves MOV-1425/1426/1427 MOV-1 425/1 426/1 427 are closed.
Page 101 Page 101
TURKEY POINT TURKEY POINT NRC EXAM - 05/09/07 NRC EXAM 05/09/07
- 51 Q #51 Q
ANSWER:
ANSWER: CC KA:
KA: 073A2.02 073A2.02 Ability to Ability to (a)
(a) predict predict the the impacts impacts of the following of the following malfunctions malfunctions or or operations operations onon the the PRMS and (b) based on those PRMS and (b) based on those predictions,predictions, use use procedures procedures to to correct, correct, control, control, or or mitigate the mitigate the consequences consequences of of those those malfunctions malfunctions oror operations:
operations: detector detector failure.
failure.
2.7/3.2 2.7/3.2 IOCFR55:
10CFR55: 41.b.1O, 41.b.11, 41.b.12, 41.b.13 41.b.10,
Reference:
Reference:
3-ONOP-071 .2, Step 3-0NOP-071.2, Step 33 RNO RNO 3-ARP-097.CR, H1/6, Step 2f.
3-ARP-097.CR, Cog Level: 11 Recall New Question Response Analysis:
A. Incorrect because S/G SIG blowdown has automatically isolated. Plausible because if blowdown had not automatically isolated, ONOP-071.2 ONOP-071 .2 would direct the operator to manually isolate blowdown.
B. Incorrect because S/G SIG blowdown has automatically isolated. Plausible because if blowdown had not automatically isolated, re-aligning the discharge to the main condenser would preclude any chance of subsequent radioactive release to the environment via that .blowdown blowdown path.
C. Correct per the references. S/G blowdown has automatically isolated.
S/G blowdown flow control valves, FCV-6278 A, B, & C C and blowdown tank to canal level control valve, LCV-3-6265 LCV-3-6265B closed ..
B have closed..
D. Incorrect because SIG S/G blowdown isolation valves, MOV-6275 A, B, & C C and S/G liquid SIC liquid sample valves MOV-1 425/1 426/1 427 are not MOV-1425/1426/1427 not the correct valves to verify closed.
closed. Plausible because of the valve nomenclature (Blowdown Isolation Isolation Valves)
Valves) and because because S/G S/G blowdown has has automatically automatically isolated.
isolated.
Page 102 Page 102
TURKEY POINT TURKEY PO11T NRC EXAM - 05/09/07 NRC EXAM - 05/09/07 Q #52 0#52 Unit 44 operators Unit operators are are responding responding to to aa loss loss of Intake Cooling of Intake Cooling Water Water (ICW).
(ICW).
Which ONE Which ONE ofof the the following following identifies identifies plant plant conditions conditions that that will will require require operators operators to to trip Unit trip Unit 44 reactor reactor and and turbine?
turbine?
A.
A. Exciter hot Exciter air temperature hot air temperature increases increases to:to: 80°C B.
B. Turbine bearing Turbine bearing temperature temperature increases increases to: to: 160°F C.
C. CCW temperature CCW temperature increases increases to:
to: 130°F D. TPCW temperature increases to: 105°F Page 103 Page 103
TURKEY POINT TURKEY POiNTNRC NRC EXAM - 05/09/07 EXAM - 05/09/07 Q #52 Q#52 ANSWER:
ANSWER: CC KA:
KA: 076A1.02 076A 1.02 Ability to Ability to predict predict and/or and/or monitor monitor changes changes in in parameters parameters (to(to prevent prevent exceeding exceeding design limits) associated with operating the Service design limits) associated with operating the Service Water Water controls controls including including reactor reactor and turbine and turbine building building closed closed cooling cooling water water temperatures.
temperatures. 2.6/2.6 2.6/2.6 IOCFR55:
10CFR55: 41.b.4, 41.b.5, 41.bA, 41.b.5, 41.b.8 41.b.8
Reference:
Reference:
4-QNQP-019 FO 4-0NOP-019 EQ Page Page 4-QNQP-019, Page 4-0NOP-019, Page 12, 12, Step Step 10 10 4-ARP-097.C 4-ARP-097.CR, R, E 9/4, Page 288 Cog Level: 11 Recall New Question Response Analysis:
A. Incorrect because reactor trip is not required until exciter air temperatures increase beyond 90°C. Plausible because exciter air temperatures should increase during this event.
B. Incorrect because reactor trip is not required until turbine bearing temperatures increase beyond 180°F. Plausible because turbine bearing temperatures should increase during this event.
C. Correct per the references.
D. Incorrect because removing load/reactor trip is not required until TPCW temperatures increase beyond 110°F. 110°F. Plausible because TPCW temperatures should increase during this event. event.
Page 104 Page 104
TURKEY POINT TURKEY POINTNRC EXAM - 05109/07 NRC EXAM - 05/09/07 Q #53 0#53 Unit 33 operators Unit operators are responding to are responding to decreasing decreasing Instrument Instrument AirAir (IA)
(IA) Pressure.
Pressure.
In accordance In accordance with with O-ONOP-013, 0-ONOP-Ol 3, "Loss Loss of of Instrument Instrument Air",
Air, which which ONEONE ofof the the following describes following describes the the PROCEDURAL PROCEDURAL REQUIREMENTS REQUIREMENTS for for the the use use of of Service Service AirAir as backup to as backup to the the IA IA System?
System?
Service Air Service Air valves valves maymay be be opened:
opened:
A. regardless of IA regardless IA pressure pressure but but only after after all all available instrument instrument airair compressors have compressors have been been started.
started.
B. if IA pressure drops below 95 psig 9 regardless of the number of available psi instrument air compressors started.
instrument c.
C. if IA pressure drops below 95 psig and no IA compressors can be started D. as backup to IA without restrictions associated with IA pressure or starting of available IA compressors.
Page 105 Page 105
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09107
- 05/09/07 Q#53 Q#53 ANSWER:
ANSWER: CC KA:
KA: 078K1 .02 078K1.02 Knowledge of Knowledge of the physical connection the physical connection and/or and/or cause-effect cause-effect relationships relationships between between the Instrument the Instrument airair and and the the service service air. 2.7/2.8 air. 2.7/2.8 10CFR55:
10CFR55: 41.b.4, 41.b.1 41.b.4, 41.b.100
Reference:
Reference:
0-ONOP-013, Steps 3 and 4 O-ONOP-013, Level:
Cog Level: 11 Recall Recall New Question Response Analysis:
A. Incorrect because Service Air valves may be opened only if IA pressure drops below 95 psig and no IA compressors can be started. Plausible because service air valves may be opened after any available instrument air compressors have been started B. Incorrect because Service Air valves may be opened only if IA pressure drops below 95 psig and no IA compressors can be started. Plausible because service air valves may be opened if IA pressure drops below 95 psig.
C. Correct per the references. Service Air valves may be opened only if IA pressure drops below 95 psig and no IA compressors can be started.
D. Incorrect because Service Air valves may be opened only if IA pressure drops below 95 psig and no IA compressors can be started. Plausible because service air valves are opened as backup to instrument air.
Page 106 Page 106
TURKEY POINT TURKEY NRC EXAM POINT NRC EXAM - 05109107
- 05/09/07 Q #54 0#54 The plant The plant was operating at was operating at 100%
100% power power when:
when:
- A small A small break break LOCA LOCA has has occurred.
occurred.
level.
- Phase "A" Phase A was was NOT NOT manually manually actuated actuated following following the the manual manual SISI actuation.
actuation.
psig.
- Phase "B" B was NOT manually actuated following the increase in containment containment pressure.
pressure.
Based upon the above conditions which ONE of the following describes the status of the containment isolation signals that should have occurred?
A. Only Phase "A"A containment isolation B. Only Phase "B"B containment isolation C. Neither Phase "A"A or Phase "B" B containment isolations D. Both Phase A"A" and Phase B"B" containment isolations Page 107 Page 107
TURKEYPOINT TURKEY POINTNRCNRC EXAM EXAM- 05/09/07
- 05/09/07 Q #54 Q#54 ANSWER:
ANSWER: DD KA:
KA: 103K4.06 103K4.06 Knowledge of Knowledge of the the Ctmt Ctmt design design feature(s) feature(s) and/or and/or interlock(s) interlock(s) which which provide provide for for containment isolation containment isolation system system 3.1/3.7 3.1/3.7 IOCFR55:
10CFR55: 41.b.7, 41.b.9 41.b.7,41.b.9
Reference:
Reference:
5610-T-L1 5610-T Sheet 11
-L 1 Sheet 11 Cog Level:
Cog Level: 22 Comprehension Comprehension Level 22 because Level because the operator operator must must recognize recognize that aa manual manual SI SI does does not not actuate actuate Phase A. He then must analyze the plant condition to determine that an automatic SI has occurred and that this will actuateactuate a Phase A. If containment containment pressure pressure increases increases above 20 psig, a Phase B isolation Phase isolation signal will still be generated even ifif itit is not manually initiated.
New Question Response Analysis:
A. Incorrect because Phase "A" A and Phase "B" B containment isolations have automatically actuated. Plausible because Phase "A" A containment isolation has occurred.
B. Incorrect because Phase A "A" and Phase B "B" containment isolations isolations have automatically actuated. Plausible because Phase B "B" containment isolation has occurred.
C. Incorrect because Phase A "A" and Phase B "B" containment isolations have automatically actuated.
automatically actuated. Plausible Plausible ifif the the operator operator does does notnot realize realize that that manual manual initiation of Phase initiation of Phase AA and and Phase Phase BB areare not not required ifif the auto auto-initiation initiation signals signals are are present.
present.
D.
D. Correct Correct per per the the reference.
reference. Both Both Phase Phase A "A" and and Phase Phase B "B" containment containment isolations isolations have have automatically automatically actuated actuated Page 108 Page 108
TURKEY POINT TURKEY POINTNRC NRC EXAM EXAM - 05109107 05/09/07 Q #55 0#55 Containment Isolation Containment Isolation Phase Phase "A"A and and Phase Phase "8" B actuated actuated onon Unit Unit 3.
3.
Which ONE Which ONE ofof the the following foNowing describes describes effects effects of of Phase Phase "A"A and and Phase Phase "8" B actuation actuation and the and correct operator the correct operator response?
response?
Phase "A" Phase A caused:
caused:
A.
A. CVCS Auxiliary CVCS Auxiliary spray spray to to the the pressurizer pressurizer to to isolate.
isolate.
Phase B caused COW Phase "8" caused CCW to the the RCPs RCPs to isolate.
isolate.
Operators will Operators will reset reset both both Phase Phase "A" A and and Phase Phase "8"B while while performing performing Attachment 33 of of 3-EOP-E-O.
3-EOP-E-O.
B.
- 8. CVCS letdown letdown from containment to isolate.
Phase "8" Phase B caused CCW to the RCPs RCPs to isolate.
Operators will reset Phase "A" A while performing Attachment 3 of 3-EOP-E-O and will reset Phase "8" B after transitioning from 3-EOP-E-O.
C. Instrument Air to Containment to isolate.
Phase "8" B caused Normal Containment Coolers to trip.
Operators will reset Phase "A" A while performing Attachment 3 of 3-EOP-E-O and will reset Phase "8" B after transitioning from 3-EOP-E-O.
D. R-1 I and R-12 PRMS R-11 R-1 2 samples to isolate.
B caused Normal Containment Coolers to trip.
Phase "8" Operators will reset both Phase A "A" and Phase B "8" while performing Attachment 3 of 3-EOP-E-O.
Page 109 Page 109
TURKEY POINT TURKEY POINT NRC EXAM - 05/09/07 NRC EXAM - 05/09/07 Q #55 Q#55 ANSWER:
ANSWER: BB KA:
KA: 103A2.03 103A2.03 Ability to Ability to (a)
(a) predict predict the the impacts impacts of of the the following following malfunctions malfunctions or or operations operations on on the the Ctmt; and (b) based on those predictions, Ctmt;and (b) based on those predictions, use use procedures procedures to to correct, correct, control, control, or or mitigate the consequences mitigate consequences of of those those malfunctions malfunctions oror operations:
operations: Phase Phase A &&B B Isolation. 3.5/3.8 Isolation. 3.5/3.8 IOCFR55:
10CFR55: 41.b.7
Reference:
Reference:
3-EOP-E-O, Attachment 3, Step 13 13 3-EOP-E-3, Steps 13 and 19 5613-M-3047, Sheet I 5613-M-3047,Sheet1 5613-M-3030, Sheet 5 5613-M-3030,Sheet5 Cog Level: 1I Recall New Question Response Analysis:
A. Incorrect because Phase A did not cause CVCS Auxiliary spray to the pressurizer to isolate and operators will not reset Phase B while still in E-O.
Plausible because Phase B B caused CCW to the RCPs to isolate and operators will reset both Phase A while performing Attachment 3 of 3-EOP-EM.
E-O.
B. Correct per the references. Phase A caused CVCS letdown from containment to isolate. Phase B caused CCW COW to the RCPs to isolate.
Operators will reset Phase A while performing Attachment 3 of 3-EOP-E-O and will reset Phase B after transitioning from 3-EOP-E-O.
C. Incorrect because Phase A did not cause Instrument Air to Containment to isolate and Phase B B did not cause Normal Containment Coolers to trip.
Plausible because operators will reset Phase A while performing Attachment 3 of 3-EOP-E-O and will reset Phase B B after transitioning from 3-EOP-E-O.
D.
D. Incorrect because Phase B B did not cause Normal Normal Containment Coolers to trip and operators operators will not reset Phase B B while still in E-O. Plausible because Phase A caused PRMS R-1 R-111 and R-1 R-12 2 samples to isolate and operators will reset Phase A while performing performing Attachment 33 of 3-EOP-E-O.
Page 110 Page 110
TURKEY POINT TURKEY POINTNRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q #56 0#56 Unit 44 is Unit is at at 100%
100% power power at the Beginning at the Beginning of of Core Core Life Life (BOL)
(BOL) with:
with:
- Control Rods Control Rods are are at D-230.
at 0-230.
- Rod control Rod control is is in in automatic automatic Control Rod Control Rod H-8 H-8 drops drops intointo the the core:
core:
- After decreasing After decreasing to to 2100 2100 psig, psig, RCS RCS pressure pressure stabilizes stabilizes at at 2235 2235 psig.
psig.
- Tavg stabilizes rF Tavg 7°F below below Tref.
Which ONE Which ONE of of the the following describes describes the the effect effect of of this event on this event on the the CVCS CVCS system?
system?
Low Pressure Letdown Letdown Control valve, PCV-4-145, throttled:
A. OPEN initially and subsequently returned to its normal position.
demineralizers have absorbed boron resulting in a positive The CVCS demineralizers reactivity insertion.
B. OPEN initially and subsequently returned to its normal position.
demineralizers have released boron resulting in a negative The CVCS demineralizers reactivity insertion.
C. CLOSED initially and subsequently returned to its normal position.
The CVCS demineralize demineralizers rs have absorbed boron resulting in a positive reactivity insertion.
D. CLOSED initially and subsequently returned to its normal position.
The CVCS demineralize demineralizers rs have released boron resulting in a negative reactivity insertion.
Page 111 Page III
05/09/07 TURKEY POINT NRC EXAM - 05/09107 Q #56 Q#56 ANSWER: C KA: 001K3.01 001 K3.01 Knowledge of the effect that a loss or malfunction of the CROS CRDS will have on the CVCS. 2.9/3.0 IOCFR55:
10CFR55: 41.b.1, 41.b.5
Reference:
3-OP-047, Step 4.10 3-0P-047, SD 013, Page 10 SO Cog Level: 2 Comprehension Level 2 because the operator will have to analyze that the temporary reduction in RCS pressure caused the letdown pressure upstream of PCV-145 to lower. PCV- PCV 145 responded by throttling closed then returning to normal. The operator must also recognize that the reduction in Tavg will result in reduced letdown temperatures. Cooler water through the CVCS demineralizers will result in increased absorption of boron in the demineralizers, resulting in lower boron concentration in the VCT and a subsequent positive reactivity insertion.
New Question Response Analysis:
A. Incorrect because PCV-145 sensed lower upstream pressure and closed initially and subsequently returned to its normal position. Plausible because cooler letdown temperatures means the CVCS demineralizers have absorbed boron resulting in a positive reactivity insertion.
B. Incorrect because PCV-145 sensed lower upstream pressure and closed initially and subsequently returned to its normal position and because cooler letdown temperatures means the CVCS demineralizers have absorbed boron resulting in aa positive reactivity insertion. Plausible because these are consistent and accurate descriptions of PCV-145 response and CVCS demineralizer response for a plant transient in the opposite direction C. Correct per the reference. PCV-145 will throttle closed initially and subsequently return to its normal position. The CVCS demineralizers have absorbed boron resulting in aa positive reactivity insertion.
D.
O. Incorrect because the CVCS demineralizers will absorb more boron resulting in aa positive reactivity insertion. Plausible because PCV-145 will throttle closed initially and subsequently return to its normal position.
Page 112 112
TURKEYPOINT TURKEY POINTNRC EXAM- 05/09107 NRC EXAM - 05/09/07 Q #57 0#57 Unit 44 reactor Unit reactor isis at at 100%
100% power power when when 4A 4A RCP RCP rotor rotor seizes.
seizes. TheThe 4A4A RCP RCP stops stops rotating instantly.
rotating instantly.
Which ONE Which ONE ofof the following describes the following describes the the initial initial effect effect (prior (prior to to the the reactor reactor trip) trip) of of this event this event on on the the Reactor Reactor Coolant Coolant System?
System?
A.
A. Pressurizer level Pressurizer level and and pressure pressure will will decrease.
decrease.
DNBR will Increase.
DNBR will Increase.
B.
B. Pressurizer level and Pressurizer and pressure pressure will will decrease.
decrease.
DNBR will DNBR will Decrease Decrease C. Pressurizer level and pressure will increase.
DNBR will Decrease.
D. Pressurizer level and pressure will increase.
DNBR will Increase Page 113 Page 113
TURKEYPOINT TURKEY POINTNRC NRC EXAM EXAM- 05109107
- 05/09/07 Q #57 Q#57 ANSWER:
ANSWER: CC KA:
KA: 002K6.02 002K6.02 Knowledge of Knowledge of the the effect effect of of aa loss loss or or malfunction malfunction of of the the following following RCS RCS components:
components:
RCP, 3.6/3.8 RCP, 3.6/3.8 100FR55:
10CFR55: 41.b.2, 41.b.3, 41.b.2, 41.b.3, 41.b.14 41.b.14
Reference:
Reference:
FSAR Section FSAR Section 14.1.9 14.1.9 Cog Level:
Cog Level: 22 Comprehension Comprehension Level 22 because Level because the the operator operator must must relate relate the the type type of of RCP RCP failure failure to to the the effects effects onon the RCS parameters.
parameters. He then must must analyze how the changing parameters relate to DNBR and determine that even though RCS DNBR RCS pressure pressure is is increasing, increasing, the reduction reduction in in causes DNB core flow causes DNB to occur.
New Question Response Analysis:
A. Incorrect because pressurizer level and pressure will increase and the DNBR will decrease. Plausible because these parameters are consistent with each other.
B. Incorrect because pressurizer level and pressure will increase. Total core cooling flow will decrease and core damage will occur.
C. Correct per the references. Pressurizer level and pressure will increase and DNBR will decrease.
decrease.
D. Incorrect Incorrect because because DNBR will decrease.
decrease. Plausible Plausible because because Pressurizer Pressurizer level level and and pressure pressure will increase.
increase.
Page 114 Page 114
TURKEY POINT TURKEY POINT NRC EXAM - 05/09/07 NRC EXAM - 05/09/07 Q #58 0#58 Operators are Operators performing aa startup are performing startup on on Unit Unit 33 and and power power is is 5%
5% with with all all pressurizer pressurizer controls in controls automatic when in automatic when the the controlling controlling pressurizer pressurizer level level transmitter, transmitter, LLT-3-459A, T 459A, fails LOW.
fails LOW.
Which ONE Which ONE of of the the following following describes describes the the effect effect of of this this failure failure assuming assuming NO NO operator action?
operator action?
Pressurizer level Pressurizer level will will continuously:
continuously:
A. decrease.
Letdown isolation Letdown isolation will occur when pressurizer pressurizer level level reaches reaches the setpoint.
setpoint.
B. decrease.
The reactor will trip on low pressurizer pressure when the setpoint is reached.
c.
C. increase.
The reactor will trip on high pressurizer level when the setpoint is reached.
D. increase.
Pressurizer PORV(s) will open when the setpoint is reached.
Page 115 Page 115
TURKEY POINT TURKEY POINTNRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q #58 Q#58 ANSWER:
ANSWER: DD KA:
KA: OIIAI.01 011A1.01 Abiflty to predict and/or monitor Ability to predict and/or monitor changes changes in in parameters parameters (to (to prevent prevent exceeding exceeding design limits) design limits) associated associated with with operating operating the the PRZ PRZ LCS LOS controls controls including including PRZ PRZ level level and pressure.
and pressure. 3.5/3.63.5/3.6 IOCFR55:
10CFR55: 41.b.3, 41.b.5 41.b.3,41.b.5
Reference:
Reference:
5610-T-D -15 5610-T-D 15 Sheet Sheet 1I 5610-T-D-16 561 0-T-D-168 B Sheet Sheet 1I Cognitive Level: 3 Application / Analysis Level 3 because the operator must first recognize that the LLT-459A T -459A signal feeds back to the control loop. ioop. When LLT-459A T-459A indicates level is too low, the control loop will send a signal to charging pumps to speed up. Additionally the LLT-459A T-459A failure causes letdown isolation. This combination results in rising pressurizer level. level, If power were above P-7 (10%), the reactor would trip at 92% level. At 5% power, the 92% level trip is not enabled. Level will continue to rise, eventually covering the spray nozzles and taking the RCS water solid. Pressure will rise and PORVs PORV5 will open at 2335 psig.
New Question Response Analysis:
A. Incorrect because pressurizer level will continuously increase. Plausible because pressurizer level would decrease if LT-459A LT-459A failed high instead of low and letdown isolation does does normally normally occur at 14%. 14%.
B.
- 8. Incorrect because pressurizer level will continuously increase. Plausible because pressurizer level level would decrease ifif LT-459A LT-459A failed high instead instead ofof low and the reactor would normallynormally trip pressure when the on low pressurizer pressure pressurizer empties.
C.
C. Incorrect Incorrect because because the reactor reactor will not not trip trip on on high high pressurizer pressurizer level level at at this this power power level.
level. Plausible Plausible because because pressurizer level level will continuously continuously increase.
increase.
D.
D. Correct Correct per per the the references references Pressurizer Pressurizer level level will will continuously continuously increase.
increase.
Pressurizer PORV(s) will open when Pressurizer PORV( s) will open when setpoint is setpoint is reached.
reached.
Page 116 Page 116
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q #59 0#59 Operators are Operators are performing performing aa plant plant start start up up on on Unit Unit 3.
3.
Reactor power Reactor power is is 15%.
15%.
Which ONE Which ONE ofof the the following following describes describes thethe effect effect of of depressing depressing both both Source Range "Source Range LessLess than than P-6 P-6 Push Push toto Re-instate" Re-instate push buttons?
pushbuttons?
The NIS The NIS source source ranges ranges will:
will:
A. re-instate causing re-instate causing aa SRSR Hi Hi Flux Flux reactor reactor trip.
trip.
B. re-instate but a SR Hi Flux reactor trip will NOT occur.
c.
C. NOT re-instate and a SR Hi Flux reactor trip will NOT NOT occur.
D. NOT re-instate until power is reduced below 10% when the SRs will automatically trip the reactor.
Page 117 Page 117
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM 05/09107
- 05/09/07 Q #59 Q#59 ANSWER:
ANSWER: C C
KA:
KA: 015A4.03 Ability monitor in the control room:
Ability to manually operate and/or monitor room: trip bypasses.
bypasses.
3.8/3.9 10CFR55:
10CFR55: 41.b.7
Reference:
5610-T-L11 Sheet 16 5610-T-L Cog Level: Comprehension 2 Comprehension Level 2 because the operator must recognize that when power is >10%, the P-10 P-i 0 permissive is enabled and sends a block signal to both the reinstatement reinstatement of the source ranges and to the source range trip signal. Also, pushing the re-instate pushbuttons does not affect the future automatic operation of the detectors as there is no seal in for these pushbuttons.
New Question Response Analysis:
A. Incorrect because the NIS source ranges will not reinstate and reactor trip will not occur. Plausible because if power was below P-1 P-I 0, this is the action that would occur.
B. Incorrect because the NIS source ranges will not reinstate. Plausible because reactor trip will not occur.
C. Correct per the references. The NIS source ranges will NOT re-instate and aa SR Hi Flux reactor trip will NOT occur.
D. Incorrect because the source ranges will not automatically reinstate and trip the reactor when power drops below 10%. 10%. Plausible because the SRs will not reinstate immediately immediately but will reinstate (without trip) when power subsequently drops below P-6.
Page 118 Page 118
TURKEYPOINT TURKEY POINTNRC NRC EXAM EXAM- 05/09107
- 05/09/07 Q #60 0#60 Unit 33 core Unit core off-load off-load isis inin progress progress when when the the refueling refueling SRO SRO inside inside containment containment reports spent fuel reports aa spent fuel element element has has dropped dropped and and aa large large amount amount of of gas gas bubbles bubbles areare originating from originating from thethe damaged damaged element.
element.
- PRMS R-3-12, PRMS R-3-12, Cont.
Cont. Air Air Gas Gas monitor's monitors countrate countrate increases increases above above setpoint setpoint and alarms.
and alarms.
- PRMS R-3-11, PRMS R-3-1 1, Cont.
Cont. AirAir Particulate Particulate monitor's monitors countrate countrate increases increases butbut does does NOT reach NOT reach thethe alarm alarm setpoint.
setpoint.
Which ONE Which ONE ofof the the following following describes describes an an expected expected plant plant response response and and the the required required operator response?
operator response? .
A. ONLY Containment Ventilation Isolation Isolation should have automatically occurred.
Manually initiate Control Manually initiate Control Room Room Ventilation Isolation Isolation and and verify the isolation isolation 3-ONOP-033.3, "Accidents alignments as directed by 3-0NOP-033.3, Accidents Involving New or Spent Fuel."
Fuel.
B. ONLY Control Room Ventilation Isolation should have automatically occurred.
Manually initiate Containment Ventilation Isolation and verify the isolation 3-ONOP-033.3, "Accidents alignments as directed by 3-0NOP-033.3, Accidents Involving New or Spent Fuel.
Fuel."
C. NEITHER Containment nor Control Room Ventilation Isolation should have automatically occurred.
Manually initiate both and verify the isolation alignments as directed by 3-DNOP-033 3-0NOP-033.3, .3, Accidents "Accidents Involving New or Spent Fuel. Fuel."
D.
D. BOTH BOTH Containment and and Control Room Ventilation Isolation Isolation should should have automatically occurred.
Verify Verify the the isolation isolation alignments alignments as as directed directed byby 3-ONOP-033 3-0NOP-033.3, "Accidents
.3, Accidents Involving Involving NewNew oror Spent Spent Fuel.
Fuel."
Page 119 Page 119
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09/07
- 05/09/07 Q #60 Q#60 ANSWER:
ANSWER: DD KA:
KA: 034A2.01 034A2.01 Ability to (a) predict the Ability to (a) predict the impacts impacts of of the the following following malfunctions malfunctions or or operations operations on on the the fuel handling fuel handling system; system; andand (b)
(b) based based on on those those predictions, predictions, use procedures use procedures to to correct, control, correct, control, oror mitigate mitigate the the consequences consequences of of those those malfunctions malfunctions oror operations:
operations:
dropped fuel dropped fuel element.
element. 3.6/4.4 3.6/4.4 10CFR55:
10CFR55: 41.b.9, 41.b.10, 41.b.9, 41.b.10, 41.b.11, 41 .b.11, 41.b.12 41.b.12
Reference:
Reference:
5610-T-L11 Sheet 5610-T-L Sheet 11 11 3-ONOP-033 .3, Steps 3-0NOP-033.3, Steps 2.2, 2.2, 4.3, 4.3, 5.1.1.1 5.1.1.1 Cog Level:
Cog Level: 22 Comprehension Comprehension The SRO should The SRO should recognizerecognize thatthat bubbles bubbles from from aa dropped dropped assembly are an indication indication the cladding has been breached. Along with the nitrogen gas the gas bubbles will be be gaseous gaseous fission products so that when detected by the containment gas monitor, an an automatic isolation signal will be generated. He then must recognize that when moving fuel, containment integrity is set and that both the control room and the moving containment ventilation system isolate on high PRMS signals.
containment New Question Response Analysis:
A. Incorrect because both containment and control room ventilation Isolation has automatically occurred. Plausible because containment ventilation Isolation should automatically occur and control room ventilation isolation can be be manually initiated.
B.
B. Incorrect Incorrect because because bothboth containment containment and and control control room room ventilation ventilation Isolation Isolation has automatically occurred. Plausible has automatically occurred. Plausible because because control control room room ventilation ventilation Isolation Isolation should should automatically automatically occur occur and and containment containment ventilation ventilation isolation isolation cancan be manually initiated.
be manually initiated.
C.
C. Incorrect Incorrect because because bothboth containment containment and and control control room room ventilation ventilation Isolation Isolation has automatically has automatically occurred.
occurred. Plausible Plausible because because control control room room ventilation ventilation Isolation Isolation andand containment containment ventilation ventilation isolation isolation can can be be manually manually initiated.
initiated.
D.
D. Correct Correct per per the the references.
references. Both Both Containment Containment and and Control Control Room Room Ventilation Ventilation Isolation should automatically occur.
Isolation should automatically occur. Verify Verify the the isolation isolation alignments alignments as as directed directed by by 3-ONOP-033 3-0NOP-033.3, .3, Accidents "Accidents Involving Involving NewNew oror Spent Spent Fuel.
Fuel."
Page 120 Page 120
TURKEYPOINT TURKEY POINTNRC EXAM- 05/09/07 NRC EXAM 05/09/07
- 61 QQ #61 Unit 44 isis inin Mode Unit Mode 33 with with the the MSIVs MSIVs closed closed as as operators operators commence commence aa reactor reactor start start up.
up.
4A main 4A main steamsteam line line safety safety valve, valve, "RV-4-1400",
RV-4-1 400, fails fails open open and and the the 4A 4A S/G SIG rapidly rapidly depressurizes.
depressurizes.
Which ONE Which ONE of of the the following following describes describes the the response response of of the the safeguards safeguards system system toto this failure?
this failure?
Safety Injection Safety Injection will:
will:
A. NOT actuate with the MSIVs NOT MSIV5 closed.
B. actuate when Tavg decreases to 543°F. 543° F.
c.
C. actuate when the 4A S/G SIG pressure decreases to 485 psig.
D. actuate when the 4A S/G pressure decreases to 900 psig.
Page 121 Page 121
TURKEY POINT TURKEY PO1NT NRC NRC EXAM EXAM - 05/09107
- 05/09/07 Q#61 Q#61 ANSWER:
ANSWER: C C
KA:
KA: 035K1.14 035K1.14 Knowledge of Knowledge of the physical connection the physical connection and/or and/or cause-effect cause-effect relationships relationships between between the S/G and the ESF.
the S/G and the ESF. 3.9/4.13.9/4.1 IOCFR55:
10CFR55: 41.b.7, 41.b.8 41.b.7, 41.b.8
Reference:
Reference:
5610-T-L11 Sheet 5610-T-L Sheet 19 19 5610-T-D-18B Sheet 5610-T-D-18B Sheet 11 Cog Level: 3 Analysis Level 3 because Level because the operator must recognize that when a S/G depressurizes, depressurizes, SI usually results due to high steam line ~P. AP. However with the MSIVs closed the 100 psid differential pressure that normally triggers this SI signal can't cant be generated depressurized. That's because the main steam lines would be depressurized. Thats why the main steam header pressure inputs have been nulled at 585 psig so that even with the MSIVs closed, when any S/G'sS/Gs pressure drops to 485 psig, the 100 psid SI actuation logic is made up.
New Question Response Analysis:
A. Incorrect because SI will actuate when the 4A S/G pressure decreases to 485 psig. Plausible because with the MSIVs closed, the header differential pressure cannot reach the 100 psid normally needed to actuate SI.
B. Incorrect because SI will actuate when the 4A S/G pressure decreases to 485 psig. Plausible because 543°F is an SI setpoint that when reached will make up part of SI logic.
logic.
C. Correct per the references. SI will actuate when the 4A S/G pressure decreases decreases to 485 485 psig psig D.
D. Incorrect Incorrect because because SI SI will will actuate actuate when the the 4A 4A S/C S/G pressure pressure decreases decreases to to 485 psig. Plausible because 485 psig. Plausible because 900 900 psigpsig would would result inin 100 100 psid psid at at hot hot zero zero power power that that is an actuation is an actuation signal signal ifif the the MSIVs MSIVs were were open.
open.
Page 122 Page 122
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09/07 05/09/07 Q #62 0#62 3-EOP-E-3, "Steam 3-EOP-E-3, Steam Generator Generator TubeTube Rupture,"
Rupture, directs directs operators operators toto use use the the Steam Steam Dump Dump to Condenser to Condenser system system to initiate aa cooldown to initiate cooldown at at maximum maximum rate rate prior priortoto RCS RCS depressurization.
depressurization.
Which ONE Which ONE ofof the the following following describes describes how how the the Reactor Reactor Operator Operator will will accomplish accomplish this cooldown using the this cooldown using the Steam Steam DumpDump to Condenser system?
to Condenser system?
Place the Place the Mode Mode Selector Selector Switch Switch in:in:
A.
A. AUTO. Bypass AUTO. Bypass the the low low Tavg Tavg interlock.
interlock. Place Place the the Hagan Hagan controller controller inin MANUAL and MANUAL and use the UP use the UP arrow arrow to open the to open the steam steam dump dump valves.
valves.
B.
B. AUTO. Place AUTO. Place thethe Hagan Hagan controller controller in in AUTO AUTO andand adjust adjust the the pot pot setting setting toto the the desired setpoint desired setpoint toto open open the steamsteam dumpdump valves.
valves.
C. MANUAL. Bypass the low Tavg interlock. Place the Hagan controller in MANUAL and use the UP arrow to open the steam dump valves.
D. MANUAL. Place the Hagan controller in MANUAL and adjust the pot setting to the desired setpoint to open the steam dump valves.
Page 123 Page 123
TURKEY POINT TURKEY POINTNRC EXAM- 05/09107 NRC EXAM - 05/09/07 Q #62 Q#62 ANSWER:
ANSWER: CC KA:
KA: 041G2.1 041 .28 G2.1 .28 As itit relates As relates toto the the SO SD Sys:
Sys: Knowledge Knowledge of of the the purpose purpose and and function function ofof major major system system components and controls.
components and controls. 3.2/3.3 3.2/3.3 IOCFR55:
10CFR55: 41.b.4, 41.b.7 41.bA,41.b.7
Reference:
Reference:
3-EOP-E-3, Step 3-EOP-E-3, Step 19 19 SD-I 05 Page SO-105 Page 17 17 0-T-L1, 561 O-T-L Sheet 22A 1, Sheet Level: 2 Comprehension Cog Level: Comprehension Level 2 because the operator must understand all the operating modes of the Hagan controller and EOP-E-3, Step 19 does not provide specific guidance regarding how to use the SOTC SDTC system to achieve the desired results. As stated in the correct response, this is a several step process and requires the operator to determine how the controller responds in various modes of operation, this particular evolution requires the controller to be in both the manual mode and manual control of the hagan process output (manual-manual(manual-manual mode). The operator must also understand that this action would result in the SOTC SDTC valves closing if he did not also bypass the low Tavg interlock.
New Question Response Analysis:
A. Incorrect because the Mode Selector Switch will be placed in MANUAL. MANUAL.
Plausible because the Hagan Plausible because the Hagan controller will be be placed placed in in MANUAL MANUAL and and the the UP arrow will be UP be used used to open open the steam dump dump valves.
B.
B. Incorrect Incorrect because because the the Mode Mode Selector Selector Switch Switch will be be placed placed inin MANUAL MANUAL and and the the Hagan Hagan controller controller will will be be place in MANUAL.
place in MANUAL. Plausible Plausible because because placing placing the the Hagan Hagan controller controller in in AUTO AUTO andand adjusting adjusting the the pot pot setting setting would would open open the the steam steam dump dump valves valves ifif the the Mode Mode Selector Selector Switch Switch werewere placed placed inin MANUAL.
MANUAL.
C.
C. Correct Correct per the references.
per the references. Operators Operators willwill place place thethe Mode Mode SS SS inin MANUAL.
MANUAL.
Bypass the low Tavg interlock.
Bypass the low Tavg interlock. Place Place the the Hagan Hagan controller controller inin MANUAL MANUAL and and use use the the UPUP arrow arrow toto open open thethe steam steam dump dump valves.
valves.
D.
O. Incorrect Incorrect because because thethe Hagan Hagan controller controller will will be be place place inin MANUAL.
MANUAL. Plausible Plausible because because the the Mode Mode Selector Selector Switch Switch will will be be placed placed inin MANUAL MANUAL Page 124 Page 124
TURKEY POINT TURKEY POINTNRC NRC EXAM EXAM- 05109/07 05/09/07 Q #63 0#63 Unit 33 isis at Unit at 100%
100% power power when when thethe steam steam jet jet air air ejector ejector common common steam steam supply supply valve, valve, 3-30-020, isis inadvertently 3-30-020, inadvertently closed.
closed.
Which ONE Which ONE of the following of the following describes describes thethe effect effect of of closing closing valve valve 3-30-020?
3-30-020?
Assume no Assume no other other operator operator action action occurs.
occurs.
A.
A. Condenser vacuum Condenser vacuum will will decrease.
decrease.
Turbine exhaust Turbine exhaust hood hood temperatures temperatures willwill decrease decrease Turbine efficiency will Turbine efficiency will decrease decrease B.
B. Condenser vacuum will decrease.
Main generator Main generator megawatts megawatts will decrease decrease Turbine exhaust hood temperatures will increase C. Tavg will increase Turbine exhaust hood temperatures will decrease Turbine efficiency will decrease D. Tavg will increase.
Main generator megawatts will increase Turbine exhaust hood temperatures will increase Page 125 Page 125
TURKEYPOINT TURKEY POINTNRC EXAM- 05/09/07 NRCEXAM - 05/09/07 Q #63 Q#63 ANSWER:
ANSWER: BB KA:
KA: 055K3.01 055K3.01 Knowledge of Knowledge ofthe the effect effect that that aa loss loss or or malfunction malfunction of ofthe the CARS CARS will will have have onon the the main condenser. 2.5/2.7 main condenser. 2.5/2.7 IOCFR55:
10CFR55: 41.b.5, 41.b.
41.b.5, 41.b.7 7
Reference:
Reference:
561 3-M-301 4, Sheet 5613-M-3014, Sheet 33 3-ONOP-014 3-0NOP-014, Step , Step 2.1.2, 2.1.2, 3-ARP-097.CR EE 5/2 3-ARP-097.CR 5/2 Gen Physics, Gen Physics, PWR PWR Components Components Ch. Ch. 33 Heat Heat Exchangers Exchangers &&
Condensers Pages Condensers Pages 13, 13, 15, 15, && 16 16 Cog Level:
Cog Level: 22 Comprehension Comprehension Level 22 because Level because the the operator operator mustmust realize realize that that closing closing valve valve 3-30-020 3-30-020 willwill stop stop the the steam supply to the CARS CARS which in in turn will allow air to flow backwards backwards through the the SJAE into the condenser which will result in condenser vacuum decreasing and and turbine exhaust hood turbine hood temperature increasing.
increasing. The operator must then relate the the operation of the air ejector to the operation of the condenser and then predict those operation those effects on turbine efficiency and megawatts.
effects New Question New Response Analysis:
Response
A.
A. Incorrect becaus because e turbine exhaust hood temperatures will increase.
Plausible becaus because e condenser vacuum will decrea decrease and turbine efficiency se and efficiency will decrea decreasese B.
B. Correct Correct per per the the references.
references. Condenser Condenser vacuumvacuum will will decrease.
decrease. Main Main generator megawatts will generator megawatts will decrease.decrease. Turbine Turbine exhaust exhaust hood hood temperatures temperatures will will increase.
increase.
C.
C. Incorrect Incorrect becaus because e turbine turbine exhaust exhaust hood hood temperatures temperatures will will increase.
increase.
Plausible Plausible becaus because e Tavg Tavg will will increase increase andand turbine turbine efficiency efficiency will will decrea decrease se D.
D. Incorrect Incorrect becaus because e main main generator generator megawatts megawatts willwill increase.
increase.
Plausible becaus Plausible because e Tavg Tavg will will increase increase andand Turbine Turbine exhaust exhaust hood hood temperatures temperatures willwill increase increase Page126 Page 126
TURKEYPOINT TURKEY POINTNRC NRC EXAM EXAM- 05/09107
- 05/09/07 Q #64 0#64 Unit 33 isis at Unit at 75% power with 75% power with all all systems systems inin normal normal alignment alignment whenwhen the the following following occurs:
occurs:
- Annunciator D Annunciator D 5/3, 5/3, SGFP SGFP AA SUCTION SUCTION LO LO PRESS, PRESS, alarmsalarms
- Annunciator Annunciator D 7/4, D 7/4, LP LP HEATER HEATER BYPASS BYPASS OPEN, OPEN, alarms alarms
- CV-3-201 1 indicates CV-3-2011 indicates open open
- turbine runback aa turbine runback isis NOT NOT inin progress progress Which ONE Which ONE of of the the following following correctly correctly describes describes the the FIRST FIRST operator operator response response in in accordance with accordance 3-ARP-097.CR?
with 3-ARP-097.CR?
A. Close CV-3-2011 Close CV-3-201 1 ifif SGFP SGFP suction suction pressure pressure is is greater greater than 220 psig.
psig.
B. Reduce turbine load to restore SGFP suction pressure.
C. Start the standby Condensate Pump to restore SGFP suction pressure.
D. Dispatch an operator to bypass the Condensate Polishing demineralizers.demineralizers.
Page 127 Page 127
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09/07 05/09/07 Q #64 Q#64 ANSWER:
ANSWER: CC KA:
KA: 056G2.4.50 056G2.4.50 As it relates to the condensate As it relates to the condensate system:
system: Ability Ability to to verify verify system system alarm alarm setpoints setpoints and and operate controls operate controls identified identified inin the the alarm alarm response response manual. 3.3/3.3 manual. 3.3/3.3 IOCFR55:
10CFR55: 41.b.4 41.b.4
Reference:
Reference:
3-ARP-097.CR, 07/4 3-ARP-097.CR, D 714 Step Step 11 && 3.b.
3.b.
3-ARP-097.C 3-ARP-097.CR, 05/3 R, D 5/3 Step Step 22 && 3.a.
3.a.
Cog Level:
Cog Level: 1I Recall Recall New Question New Question Response Analysis:
Response Analysis:
A.
A. Incorrect because Incorrect because the ARP directs operators to start start the standby Condensate Pump to restore SGFP suction pressure to >> 220 psig. .
9 psi because closing CV-2011 Plausible because CV-201 1 would help to restore SGFP suction pressure.
B. Incorrect because because the ARP directs operators to start the standby Condensate Pump to restore SGFP suction pressure to > > 220 psig.
9 psi Plausible becaus because e reducing turbine load would help to restore SGFP suction pressure.
C. Correct per the references. The RO will start start the standby Condensate Condensate Pump to restore SGFP suction pressure pressure to greater greater than 220 psig.psig.
D.
D. Incorrect Incorrect becaus because e the the ARPARP directs directs operators operators to to start start the the standby standby Condensate Pump Condensate Pump to to restore SGFP SGFP suction suction pressure pressure to to> 220 psig.
> 220 psig.
Plausible Plausible becaus because e bypassing bypassing the the Condensate Condensate Polishing Polishing demineralize demineralizers rs would improve SGFP suction would improve SGFP suction pressure. pressure.
Page128 Page 128
TURKEYPOINT TURKEY PONTNRC NRCEXAM EXAM- 05/09107
- 05/09/07 Q #65 0#65 Chemistry has Chemistry has reported reported that that the the concentration concentration of of Oxygen Oxygen inin thethe in-service in-service gas gas decaytank decay tank (GOT)
(GDT) isis 4.2%
4.2% and and the the Hydrogen Hydrogen concentration concentration isis 4.8%.
4.8%.
Which ONE Which ONE ofofthe the following following describes describes the the correct correct operator operator response?
response?
Stop addition Stop addition ofof waste waste gas gas to to the the gas gas decay decay tank tank and:
and:
A.
A. place the place the affected affected GOT CDT tanktank inin the the "standby" standby position.
position.
B.
B. pressurize the pressurize the affected affected GOTCDT with with Nitrogen Nitrogen and and release the GOT release the CDT lAW lAW release release permit as permit as soon soon as as possible.
possible.
C.
C. vent the vent the affected affected GOTCDT to to the the vent vent header header to to remove remove excess excess Oxygen.
D.
O. cross tie cross tie the the affected affected GOTCDT withwith the the standby standby GOTCDT toto reduce reduce the the Oxygen Oxygen concentration concentration. .
Page 129 Page 129
TURKEYPOINT TURKEY POINTNRCNRCEXAM EXAM- 05/09107
- 05/09/07 Q #65 Q#65 ANSWER:
ANSWER: BB KA:
KA: 071K5.04 071 K5.04 Knowledge of Knowledge of the the operational operational implications implications of ofthe the following following concept concept as as itit applies applies toto the WGD the WGD system:
system: relationship relationship of of H2/02 H2/02 concentrations concentrationsto flammability.
to flammability. 2.5/3.12.5/3.1 10CFR55:
10CFR55: 41.b.10, 13 41.b.10,13
Reference:
Reference:
0-ONOP-061, NOTE 0-ONOP-061, NOTE priorprior to to Step Step 55 && steps steps 55 thru thru end end Cog Level:
Cog Level: 1I Recall Recall New Question New Question Response Analysis:
Response Analysis:
A.
A. Incorrect because ONOP-061 directs operators to reduce the Incorrect the oxygen concentration to less than flammability limits by isolating the tank and pressurizing it with Nitrogen and then releasing it if the 02 and H2 concentrations are in this flammability range. Standby could automatically concentrations place the tank back in service if the in-service tank pressure got high enough.
B.
B. Correct per the reference.
C. Incorrect because ONOP-061 directs operators to reduce the oxygen concentration to less than flammability limits by isolating the tank and pressurizing itit with Nitrogen and then releasing itit ifif the the 02 and and H2H2 concentration concentrations s are are in in this flammability range. Venting to to vent vent header header wouldwould only recirculate only recirculate the flow the flow from from the the compressors compressors back back to to the the tank tank and and have have nono effect.
effect.
D.
D. Incorrect Incorrect because because ONOP-061 ONOP-061 directsdirects operators operators to to reduce reduce the the oxygen oxygen concentration concentration to to less less thanthan flammability flammability limits limits by by isolating isolating the the tank tank and and pressurizing pressurizing itit with with Nitrogen Nitrogen and and then then releasing releasing itit ifif the the 02 02 and and H2H2 concentration concentrations s are are inin this this flammability flammability range.
range. Although Although this this would would reduce reduce thethe concentration concentrations, s, itit isis not not allowed allowed by by procedures.
procedures.
Page130 Page 130
TURKEYPOINT TURKEY POiNTNRC NRCEXAM EXAM- 05/09/07
- 05/09/07 Q #66 0#66 The following The following conditions conditions existexist on on Unit Unit 3.3.
- Unit Unit 33 isis at at 90%
90% power.
power.
- Tavg Tavg = 630°F630°F
- RCS RCS pressure pressure isis 22352235 psig psig Which ONE Which ONE of of the the following following describes describes the the required required operator operator response?
response?
A.
A. Place the Place the unit unit in in Mode Mode 33 within within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
hour.
B.
B. Reduce Tavg Reduce Tavg to less than to less than 625°F 625°F within within 15 15 minutes.
minutes.
C.
C. Reduce power Reduce power to to less less than than 75%
75% within within 15 minutes 15 minutes D.
D. Reduce RCS Reduce RCS pressure to less than 2235 psig within 5 minutes.
REFERENCE PROVIDED REFERENCE Page 131 Page 131
TURKEYPOINT TURKEY POiNTNRC NRCEXAM EXAM- 05/09/07
- 05/09/07 Q #66 Q#66 ANSWER:
ANSWER: AA KA:
KA: G.2.1.11 G.2.1.11 Knowl edge of Knowledge of less lessthan than oneone hour hourtechnical technical specification specification action action statements statementsfor for systems. 3.0/3.8 systems. 3.0/3.8 IOCFR55:
10CFR55: 41.b.5 41.b.5
Reference:
TS
Reference:
TS 2.1.1 2.1.1 TS Figure 2.1-1 TS Figure 2.1-1 Provide as Provide as reference:
reference: Tech Spec Tech Spec Figure Figure 2.1-1 2.1-1 Cog Level:
Cog Level: 22 Comprehension Comprehension Level 2 becaus Level 2 becausee the the applicant applicant must must plot plot the the provided provided values values on on thethe given given curve curve and and then evaluate then evaluate ifif the the Safety Safety LimitLimit has has been been violated violated and and then recall the required then recall the required corrective actions.
corrective actions. Note Note thatthat the the given given curve curve has has 33 parameters parameters that that have have to to be be evalua ted and evaluated and the the loci loci of the parameters parameters lies lies between between the labeled Acceptable Acceptable and and Unacc eptable region Unacceptable regions. s. The applica applicant nt has to judge, based on the applicable applicable pressure curve, pressure curve, that the point location location is unacceptable.
unacceptable.
New Question New Question Response Analys Response Analysis: is:
A.
A. Correc Correctt per the referenreference. ce. A Safety Limit has been violate violated. d. Place the unit unit in in Mode Mode 33 within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />. hour.
B.
B. Incorre ct becaus Incorrect because e the TS TS require required response d respon is to se is to shutdo shutdown wn within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
hour.
Plausib le becaus e reducin Plausible because reducing Tavg to g Tavg to less less than than 625° 625°F would restore F would restore condit ions to conditions to within within the the accept able operati acceptable operating region and ng region and becaus because there are e there are other short term Tech Specs that other short term Tech Specs that require aa 15 require 15 minute minute respon response. se.
C.
C. Incorre ct becaus Incorrect because e the the TS TS require required response d respon se isis to to shutdo shutdown within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
wn within hour.
Plausib le Plausible becaus because e reducin reducing g power power to to less less than than 75% 75% would would restore restore conditi conditions ons to within to within the the accept acceptableable operati ng region operating region and and becaus because there are other e there are other short short term term Tech Tech SpecsSpecs that that require require aa 1515 minute minute respon response. se.
D.
D. Incorre ct becaus Incorrect because e the the TS TS require required response d respon se isis toto shutdo shutdown within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
wn within hour.
Plausib le becaus Plausible because e reducin reducing g pressu pressure within 55 minute re within minutes s isis aa require requiredd action ifif action the other PTN Safety Limit (press the other PTN Safety Limit (press >2735 psig) >2735 psig) isisviolate violated.
d.
Page132 Page 132
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09107
- 05/09/07 Q#67 0#67 Operators have Operators have evacuated evacuated the the Control Control Room.
Room.
The Unit The Unit 33 RO RO isis performing performing Attachment Attachment 33 ofof 0-ONOP-1 0-ONOP-1 05, 05, "Control Control Room Room Evacuation and Evacuation" and hashas determined determined that that RCS RCS boration boration isis required.
required.
Which ONE Which ONE of of the the following following describes describes the the correct correct orders orders thethe RO RO should should give give the the SNPO to SNPO successfUlly borate to successfully the RCS?
borate the RCS?
Locally open "Locally open the:
the:
A.
A. Emergency Soration Emergency Boration Valve, Valve, MOV-3-350.
MOV-3-350. After After II start start the the 3C 3C Charging Charging pump, II will direct you to increase the 3C Charging pump speed controller setpoint to 6 psig."
setpoint psig.
B.
S. Boration Valve, MOV-3-350. After I start the 3S Emergency Soration 3B Charging pump, II will direct you to increase the 3S 3B Charging pump speed controller setpoint to 1212 psig."
psig.
C. Manual Soration Boration Valve, 3-356. After II start the 3S 3B Charging pump, II will direct you to increase the 3S 3B Charging pump speed controller setpoint to 6 psig.
psig."
D. Manual Soration Boration Valve, 3-356. After II start the 3C Charging pump, II will direct you to increase the 3C Charging pump speed controller setpointto setpoint to 12 psig.
psig."
Page 133 Page 133
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09/07
- 05/09/07 Q #67 Q#67 ANSWER:
ANSWER: 8B KA:
KA: G.2.1.8 G.2.1.8 Conduct of Conduct ofOperations:
Operations: Ability Abilityto to coordinate coordinate personnel personnel activities activities outside outside the the control control room. 3.8/3.6 room. 3.8/3.6 IOCFR55:
10CFR55: 41.b.7, 41.b.10 41.b.7, 41.b.1O
Reference:
Reference:
O-ONOP-105, Attachment 0-ONOP-105, Attachment 3, 3, Page Page 65, 65, Step Step 23 23 Cognitive Level:
Cognitive Level: 11 Recall Recall New Question New Question Response Analysis:
Response Analysis:
A.
A. Incorrect because Incorrect because the 3C ChargingCharging pump pump is the wrong pump (it will have have no no power) power) and the SNPO should increase the Charging increase Charging pump speed controller controller setpoint to 12 psig. Plausible setpoint Plausible because because MOV-350 MOV-350 is the correct valve to to open open and and 6 psig is the initial chargin g charging pump controller controller setting.
setting.
B.
- 8. Correct per the references Correct references C.
C. Incorre Incorrect ct becaus because e valve 3-356 is the wrong valve and the SNPO should increas increase e the Chargi Charging ng pump speed contro controller setpointtto ller setpoin to 12 12 psig.. Plausib Plausible le becaus because e 3-356 is is aa manua manuall emerge emergencyncy boratio boration valve used n valve used for boration boration under under differe nt circum different stances and circumstances and 66 psig psig is is the the initial initial chargin charging pump g pump contro controllerller setting setting and and 3B38 Chargi Chargingng pump pump is is the the correct correct pump.
pump.
D.
D. Incorre Incorrect ct becaus because e valve valve 3-356 3-356 is is the the wrong wrong valvevalve and and the the 3C 3C Chargi Charging pump ng pump isis the wrong pump (it will the wrong pump (it will have no have no power) power) Plausib Plausible because le becaus 3-356 is e 3-356 is aa manua manual l emerge emergencyncy boratio boration n valve valve used used for for boratio boration under differe n under different nt circum stances and circumstances and becaus because e 12 12 psig psig isis the the correct correct chargin charging pump contro g pump controllerller setting setting. .
Page134 Page 134
TURKEYPOINT TURKEY POINTNRCNRC EXAM EXAM - 05/09107
- 05/09/07 Q#68 Q#68 Which ONE Which ONE of of the the following following isis an an accurate accurate comparison comparison of of the the Unit Unit 33 SFP SEP radiological monitoring radiological monitoring system system to to the the Unit Unit 44 SFP SEP radiological radiological monitoring monitoring system?
system?
AA gaseous gaseous radioactive radioactive release release from:
from:
A.
A. both SFPs both SEPs areare monitored monitored by their own by their own separate separate Unit Unit 33 and and Unit Unit 44 SFP SEP SPING detectors SPING detectors located located in in each each SFPSEP vent duct.
vent duct.
B.
B. both SFPs both SEPs areare monitored monitored by by aa common common SFP SEP SPING SPING located located inin the the SFP SEP common common vent duct.
duct.
c.
C. Unit 3 SFP Unit SEP is is monitored by by the plant plant vent monitor monitor while Unit Unit 4 SFP SEP isis monitored by monitored by aa separate separate U4 U4 SFP SPING.
SEP SPING.
D. SEP is monitored by the plant vent monitor while the Unit 3 SFP Unit 4 SFP SEP is monitored by a separate U3 SFP SEP SPING.
Page 135 Page 135
TURKEYPOINT TURKEY POINTNRC NRC EXAM EXAM- 05/09/07
- 05/09/07 Q #68 Q#68 ANSWER:
ANSWER: D D
KA:
KA: G.2.2.4 G.2.2.4 Ability to explain Ability to explain the variations in the variations in control control board board layouts, layouts, systems, systems, instrumentation instrumentation and procedural and procedural actions actions between between units units at at aa facility.
facility. 2.8/3.0 2.8/3.0 IOCFR55:
10CFR55: 41.b.11 41.b.11
Reference:
Reference:
SD-041 Page SD-041 Page 20, 20, SD-068 SD-068 Page Page 33, 33, 5614-M-3034, Sheet 5614-M-3034, Sheet 1, 1, 5610-M-3060 5610-M-3060 Sheet Sheet 1, 17 5613-M-3034 5613-M-3034 Sheet Sheet 1, 1, Cog Level: 11 Recall Cog Level: Recall New Question Response Analysis:
A. Incorrect because a gaseous radioactive release from both SFPs is monitored differently. Plausible because only unit 4 is vented to the plant vent while unit 3 has a SPING detector in its vent duct.
B. Incorrect because a gaseous radioactive release from both SFPs is monitored differently. Plausible because only unit 4 is vented to the plant vent while unit 3 has a SPING detector in its vent duct.
C. Incorrect because aa gaseous radioactive release from both SFPs is monitored differently. Plausible because only unit 4 is vented to the plant vent while unit 33 has aa SPING detector detector in its vent duct.
D.
D. Correct Correct per per the the references. UnitUnit 44 SFP SFP is is monitored monitored by by the the plant vent monitor monitor while the Unit Unit 33 SEP SFP isis monitored by by aa separate separate U3 U3 SEP SFP SPING.
SPING.
Page 136 Page l36
TURKEYPOINT TURKEY POINTNRCNRCEXAM EXAM- 05/09/07 05/09/07 Q #69 0#69 Which ONE Which ONE of ofthe the following following temporary temporary alterations alterations would would require require aa "prior prior PNSC PNSC approved Temporary approved Temporary SystemSystem Alteration Alteration (TSA),,?
(TSA)?
A.
A. lifting of lifting of aa wire wire to perform aa troubleshooting to perform troubleshooting procedure procedure on on aa circuit circuit associated with turbine runback associated with turbine runback logic. logic.
B.
B. addition of addition of aa jumper jumper inin the the start start circuit circuit of of the the 3A3A HHSI HHSI Pump Pump which which will will remain remain OOS OOS on on an an ECO ECO while while the the jumper jumper isis in in place.
place.
C.
C. addition of addition of aa temporary temporary power power supply supply forfor aa Phase Phase AA Containment Containment Isolation Isolation actuation circuit actuation circuit until until aa permanent permanent powerpower supply supply cancan be be obtained.
obtained.
D.
D. installation of installation of drain drain rigs rigs on on the the pressurizer pressurizer in in preparation preparation for for fill fill and and vent vent following refueling.
following refueling.
Page 137 Page 137
TURKEYPOINT TURKEY POIISTTNRC NRCEXAM EXAM- 05109107
- 05/09/07 Q#69 Q#69 ANSWER:
ANSWER: CC KA:
KA: G.2.2.11 G.2.2.11 Knowledge of Knowledge of the the process processfor forcontrolling controlling temporary temporary changes.changes. 2.5/3.4 2.5/3.4 10CFR55:
10CFR55: 41.b.1O 41.b.10
Reference:
Reference:
ADM-503, Step ADM-503, Step 5.1.4, 5.1.4, Step Step 5.6.1.1 5.6.1.1 ADM-503, Att.
ADM-503, Att. 1, 1, Page Page 11 Cog Level:
Cog Level: Recall 1I Recall New Question New Question Response Analysis:
Response Analysis:
A.
A. Incorrect because Incorrect because lifting of a wire to perform perform troubleshooting troubleshooting on a circuit is is specifically exclud specifically excluded ed from requiring a TSA by ADM-503 (Ref. Step 4.1.2.5). 4.1.2.5).
Plausible because Plausible because lifting a wire is a temporary temporary alteration.
B.
B. Incorrect because Incorrect because addition of a jumpe jumperr in a circuit of a component component which will will remain remain OOSDOS on an ECO while the jumpe jumperr is in place is specifically exclud excluded ed from from requiring a TSA by ADM-503 (Ref. Step 4.1.5.9 4.1.5.9). Plausible
). Plausib because le because adding adding aa jumpe jumperr to aa circuit is aa tempo rary alteration.
temporary C.
C. Correc Correctt per per the the referen references.ces. Addition of of aa tempo temporary power supply rary power supply for aa Phase A Contai Phase Containment nment Isolation Isolation actuati actuation circuit until on circuit until aa perman permanent power ent power supply supply can can be be obtain obtained ed require requires s aa prior prior PNSC PNSC approv approved TSA.
ed TSA.
D.
D. Incorrect Incorrect becaus because e installation installation of of drain drain rigs rigs connec connectedted toto floor floor drains drains isis specifically exclud ed from requiring specifically excluded from requiring aa TSA TSA by by ADM-503 ADM-503 (Ref. (Ref. Step Step 4.1 4.1.2.1).
.2.1).
Plausib le becaus Plausible because e installing installing aa drain drain rig rig isis aa tempor temporary alteration.
ary alteration.
Page138 Page 138
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05109/07 05/09/07 Q #70 0#70 Refueling core Refueling core off-load off-load isis being being conducted conducted on on Unit Unit 3.
3.
The following The following off-load off-load data data has has been been recorded:
recorded:
Time Time Cumulative ## of Cumulative of fuel fuel elements elements off-loaded off-loaded SFP SEP temperature temperature 0800 0800 o0 138°F 138°F 0900 0900 33 138°F 138°F 1000 1000 99 139°F 139°F 1100 1100 15 15 139°F 139°F 1200 1200 22 22 141°F 141°F 1300 1300 30 30 142°F 142°F 1400 1400 37 37 14rF 147°F 1500 1500 47 47 151°F 151°F identifies the FIRST time when core off-load Which ONE of the following identifies off-load should should have been been stopped as required by 3-0P-040.2, 3-OP-040.2, "Refueling Refueling Core Shuffle"?
Shuffle?
A.
A. 1200 B. 1300 C. 1400 D. 1500 Page 139 Page 139
TURKEYPOINT TURKEY POINTNRC EXAM- 05/09/07 NRCEXAM - 05/09/07 Q #70 Q#70 ANSWER:
ANSWER: AA KA:
KA: G.2.2.28 G.2.2.28 Knowledge Knowledge of of new new and and spent spentfuel fuel movement movement procedures.
procedures. 2.6/3.5 2.6/3.5 IOCFR55:
10CFR55: 41 .b.1, 41.b.11, 41.b.1, 41 .b.1 1, 41.b.13 41 .b.13
Reference:
Reference:
3-OP-040.2, Steps 3-0P-040.2, Steps 4.5 4.5 and and 4.6 4.6 Cog Level:
Cog Level: 1I recall recall New Question New Question Response Analysis:
Response Analysis:
A.
A. Correct because Correct because thethe SFP SFP temperature temperature increased increased toto 141°F 141°F at at 1200.
1200. This This exceeds the OP-040.2 OP-040.2 limitlimit of 140°F.
140°F.
B.
B. Incorrect because Incorrect because the off-load should have been stopped at 1200. Plausible Plausible because the cumulative off-load limit and the instantaneous because instantaneous off-load limits limits have been reached at 1300.
C.
C. Incorrect because because the off-load should have been stopped at 1200. Plausible because the cumulative off-load limit has been exceeded at 1400.
because D. Incorrect becaus because e the off-load should have been stopped at 1200. 1200. Plausible becaus because e the instantaneou instantaneous s off-load limit has been exceeded at 1500.1500.
Page140 Page 140
TURKEY TURKE POINT NRC Y POINT NRC EXAM EXAM - 0510910
- 05/09/077 Q #71 0#71 A plant A plant worke workerr is is assign assigneded toto work work inin aa radiat radiation ion field field under under the the follow following ing condit condition ions:
s:
- The job The job is is locate locatedd 22 meter meters from aa 1" s from 1 valve valve that that is is readin reading g 6060 mr/hr mr/hr atat 1I meter distan meter distance.
ce.
- Additionally Additi onally, thethe job locatio location general n gener area dose al area dose rate rate from from other other radiat radiation ion sources sourc is exact es is exactly equal to the ly equal the 10CF IOCFR 2O minim R20 minimumum dose dose rate rate that define defines sa Radiation Radia Area.
tion Area.
- The opera The operator cumulati tor'ss cumu ve docum lative documen ted dose ented dose for the year is is 940 mrem mrem.
- An extension of the expos exposure guideline ure guide liness has NOT NOT been been grante granted.d.
Determin Deter minee the MAXI MAXIMUM numb number er of hours hours he may work withou withoutt receiv receiving ing a dose sion?
extension?
A. 1lhr hr B. 2hrs 2 hrs C. 3hrs 3 hrs D. 4hrs 4 hrs Page 141 Page 141
TURKEY TURKE POINT NRC Y POINT NRC EXAM EXAM - 05/09/0
- 05/09/07 7
Q#71 Q#71 ANSWER:
ANSW ER: C KA: G.2.3.1 G.2.3. 1 Knowlledge Know edge of 10CF IOCFR R2020 and relate related d facility radiat radiatiion on control requir requirememen ts. 2.6/3.
ents. 2.6/3.0 0 100FR55 10CF R55:: 41.b.12 41.b.1 2 Referenc Refer ence: e: 0-ADM-600, 0-ADM -600, Sectio Section 5.7.1.4 n 5.7.1. 4 11OCFR OCFR2O 20 - Radia Radiattion ion Area Definition Cog Level: 3 Analy Analys is sis Level 3 becau because se the opera operator must recall the administrati tor must istrativ vee limits and then calcu calcullate ate the remai remain ing stay time by determining the total dose rate. The opera ning operator tor must recog must recogniznizee to use the inversinverse square e squar e law to calcul calculate ate that the valve readin readingg 60 mr/hr at 11 meter meter will causecause a 15 mr/hr dose rate at the 2 meter meter work location.
Howev Howe er, the opera ver, operator must recog tor must recogniz nizee that the gener general al area dose (1 (1OCF OCFR R2O20 dose rate = 5 mr/hr minimum for Rad Area) needs needs to be added added as well as the worke workerr is exposed also expos ed to this. This will allow 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> hours of stay time before before excee exceedinding g the 1000 guidelline.
mr guide ine. Admin Administrati istrativ vee Limit is 1000 mr/yr without an extension sion.. Opera Operatortor has remain 60 mr remai ing expos ning exposure.ure.
Question New Quest ion
Response
Respo Analys nse Analy is:
sis:
A. Incorrect Incorr ect-pl-plau ausibl siblee if you impro improp erly calcul perly calculate ate the 60 mr/hr at 1 1 meter meter remains remai ns const constant ant out to 2 meter meterss (plane (plane sourc source calculaation) e calcul tion)..
B. Incorrect Incorr ect-pl-plau ausibl siblee if you do not accou accountnt for the invers inverse squaree law and only e squar reduce reduc e the dose by A Y2 (30 mr/hr) instea instead of % (a com d of}4 comm monon mist mistakake) e)
C. Correct Corre ct - the 15 mr/hr from the valve is added added to the 55 mr/hr gene generral al area dose rate to have 20 mr/hr total resulti resultin ngg in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> hours of stay time.
D. Incorre Incorrect ct becau because se the dose from the valve at 2 meter meterss is 15 mr/hr but the gene generral al area dose rate must must be added added to it.
Page 142 142
TURKEY TURKE PONT NRC Y POINT NRC EXAM EXAM - 05/0910 05/09/077 Q #72 0#72 Given the Given the follow following ing condit condition ionss atat aa work work site:
site:
- Radiation Radia level is tion level is 40 40 mrem mrem/hr
- Radi ation Radiation level level with with shield shielding is 10 ing is 10 mrem mrem/hr
- Time for Time for one one worke workerr to to place place shield shielding ing isis 15 15 minut minuteses
- Time to Time to condu conduct the task ct the task with oneone worke workerr is is 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
hour.
- Time to condu Time conduct the task with 22 worke ct the workersrs isis 20 20 minut minutes.
es.
Assumpti Assum ons::
ptions
- shielding If shield ing is used, used, itit is install installed ed by by one worke workerr only and left left in place.
place.
- workerr placin The worke placing shielding g shield ing will be expos exposed ed to a dose rate of 40 mr/hr.
Which ONE of the follow Which following ing would would result result in the lowes lowestt total wholewhole body dose?
dose?
A. Conduct Cond uct the task with two worke workersrs with shield shieldinging..
B. Conduct Cond uct the task with two worke workers withoutt shield rs withou shielding ing C. Conduct Cond uct the task with one worke workerr with shield shielding ing..
D. Conduct Condu ct the task with one worke workerr withou withoutt shield shieldinging..
Page 143 Page 143
TURKEY TURKE Y POINT NRC EXAM - 05/0910
- 05/09/077 Q #72 Q#72 ANSWER: A KA: G.2.3 G.2.3.2 .2 Know Knowlledge edge of facility ALARA program. 2.5/2. 2.5/2.9 9
10CF 10CFR R55:55: 41.b.9 41.b.9,, 41.b.1 41.b.12 2,, 41.b.1 41.b13 3 Refer Refereence:
nce: 0-ADM-600, 0-ADM -600, Step 5.1.1.
5.1.1.2 2
Cognittive Cogni ive Level: 3 Applic Application ation /I Analy Analys is sis Level 3 becau becaussee the opera operato torr must recall the ALARA rule which calls for the total collec collecttive ive expos exposu re ure to be minimized. Then the opera operatotorr must calcul calcula te the ate collec collecttive ive expos exposu re for each option and choos ure choose e the altern alternaative tive with the lowes lowestt total collec collecttive ive expos exposu re.
ure.
Bank Quest Questiionon Response Analy Analyssis:
is:
A. correc correctt becau becaus see the total dose would be 10 mr to the worke workerr placin placingg the shield shieldiing ng plus 3.3 mr to each worke workerr resulting in 16.6 total mr.
B. incorr incorre ect ct becau becaus see each worke workerr receiv receiveess 13.3 mr for a total dose of appro approxximat imatelely y 26.6 mr.
C. incorr incorre ect ct becau becaus see the worke workerr would receiv receive e 20 mrem mrem.. (10 mrem while placin placing g the shield shieldiing ng and 10 mr while perforperformming ing the work).
D. Incorr Incorre ect ct becau becaus see this would result in one workeworkerr receiv receiviing ng 40 mr.
Page 144
TURKEY TURKE POINT NRC Y POINT NRC EXAM EXAM - 05109/0 05/09/07 7
Q #73 0#73 An opera An operator has volunt tor has volunteer eereded toto be be aa memb member of an er of an Emer Emergen gencycy Respo Responsense Team Team that will that will enter enter aa high high radiat radiation area ion area to to rescue rescue aa perso personn from from aa non-li non-life-t fe-thre hreaatenin teningg situation.
situati on.
year.
Which ONE Which ONE of of the follow following ing isis correc correctt regard regarding ing this situati situation?
on?
The operaoperator may:
tor may:
A. NOT be part of the rescue team. team.
operator If the opera participat tor partic ipateded,, the additio additiona nall 4 REM would would excee exceed d the annua annuall 1 OCFR20 10CF R2O limit but wouldwould NOT excee exceed d the allowa allowableble expos exposure ure limit of Enclosur Enclo sure e 11 of O-EPI O-EPIP-2P-20101 11, II, "Re-E Re-Entr y.
ntry".
B. NOT be part of the rescue team. team.
operator If the opera parti cipat tor participated ed,, the additio additiona nall 4 REM wouldwould excee exceed d the annua annuall 100FR2O 10CF R20 limit and would would excee exceed d the allowa allowable ble expos exposureure limit of Enclo Enclosur sure e 1I O-EPIP-2 of O-EPI P-20101 11, 11, "Re-E Re-Entr y.
ntry".
C. be part of the rescu e team team..
The additio additionanall 4 REM will NOT exce exceeedd the annu annua all 1OC 10CF R20 FR2 O limit and will NOT exce excee edd the allow allowaableble expo expossure ure limit of Encl Enclo osur suree 1 I of O-EP O-EPIIP-2 P-201 01 11, Re-
"Re-E Entr y..
ntry" D. be part of the rescue team team..
The addi tiona additio nall 4 REM will exce excee edd the annu annua all I10CF OCFR2OR20 limit but will NOT NOT exce excee edd the allow allowa able ble expo expos sure ure limit of Encl Enclo osur suree 11 of of O-EP O-EPIIP-2 P-20101 11, 11, Re-
"Re-E Entr y..
ntry" Page 145 Page 145
TURKEY TURKE Y POINT NRC EXAM - 05/0910 - 05/09/07 7 Q#73 Q #73 ANSWER: 0D KA: G.2.3.4 G.2.3 .4 Knowlledge Know edge of radiat radiatiionon expos exposure ure limits limfts and contacontamminat ination ion control, including permis permi sible levels in exces ssible excesss of those those autho authorrized.
ized. 2.5/3.1 100FR 10CF 55:
R55: 41.b.12 41.b.1 2 Refere Refer nce:
ence: 0-EPIP 0-EPI -201 11, P-201 11, Step 5.1.1.
5.1.1.11,, 5.1.1.
5.1.1.44,, 5.1.1.
5.1.1.8 8,, Enclo Enclos sure ure 1I I OCFR 10CF R20.1201 20.1 201 Cog Level: 1I Recal Recalll New Quest Questiion on
Response
Respo nse Analy Analys is:
sis:
A. Incorre Incorr ct becau ect because se the opera operato torr may be a memb membe err of the team in spite of violating the 10CF IOCFR 2O limits. Plaus R20 Plausib le becau ible because se the annua annuall 10CF 10CFR R20 2O limit will be excee exceeded ded and the EPIP-EPIP-2 01 20111 limit of 10 REM will not be excee 11 exceeded ded..
B. Incorre Incorr ct becau ect because se the opera operato torr may be a membmembe err of the team and the additional 4 REM would not violate the EPIP limit of 10 REM. Plaus Plausib ible le because becau se the annuaannuall 10CF 10CFR 2O limit will be excee R20 exceeded ded..
C. Incorr Incorreect ct becau because se the 10CF 100FRR20 2O limits will be violated. Plaus Plausib ible le becau because se the opera operato torr may be a membmembe err of the team and the EPIP- EPIP-220111 01 11 limit of 10 REM will not be violated.
D. Correcctt becau Corre because se the opera operatotorr may be a memb membe err of the team in spite of violating the 10CF IOCFR R20 2O limits. The EPIP- EPIP-2 0111 limit of 10 REM will not be 20111 violated.
Page 146
TURKEY TURKE POINT NRC Y POINT NRC EXAM EXAM - 0510910
- 05/09/07 7
Q #74 Q#74 Unit 44 trippe Unit tripped from 100%
d from 100% power power..
The follow The following condition ing condit ionss are are obser observed by the ved by the contro controll room room opera operators tors upon upon completi comp on of letion of 4-EOP 4-EOP-E- 0:
-E-O:
- Steam Gene Steam Generator narrow narrow range range levels levels:: off-sc off-scale ale low low
- Stea m Steam GeneGenerator presspressures: 800 psig 800 psig
- 4A S/G 4A S/G AFWAFW flow flow rate:
rate: 100 100 gpm gpm
rate: 125 gpm 125
- 40 S/G 4C S/G AFWAFW flow rate:rate: 125 125 gpm gpm
- Pressuriz Press er level:
urizer level: off-sc off-scale ale low low
- RCS pressure:
RCS press 600 psig
- a RCS Cold Leg tempe temperatu res:
rature s: 330°F 330°F
- Con Conta tainm inmen entt pressure: 16 psig Which ONE of the follow Which following procedur ing proce es should dures should the opera operators tors transi transition tion to?
A. 4-EOP-E-4-EOP 1, "Loss
-E-1, Loss of React Reactor or or Secon Secondardaryy Coola Coolant nt" B. 4-EOP-E-4-EOP 2, "Fault
-E-2, Faulted Steam Generator Isolati ed Steam Isolation on" C. 4-EOP-FR 4-EOP -FR-P-P.1, Respons
.1, "Resp e to Immin onse Imminen entt Press Pressuriz urized ed Ther Thermmalal Shock Shock Con Condiditio n tion" D. 4-EOP-FR 4-EOP -FR-H-H.1
.1,, "Resp Respons e to Loss of Seco onse Secon ndar dary y Heat Sink Sink" Page 147 Page 147
TURKEY TURKE POINTNRC Y POINT NRCEXAMEXAM- 05/0910
- 05/09/07 7 Q#74 Q#74 ANSWER ANSW ER:: AA KA:
KA: G.2.4.4 G.2.4 .4 Abil ity to Ability to recog recogni nizeze abnor abnorm mal al indica indication tionss for for system system operaoperati ting ng param parame eters ters which which are are entry level entry level condi conditi ons for tions for emerg emerge ncy and ency and abnor abnorm malal opera operati tingng proce proced dures ures.. 4.0/4.
4.0 3
/4.3 IOCFR5 10CF R55: 5: 41.b.100 41.b.1 Referen Refer ence:ce: 4-EOP-E-0, 4-EOP -E-0, Step Step 15* 15 4-EOP-F-0, 4-EOP -F-0, Enclo Enclosu res 33 and sures and 44 Cog Level:
Cog Level: 22 Comp Compre hension rehen sion Level 22 becau Level becaus see the the opera operato torr must must recog recogni ze that nize that aa LOCA LOCA exists exists andand aa secon second dary ary bre breakak does does not.not. The The Opera Operato r must then tor must then apply apply the the criteria criteria of of EOP-F EOP -O
-F-0 to to determ dete rmi ine ne that aa red that red or orang orange path does e path does not not exist exist for for heat heat sink sink or or integr integrity.ity.
New Quest New Questio ionn Respon Respo nsese Analy Analysis:
sis:
A.
A. Correct Corre ct per the refere referen ces. Opera nces. Operato rs should tors should transi transitiotion n to 4-EOP 4-EOP-E- -E-1, 1, "Loss Loss of React Reactor Seconddary or or Secon ary Coola Coolant nt whe when n 4-EOP 4-EOP-E- -E-00 is compcomplet lete becau e because a se LOCA exists LOCA exists and the entry criteria criteria for FR-P.
FR-P.11 and FR-H. FR-H.11 are not yet met. met.
B.
B. Incorrect Incorr ect bec becau aussee a LOCA LOCA exis existsts and the cor correc rectt tran transi tion sitio n is to EOP EOP-E -1,,
-E-1 not EOP-EOP-E-2 E-2.. Plaus Plausib le bec ible becauausse e S/C S/G prepress ssuures res are lowe lowerr than exp expec ted ected for the post post-t -trip rip cond conditition ion and con contatain inmen ment pre press ssuurere is at aa valu value e that can be cau cause sedd by aa MSL MSLB B..
C.
C. Inco Incorr rrect ect bec becau aussee aa LOC LOCA A exis ts and the cor exists correc rectt trans transiition tion isis to to EOP EOP-E -E-1-1,,
not EO not EOP- P-F R-P.1.
FR-P. 1. Pla usib Plaus le bec ible becauaussee RCS RCS cold cold legleg tem tempe per rature atur s are above es are above the the thre threshshooldld valu value e of of 320° 320°F F that that wou would ld forc force transiition e trans tion to to FR-P FR-P..1. 1.
D.
D. Inco Incorr rrect ect bec becau aussee aa LOC LOCA A exis ts and exists and the the cor correc rectt trans transi tion is ition is to to EOP EOP- E-1,,
-E-1 not EOP not EOP-FR-H. -FR- H.1.1. Pla usib Plaus le bec ible becauaussee S/C S/G NR NR level levels are off-s are off-sc scaale le low low andand AFW AFW flow flow rate ratess are are bare barelyly abo ve the above the thre thresh shoold value ld valu e of of 345 345 psig psig that that would wou ld force force trans transi ition tion to to FR-H FR-H..1. 1.
Page 148 Page 148
TURKEY TURKE POINTNRC Y POINT NRC EXAM EXAM- 0510910
- 05/09/07 7
Q #75 0#75 Operato Opera rs are tors are perfor performin mingg 3-EOP 3-EOP-E- -E-1,1, "Loss Loss ofof Prima Primaryry or or Secon Second dary ary Coola nt" Coolant when the follow when the following condition ing condit s ions areare noted noted::
- Containm Conta inmenentt tempe temperatu raturere:: 230°F 230°F
- Con tainm ent Conta inmen t presspressu re:
ure: 25 psig 25 psig
- Pressu Press rize r level urizer level: : Off-scale Off-sc ale low low
- NIS IR NIS IR N-35 N-35 && N-36 N-36 powerpower:: 33 X X 10- 9 i0 ampsamps and and increa increasing sing
- Gam ma metr Gamm a metric ics powerr s powe 55 X 1022 cps X 10 cps and and stable stable Which ONE Which ONE of of the the follow following describ ing descr es the ibes the correc correctt opera operatotorr respo responsnse?e?
Immediat Imme elyy transi diatel transition tion to:
A.
A. 3-EOP-FR 3-EOP -FR-Z-Z.1
.1,, "Resp Respons onsee to High High Conta Containminmenentt Press Pressure.
ure."
B. 3-EOP-FR 3-EOP -FR-S-S.1, Respons
.1, "Resp onsee to Nucle Nuclear Powerr Gene ar Powe Generatio ration /ATW n/AT WS.S."
C. 3-EOP-FR 3-EOP -FR-1-l.2, Respons
.2, "Resp onse e to Low Press Pressuurizer rizer Level.
Level."
D. 3-EOP-FR 3-EOP -C.2
-FR-C .2,, "Resp Respo nse to Degra onse Degraded ded Core Coolin Cooling. g."
Page 149 Page 149
TURKEY TURKE POINTNRC Y POINT NRC EXAMEXAM - 05109/0
- 05/09/07 7
Q#75 Q#75 ANSWER ANSW ER:: 0D KA:
KA: G.2.4.5 G.2.4 .5 Kno Know wled ledgege of of the the organ organizat ion of ization of the the opera operatingting proce procedurdureses netwo network rk for for norma normal, l, abnormal abnor mal andand emerg emergenc encyy evolut evolutionions.s. 2.9/3.
2.9/3.6 6 IOCFR5 10CF R55: 5: 41.b.1O 41.b.1 0 Referenc Refer ence: e: 3-EOP-F-3-EOP O, Enclo
-F-O, Enclosur sures es 1, 1, 2, 2, 5, 5, 6, 6, Attach Attachm ment ent 11 - Pages
- Pages 11 & & 22 Cognitiv Cogni tivee Level:
Level: 22 CompCompreh rehen ensio sion n Leve l 2 beca Level becauuse operator se the opera must evalua tor must evaluate te the condit conditionionss given given to determ determine ine the highest highe priority st priorit condition y condit ion and associate assoc iatedd proce procedur dure.e. The quest question ion is made made more difficult difficu lt by the fact that it appea appears rs that an orang orange e path on subcrsubcritica iticalit y lity exists exists but with adver adverse containm se conta inmen entt condit conditionions,s, an orang orange e path path on subcr iticalit subcritica y lity does not actually actua exist.
lly exist.
Question New Quest ion
Response
Respo Analysis:
nse Analy sis:
A. Incorrect Incorr because ect becau se the opera operatorstors should should transi transition tion to FR-C.
FR-C.2 2 becau because se an oran ge orange path on core coolin cooling g has priorit priorityy over an orang orange e path on containm conta inmen ent. Plausible
- t. Plaus ible becau because se the conta containminmen entt cond condit ionss do meet the ition crite ria criteria for an orang orangee path and the trans transiition tion to FR-Z.1 FR-Z.1 is the usua usuall trans transiition tion operators opera tors will makmake e unde underr these circumcircumsta stance ncess..
B. Incorrect Incorr because ect becau se the operopera ators tors shou should ld trans transiition tion to FR-C FR-C..22 becabecau se an use oran orang gee path on core cool cooliningg exist existss.. Plau Plaus ible beca sible becau se it appe use appea rs that an ars oran orang gee path on subc subcr ritica iticalit lityy exist exists s when the oper opera tor obse ator obserrvesves the IR pow powe err incre increa asing sing.. HowHoweever ver,, adve adverrse se cond condit ition ions s exist andand the oper opera tor shou ator should ld rely on on gamgamm mam etric ametr icss whic which h are stabl stablee..
C.
C. Inco Incorr rrect ect beca becau use se the operopera ators tors shou should ld trans transiition tion to FR-C FR-C..22 becabecau se an use an oran orang gee path path on on core coolcooliningg exist existss.. Plau Plaus ible beca sible becau se press use pressurize urizerr level level isis off-s off-sc cale ale low low whic which h repre repres sents ents aa yello yellow w path path on on inve invent ory..
ntory D.
D. Corr Corre ectct per per thethe refer refere ence nce.. The The oper opera ator tor shou should transiition ld trans tion to to FR-C FR-C..22 in in response to to the the high highe estst oran orang gee path path whicwhich exists h exist at the s at the time time..
Page 150 Page 150
Final Submittal Final Submittal (Blue Paper)
(Blue Paper)
Senior Operator Written Examination
TURKEYPOINT TURKEY POINTNRC NRC EXAM EXAM- 05/09107
- 05/09/07 Q #76 0#76 The Unit The Unit Supervisor Supervisor isis briefing briefing the the crew crew inin preparation preparation for for starting starting anan RCP RCP asas directed by directed 3-EOP-ES-1 .2, "Post by 3-EOP-ES-1.2, Post LOCA LOCA Cooldown Cooldown and and Depressurization."
Depressurization.
Primary system Primary system parameters parameters are:are:
- PRZ Level:
PRZ Level: 73%
73%
- RVLMS Plenum RVLMS Plenum Level:
Level: Full Full
- RVLMS Head RVLMS Head Level: Level: NOT Full NOT Full Which ONE Which ONE of the following of the following describes describes the the effect effect on pressurizer level on pressurizer level when when an an RCP RCP is started is started under under these these conditions conditions and and the the correct correct procedure procedure pathpath the the Unit Unit Supervisor should Supervisor should take?
Pressurizer level will:
Pressurizer A. drop when an RCP RCP isis started.
Transition to 3-EOP-FR-1.3, 3-EOP-FR-l.3, "Response Response to Voids in Reactor Vessel." Vessel.
B. NOT be affected when an RCP is started.
3-EOP-FR-l.3, "Response Transition to 3-EOP-FR-1.3, Response to Voids in Reactor Vessel." Vessel.
C. drop when an RCP is started.
Continue to implement 3-EOP-ES-1.2.
3-EOP-ES-1 .2.
D. NOT be affected when an RCP is started.
Continue to implement 3-EOP-ES-1 3-EOP-ES-1.2. .2.
Page 151 Page 151
TURKEYPOINT TURKEY POINTNRC NRC EXAM EXAM- 05/09/07
- 05/09/07 Q #76 Q#76 ANSWER:
ANSWER: CC KA:
KA: 000009EA2.04 000009EA2.04 Able to Able to determine determine and and interpret interpret the following as the following as they they apply apply toto Small Small Break Break LOCA:
LOCA:
PRZ Level. 3.8/4.0 PRZ Level. 3.8/4.0 10CFR55:
10CFR55: 43.b.5 43.b.5
Reference:
Reference:
3-EOP-ES-i .2, Step 3-EOP-ES-1.2, Step 25 25 and and BO BD 3-EOP-F-O, Enclosure 3-EOP-F-0, Enclosure 66 3-EOP-FR-l.3, CAUTION 3-EOP-FR-1.3, CAUTION prior prior to to Step Step 1I Cog Level:
Cog Level: 22 Analysis Level 2 because the operator must determine that the RVLMS and pressurizer level indications indicate a void in the vessel head and predict that starting an RCP will collapse the void, lowering the pressurizer level. The operator must recall that circumstances to provide forced cooling and starting an RCP is desirable in these circumstances normal pressure control during the cooldown. Finally these conditions are to be expected and there is no need to transition to the identified yellow path procedures.
FR-l.3 should not be implemented when SI pumps are operating.
Additionally FR-1.3 New Question Response Analysis:
A. Incorrect because FR-l.3 FR-1.3 should not be implemented when SI pumps are operating.
operating. Plausible because pressurizer level will drop when an RCP is started as coolant flow to the head region collapses the void, lowering the pressurizer level.
B.
B. Incorrect because pressurizer pressurizer level level will drop drop when an an RCP RCP is is started as as coolant coolant flowflow to the head to the head region region collapses collapses the the void, void, lowering lowering thethe pressurizer pressurizer level.
level. Plausible Plausible because because aa transition to to FR-l-3 FR-I-3 would would address address the the head head void.
void.
Additionally Additionally the the operator operator must must recognize recognize FR-I.3 FR-1.3 should should notnot be be implemented implemented when when SI SI pumps pumps are are operating.
operating.
C.
C. Correct Correct per per the the reference reference D.
O. Incorrect Incorrect because because pressurizer level will pressurizer level will drop drop when when anan RCP RCP isis started started as as coolant coolant flow to the flow to the head head region region collapses collapses the the void, void, lowering lowering thethe pressurizer pressurizer level.
level. Plausible Plausible because because the the operators operators should should continue continue to to implement implement 3-EOP-3-EOP-ES-i .2.
Page 152 Page 152
TURKEYPOINT TURKEY POINTNRC EXAM - 05/09/07 NRC EXAM - 05/09/07 Q #77 Q#77 3-EOP-ECA-2.1, "Uncontrolled 3-EOP-ECA-2.1, Uncontrolled Depressurization Depressurization ofof All All Steam Steam Generators,"
Generators, directs directs operators to operators control feed to control feed flow flow to to minimize minimize RCS RCS cooldown.
cooldown.
RCS cold RCS cold leg leg temperatures temperatures have have decreased decreased from from 54rF 547°F to to 340°F 340°F in in the the past past 60 60 minutes.
minutes.
Which ONE Which ONE of of the the following following describes describes the the correct correct operator operator response?
response?
A.
A. Decrease feed Decrease feed flow flow to to 345 345 gpm.
gpm.
Transition toto 3-EOP-FR-P.1, 3-EOP-FR-P.1, "Response Response to to Imminent Imminent Pressurized Pressurized Thermal Thermal Shock Condition."
Shock Condition.
B.
B. Decrease feed flow Decrease flow to 25 25 gpm gpm to each S/G.
to each S/G.
Transition to and complete 3-EOP-FR-H.1, 3-EOP-FR-H.1, "Response Response to Loss of Secondary Sink.
Heat Sink."
C. 3-EOP-ECA-2.1. Decrease feed flow to 25 gpm to Continue to implement 3-EOP-ECA-2.1.
each S/G.
D. 3-EOP-ECA-2.1. Decrease total feed flow to 345 Continue to implement 3-EOP-ECA-2.1.
gpm.
Page 153 Page 153
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09107
- 05/09/07 Q #77 Q#77 ANSWER:
ANSWER: CC KA:
KA: W/EI2EA2.2 W/E12EA2.2 Able to determ Able to determine ine andand interpret interpretthe thefollowing following as asthey theyapply applytoto Uncontrolled Uncontrolled Depres surizat ion of all S/Gs:
Depressurization of all S/Gs: Adherence to Adhere nce to appropriate appropriate procedures procedures and and operation operation within the within the limitations limitations inin the the facility's facilitys license license andand amendments.
amendments. 3.4/3.9 3.4/3.9 10CFR55:
10CFR55: 43.b..1 43.b .. 1 && b.5 b.5
Reference:
Reference:
3-EOP-ECA-2.1, Step 3-EOP-ECA-2.1, Step 33 3EOP-F-0, Enclosure 3-EOP-F-O, Enclosure 44 3-EOP-FR-H.1, CAUTION 3-EOP-FR-H.1, CAUTION prior prior toto Step Step 11 Cog Level:
Cog Level: 22 Comprehension Comprehension Level 22 because Level because the the operator operator mustmust recognize recognize that that with cool down>
with aa cool down> 100°F/hour, 100°F/hour, ECA-2 .1 will require feed flow ECA-2.1 will require flow toto bebe reduced reduced to to 25 25 gpm gpm per per S/G.
S/G. This This reduction reduction in in feed flow feed flow will will result result in in a red pathpath on heat sink, but because because the reduction reduction of of feed feed flow was flow was procedurally procedurally driven, driven, performance performance of FR-H.1 FR-H.1 is not desirable.
desirable.
New Question New Question Response Analysis:
Response Analysis:
A.
A. Incorrect becaus Incorrect because e RCS temper atures have not droppe temperatures dropped d far enough to trigger trigger an an orange path on Integri Integrity ty and feed flow should be reduce reduced d to 25 gpm per per S/G. Plausib S/G. Plausible becausele becaus e RCS temper temperatures have droppe atures have dropped 22rF in the past d 227°F past 60 minute 60 minutes s which is is aa condit conditionion which norma normally may lead lly may lead to to transit transition ion toto FR-P.1 FR-P.1..
B.
B. Incorre Incorrect ct becaus because e transit transitionion toto FR-H.1 FR-H.1 is is not not require required because d becaus feed flow e feed flow hashas been reduce been reduced due to d due to proced proceduralural require requirements. Plausible ments. Plausib because le becaus operators e operato rs will will decrea decrease se feed feed flow flow toto 25 25 gpm gpm to to each each SIG.
S/G.
C.
C. Correc Correct t per per thethe referen reference.ce. Operat Operators should continu ors should continue e toto implem implement 3-EOP-ent 3-FOP -
ECA-2.1 and decrea se ECA-2.1 and decrease feed flow to feed flow to 25 25 gpm gpm to to each each S/G.
S/G.
D.
D. Incorre Incorrectct becaus because e feed feed flow flow needs needs to to be be reduce reduced to 25 d to 25 gpmgpm to to each each S/GS/G as as directe d by EOP-E directed by EOP-ECA-2.1. CA-2.1. Plausib Plausible because le becaus operators e operato will continu rs will continue e toto implem implement ent 3-EOP -ECA-2.1.
3-EOP-ECA-2.1.
Page154 Page 154
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09107
- 05/09/07 Q #78 0#78 Unit44isisatat100%
Unit 100%powerpowerwithwithall allsystems systemsininnormal normalalignment.
alignment.
TheUnit The UnitSupervisor Supervisorhas hasdirected directed operators operatorstoto remove removethe the4A 4ACCW 00W pumppumpfrom from service service. .
- The The switchyard switchyard subsequently subsequently de-energizes.
de-energizes.
Which ONE Which ONE of of the the following following correctly correctly describes describes Unit Unit 44 sequencer(s) sequencer(s) response response andand the FIRST proced the FIRST procedure the ure the Unit Unit Supervisor Supervisor will will use use to to verify verify correct correct CCW COW system system alignment?
alignment?
A.
A. 4A sequencer 4A sequencer will will close close the the 4C 40 CCW COW pumppump breaker.
breaker.
4B sequen 48 sequencer cer will close the 48 close the 4B CCW COW pumppump breaker.
breaker.
4-EOP-ES-0.1, "Reactor 4-EOP-ES-0.1, Reactor Trip Response."
Response.
8.
- 8. 4A sequencer 4A sequencer will close the 4C CCW COW pump breaker.
breaker.
4B sequen 48 sequencer cer will close the 4B COW 48 CCW pump breaker.
breaker.
4-ONOP-004, "Loss 4-0NOP-004, Loss of Offsite Power."
Power.
C.
C. 4A 4A sequen sequencer cer will attemp attemptt to close the 4A COW CCW pump breaker.
breaker.
4B 48 sequen sequencer cer will close the 4B 48 COW CCW pump breakebreaker.r.
4-EOP -ES-0.1, React 4-EOP-ES-0.1, "Reactoror Trip Respo nse.
Response."
D.
D. 4A 4A sequen sequencer cer will attemp attemptt to to close close the the 4A4A COW CCW pump pump breake breaker.r.
4B 48 sequen sequencer cer will will close close the the 40 4C COW CCW pumppump breake breaker.r.
4-ONO P-004, Loss 4-0NOP-004, "Loss ofof Offsite Offsite Power .
Power."
Page155 Page 155
TURKEYPOINT TURKEY P0111TNRC NRCEXAMEXAM- 05/09/07
- 05/09/07 Q #78 Q#78 ANSWER:
ANSWER: CC KA: 000056AA2.47 KA: 000056AA2.47 - Able - Able toto determine determine and and interpret interpretthe thefollowing following as as they theyapply apply to Loss of Off-site Power: Proper to Loss of Off-site Power: Proper operation of theoperati on of the EOGEDG load load sequencer.
sequencer. 3.8/3.9 3.8/3.9 100FR55:
10CFR55: 43.b.5 43.b.5
Reference:
Reference:
4-EOP-ES-0.1,, Step 4-EOP-ES-0.1 Step 17 17 4-ONO P-004, 4-0NOP-004, First First NOTE NOTE prior prior toto Step Step 11 5614-T-L1, Sheet 5614-T-L1, Sheet 12A&12A& 128,12B, 5610-T-L1, 5610-T-L Sheet 1240 1, Sheet 124D 5610-T-L1, Sheet 5610-T-L1, Sheet 152A 152A Cog Level:
Cog Level: 22 Comprehension Comprehension Level 22 because Level because the the operator operator must must recognize recognize that that ifif the the 4A4A CCW CCW pumppump is is in in PTL PTL itit cannot start.
cannot start. IfIf the the 4A4A CCW CCW pumppump breaker breaker has has not been been racked out, the 4A sequencer will still try sequencer try to close close its its breaker breaker in in the the event event of of a LOOP.
LOOP. 4C CCW CCW pump pump can be can be started started by either sequencer sequencer depending depending on the alignment alignment of 40 4D bus.
However ifif both However both 4A and 48 4B CCW pumps are racked in, 4C CCW pump will not get get aa start signal start signal from a sequencer.
sequencer. Operators Operators will transition from EOP-E-O EOP-E-0 to EOP-ES-EOP-ES 0.1 in 0.1 in response response to the reactor trip caused by the LOOP. ES-0.1, Step 17 is the the first first procedural opportunity to verify proper CCW procedural COW operation.
operation. Note that it is checked checked a a second time second time in ONOP-004 ONOP-004 after operatorsoperators complete complete ES-0.1.
New Questi New Question on Respo Response nse Analysis:
Analysis:
A.
A. Incorrect Incorrect becaus because e 4A 4A sequen sequencer cer will attemp attemptt to close the 4A 4A CCW CCW pump pump breake r. Plausib le breaker. Plausible because becaus e 4B 48 sequen sequencer will close cer will close the the 4B48 COW CCW pump pump breake breaker r and and operato operatorsrs will will verify verify the the COW CCW alignment alignment first first using using 4-EOP 4-EOP-ES- -ES-0.1, 0.1, React "Reactor or Trip Trip Respo nse.
Response."
B.
- 8. Incorrect Incorrect becaus because e 4A 4A sequen sequencer cer will will attemp attempt t toto close close thethe 4A 4A COW CCW pump pump breake breaker r and and operato operatorsrs will will verify verify the the COW CCW alignment alignment first first using using 4-EOP 4-EOP-ES- -ES-0.1, 0.1, React "Reactor or Trip Trip Respon Response."se. Plausib Plausible because le becaus 48 sequencer will e 4B sequencer will close close the the 4B48 COW CCW pump pump breake breaker r C.
C. Correc Correctt perperthe the referen ce reference D.
O. Incorrect Incorrect becaus because e 4B48 sequen sequencer cer will will close close thethe 4B 48 CCWCCW pumppump breake breaker and r and operato operatorsrs will will verify verifythe the COW CCW alignm alignmentent first first using using 4-EOP 4-EOP-ES-0.1, "Reactor
-ES-0.1, Reactor Trip Trip Respon Response." se. Plausib le becaus Plausible because e 4A 4A sequen sequencer will attemp cer will attemptt toto close close thethe 4A COW pump 4A CCW pump breake r.
breaker.
Page156 Page 156
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05109/07
- 05/09/07 Q #79 Q#79 Unit33 isisatat75%
Unit powerwhen 75% power whenthe thefollowing followingoccur:
occur:
50% on on LLT-1 T-112.12.
- 3B main 3B main feedwater feedwaterflowflow control control valve valve transfers transfers toto MANUAL MANUAL mode. mode.
A.
A. Restore 3A Restore 3A EDG EDG to to service service within within 72 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> hours or or initiate initiate aa plant plant shutdown shutdown to to reach Mode reach Mode 33 within within the the following following 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br />.
hours.
B.
B. Restore 3P07 Restore 3P07 toto service service within within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> hour or or initiate initiate aa plant plant shutdown shutdown to to reach reach Mode 3 within the follow Mode 3 within the following ing 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br />.
hours.
C.
C. Verify that all Train B emergency Verify emergency equipment equipment is operable operable within 22 hour2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />shours oror initiate shutdown to reach Mode 3 within the following initiate a plant shutdown following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D.
D. Place 3A 4kv bus and 3A/3C Place 3A13C 480V load center bus stripping stripping logic in thethe tripped condition tripped condition within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Page157 Page 157
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09107
- 05/09/07 Q #79 Q#79 ANSWER: BB ANSWER:
KA:
KA: 000057G2.1.33 000057G2.1.33 AsAsititrelates relatestoto LossLossof ofVital VitalACAC Inst.
Inst. Bus:Bus:Ability Abilitytoto recognize recognize indications indicationsfor forsystem system operati ng parame operating parameters which areters which are entry-level entry-level conditions conditionsfor fortechnical technical specifications.
specifications.
( (3.4 3.4 1/4.0) 4.0 )
IOCFR 10CFR55: 55: 43.b.2 43.b.2
Reference:
Reference:
3-ONOP-003.7 Encl.
3-0NOP-003.7 End. 1,1, NOTE NOTE 1.1. Tech Tech Specs.
Specs. 3.0.3 3.0.3 - Page
- Page 3/43/4 0-1 0-1 Cog Level:
Cog Level: 22 Comprehension Comprehension Level 2 becaus Level 2 because the e the operator operator mustmust analyze analyze indications, indications, determine determine that that they they are are caused by a loss of 3P07 and caused by a loss of 3P07 and relate that the relate that the most most limiting limiting impact impact results results inin aa loss loss ofof the bus the bus stripping stripping relays.
relays. He He must must then then relate relate that that the the loss loss of of bus bus stripping stripping results results inin loss of aa loss of an an auto auto start start signal signal toto the the AFW AFW actuation actuation as as well well as as the the EDG EDG output output breaker auto breaker auto closure closure failure.
failure. He He then then must must determine determine that that the the TS TS actions actions of of 3.0.3 3.0.3 are required based are required based on on AFW AFW availability.
availability.
New Question New Question Response Analysis:
Response Analysis:
A.
A. Incorrect, indications Incorrect, indications are for a loss of 3P07 therefore therefore operators operators must must take take action within action within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour to restore the Vital AC panel or initiate a plant shutdown shutdown to to reach reach ModeMode 3 within the follow following ing 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> becaus because actuation e AFW actuati logic on logic has been degrad ed. Plausib le has been degraded. Plausible because 3A EDG auto-st becaus e auto-start capability art capabi has lity has been been degrad degraded ed and 3A EDG tech specs are also also applica applicable less ble (but less restrict ive).).
restrictive B.
B. Correc Correctt per per thethe referen reference.ce. Operat Operators ors should should restore restore 3P07 3P07 to to service service within within I1 hour or initiate a plant hour or initiate a plant shutdown shutdo wn to to reach reach Mode Mode 33 within within thethe follow following ing 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> hours becaus because e AFW AFW actuatiactuationon logic logic has has been been degrad degraded. ed.
C.
C. Incorre Incorrect,ct, indicat indicationsions are are for for aa loss loss ofof 3P07 3P07 therefo therefore operators re operato must take rs must take action within 1 hour to restore action within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to restore the Vital AC the Vital AC panel panel or or initiate initiate aa plant plant shutdo shutdownwn to to reach reach ModeMode 33 withinwithin the the follow followinging 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> hours becaus because AFW actuati e AFW actuation logic on logic has has been been degrad degraded. ed. Plausib Plausible le becaus because e all all Train Train BB emerge emergency equipment ncy equipm ent needs needs to to be be verifie verifiedd operab operable le within within 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />.
hours.
D.
D. Incorre Incorrect,ct, indicat ions are indications areforforaa loss loss of of3P07 3P07therefo therefore operators re operato musttake rs must take action within action within 11hour hourtoto restore restorethe theVital Vital AC AC panel panel or orinitiate initiate aaplant plantshutdo shutdownwn toto reach reach ModeMode33within withinthethefollow followinging 66hours hoursbecausbecause e AFWAFWactuati actuation logic on logic has hasbeenbeendegrad degraded. ed. Plausib Plausible le becaus because e operato operators will need rs will needtoto place place3A 3A4kv4kv bus and 3A/3C 480V load center bus and 3A/3C 480V load center bus stripping bus strippi logicininthe ng logic thetripped trippedconditi condition.
on.
Page158 Page 158
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09/07
- 05/09/07 Q #80 0#80 Unit44 isis atat 100%
Unit 100% power powerwith with all systems inin normal all systems normal alignment alignmentwhen when the the 4A 4A ICW lOW pump breake pump breakerrtrips trips open open on on over-current.
over-current.
The 4A The 4A ICW lOW pump pump isis declared declared inoperable inoperable and and removed removed fromfrom service.
service.
Which ONE Which ONE of of the following describes the following describes the the Technical Technical Specification Specification limits limits associated associated with the with the 4A 4A ICWlOW pumppump being being out out of service?
of service?
Unit 44 isis inin a:
Unit a:
A.
A. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hour action action statement.
statement. The The action action statement statement time time can can be be extended extended to to seven days if 4D 4KV Bus seven days if 40 4KV Bus is realigned to is realigned to 4A 4A 4KV 4KV Bus.
Bus.
B.
B. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hour action action statement.
statement. The The action action statement statement time time can can NOT NOT bebe extended extended by realigning by realigning 40 4D 4KV 4KV Bus.
Bus.
C.
C. seven day action statement.statement. The The action action statement statement time can be be extended extended to to thirty days if 40 4D 4KV BusBus is realigned realigned to 4A 4KV Bus.
D.
- o. seven day action statement.
seven statement. The action statementstatement time can NOT be extend extended ed by realigning 4D 40 4KV Bus.
Page159 Page 159
TURKEYPOINT TURKEY POiNTNRC NRCEXAM EXAM- 05/09107
- 05/09/07 Q #80 Q#80 ANSWER:
ANSWER: AA KA:
KA: 000062G2.2.22 000062G2.2.22 As it relates As it relates toto LossLossof ofNuclear NuclearSvc SvcWater:Water: Knowledge Knowledgeof oflimiting limiting conditions conditionsfor for operati ons & safety limits.
operations & safety limits. 3.4/4.1 3.4/4.1 IOCFR55:
10CFR55: 43.b.2 43.b.2
Reference:
Reference:
Tech Spec Tech Spec 3.7.3 3.7.3 Actions Actions aa and and bb 5610-T -E-1 591, 5610-T-E-1591, Sheet Sheet 11 Cog Level:
Cog Level: 22 Comprehension Comprehension Level 22 because Level because the the operator operator must must recognize recognize that that the the 4A 4A ICW ICW pump pump is is powered powered from 4A 4KV from 4A 4KV Bus. Bus. IfIf plant plant components components are are in in normal normal alignment, alignment, 4B 4B and 4C and 4C ICWICW pumps share the same train power pumps share the same train power supply resulting supply resulting in in aa 72 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> hour action action statement.
statement.
Swapping 40 Swapping 4D Bus Bus to to 44 AA Bus Bus places places 4CICW 4CICW pump pump on on the "A" A Train increasing increasing the the Action Time to Action Time to 7 days. 7 days.
New Question New Question Response Analysis:
Response Analysis:
A.
A. Correc Correctt perper thethe referen ce. Unit 4 is in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statem reference. statement.
ent. The The action action statem statement ent time can be extend extended ed to seven days if 4D 40 4KV Bus is realign realigned to ed to 4A 4A 4KV4KV Bus.
Bus.
B.
B. Incorre Incorrect ct becaus because e the the action action statem statementent time time can can be be extend extendeded toto seven seven days days ifif 4D 40 4KV 4KV Bus Bus is is realign ed to realigned to 4A 4A 4KV 4KV Bus.
Bus. Plausib Plausible because Unit le because Unit 4 is in 4 is in aa 72 hour action statem 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement. ent.
C.
C. Incorre Incorrect ct becaus because e Unit Unit 44 isis in in aa 72 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> hour action action statem statement. Plausible ent. Plausib because le becaus e 77 days days isis the the correct correct action action statem statement ent time time for for aa CCWCCW pumppump andand the the action action statem statement ent time time cancan bebe extend extended ed toto 30 30 days days (for (for aa CCW CCW pump) pump) ifif4D 40 4KV4KV BusBus isis realign ed to realigned to 4A 4A 4KV4KV Bus.
Bus.
D.
O. Incorre Incorrect ct becaus because e Unit Unit44 isis inin aa 72 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> houraction action statem statement and the ent and the action action statem ent time can be extend statement time can be extended if 40 4KV Bus ed if 4D 4KV Bus isis realign realigneded toto 4A 4A 4KV4KV Bus. Bus.
Plausib Plausible le becaus because e 77days days isisthe the correct correct action action statem statement timefor ent time foraaCCW CCW pump.
pump.
Page160 Page 160
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09/07
- 05/09/07 Q#81 Q#81 Unit33 isis atat100%
Unit 100% power powerwhenwhen aa loss loss of ofall allfeedwater feedwatereventeventoccurs.
occurs.
Asthe As the crew crewtransitions transitionsfromfrom 3-EOP-E-O, 3-EOP-E-0, the the STA STA informs informsthemthem aa red red path path exists exists on on Heat Sink.
Heat Sink.
The operators The operators successfully successfully initiate initiate bleed bleed and and feed.
feed.
Which ONE Which ONE of of the the following following describes describes thethe reportability reportability of of this this event?
event?
The event The event must must be be reported reported toto the:
the:
A.
A. NRCOC within NRCOC within 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br />.
hours.
B.
B. NRC Resident NRC Resident within within 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br />.
hours.
C.
C. State of State of Florida Florida within within 15 15 minutes minutes andand toto the the NRC NRC immediately immediately following following State notific ation.
State notification.
D.
D. State of Florida State Florida within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> and to the NRC immediately immediately following following State State notification.
notification.
REFERENCE PROVIDED REFERENCE PROVIDED Page161 Page 161
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09107
- 05/09/07
- 81 QQ#81 ANSWER:
ANSWER: CC KA:
KA: W/E05G2.4.30 W/E05G2.4.30 As it relates to As it relates to Loss Loss of ofsecondary secondary Heat Heat Sink:
Sink: Knowledge Knowledge of ofwhich which events events related related toto system operati ons/sta tus should system operations/status should be reportedd to be reporte to outside outside agencies.
agencies. 2.2/3.6 2.2/3.6 IOCFR55:
10CFR55: 43.b.5 43.b.5
Reference:
Reference:
O-EPIP-2010 0-EPIP-201 01, 1, Enclosure Enclosure 1, 1, Category Category 5, 5, Item Item C.3 C.3 O-EPI P-2010 1, 0-EPIP-201 01, CAUTIONS CAUT IONS beforebefore Step Step 5.6.1.11 5.6.1.11 ADM-1 15, Enclosures ADM-115, Enclosures 11 & & 22 Cog Level:
Cog Level: Recall 11 Recall New Question New Question Provide EPIP-20101 Provide EPIP-20101 Enclosure Enclosure 1I and ADM-115, ADM-115, Enclosures Enclosures 1I & 22 as as aa reference reference Response Analysis:
Response Analysis:
A.
A. Incorrect because Incorrect because the event must be reported reported to the State of Florida within within 15 minute 15 minutes s and to the NRC immediately follow immediately following notification in ing State notification in accordance with 0-EPIP-201 accordance O-EPIP-201001, 1, "Duties Duties of the Emergency Emergency Coordinator."
Coordinator.
Plausib le becaus e notific ation Plausible because notification the NRCO to NRCOC C lAW ADM-ADM-115 required 1 15 is require in d in the the event event of the occurroccurrenceence of signifi cant events as defined in IOCFR significant 10CFR50. 72.
5O.72.
B.
B. Incorre Incorrectct becaus because e the event event must be be reporte reported to the d to the State State of of Florida Florida within within 15 minute 15 minutes s and and toto the the NRC NRC immed iately follow immediately following State notification ing State notification in in accord ance with accordance with O-EPI P-201001, 0-EPIP-201 1, Dutie "Duties of the s of the Emerg Emergency Coordinator."
ency Coord inator.
Plausib Plausible le becaus because e notific ation to notification to the the NRC NRC Reside Resident lAW ADM-115 nt lAW ADM-1 15 is is require d in the event required in the event of of the the occurr ence of occurrence of signifi significant events..
cant events C.
C. Correc Correct t per per the the referen reference. ce. The The event event must must be be reporte reported to the d to the State State of of Florida Florida within within 1515 minute minutes s and and toto the the NRC NRC immed immediately following iately follow State ing State notific ation notification D.
D. Incorre ct becaus Incorrect because e the the event event must must be be reporte reported d toto the the State State of of Florida Florida within within 15 minute s and to 15 minutes and to the NRC the NRC immed iately follow immediately following State notific ing State notification ation inin accord ance with accordance with O-EPI P-201001, 0-EPIP-201 1, Dutie "Duties ofthe s of the Emerg Emergency Coordinator."
ency Coordinator.
Plausib Plausiblele becaus because e the the 11hour hourtime timeframe frame applies appliesto to NRC NRC notific notification ation andand certain certain other othernotific ations describ notifications described ed inin O-ADM-1 0-ADM-115. 15.
Page162 Page 162
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09/07 05/09/07 Q #82 Q#82 Unit33 isis atat 50%
Unit 50% power powerwith with control control Bank Bank"0"D at at 180 180 steps.
steps.
A mome A momentary ntary power powerloss loss inin the the 2BO 2BD Power PowerCabinet Cabinetcontrol control power powercircuitry circuitry causes causes all 3 of the Bank D group 2 rods all 3 of the Bank "0" group 2 rods to drop 140 to drop 140 steps steps into into the the core core where where they they are are gripped and gripped and held held normally normally by by the the re-energized re-energized stationary stationary grippers.
grippers.
Which ONE Which ONE of of the the following following describes describes the the correct correct actions actions the the Unit Unit Supervisor Supervisor should direct should direct thethe operators operators to to perform?
perform?
A.
A. Verify rod Verify rod control control isis in AUTOMATIC and in AUTOMATIC and reduce reduce turbine turbine load load using using 3-0NOP-3-ONOP-100, Fast Load Reduction, 100, "Fast Load Reduction", to to lower lower Tref Tref toto within within 3°F 3°F of of Tavg.
Tavg.
B.
B. Verify rod Verify rod control control isis in in MANUAL MANUAL and and reduce reduce turbine turbine load load using using 3-0NOP-100, 3-ONOP-100, Fast Load "Fast Load Reduction",
Reduction, until until all all Bank Bank "0" D rods rods are are aligned within 12 aligned within 12 steps steps C.
C. Manually trip Manually trip the the reactor, reactor, verify verify the the reactor reactor isis tripped, tripped, perform perform 3-EOP-E-0 3-EOP-E-0 and stabilize and stabilize the the plant plant using using 3-EOP-ES-0.1.
3-EOP-ES-0.1.
D.
O. Manually trip the reactor, Manually reactor, verify the reactor is tripped and Emergency Emergency Borate Borate per 3-ONO P-046.
per 3-0NOP-046.11..
Page163 Page 163
TURKEYPOINT TURKEY PONTNRCNRCEXAMEXAM- 05/09/07
- 05/09/07 Q #82 Q#82 ANSWER:
ANSWER: CC KA:
KA: 000003G.2.4.6 000003G.2.4.6 As it relatesto As it relates to thethe dropped dropped control control rodrod event:
event: Knowledge Knowledge of ofsymptom symptom based based EOP EOP mitiga tion strateg ies.
mitigation strategies. 3.1/4.0 3.1/4.0 IOCFR55:
10CFR55: 43.b.5 43.b.5
Reference:
Reference:
3- ONOP-028.3, 3- ONOP-028.3, Step Step 11 3-EOP -E-0, 3-EOP-E-0, Step Step 1, 1, 3-EOP-ES-0.1, Step 3-EOP-ES-0.1, Step 55 Cog Level:
Cog Level: 22 Comprehension Comprehension The SRO must The SRO must recognize recognize that that even even though though thethe dropped dropped rods rods did did not not fully fully insert insert aa reactor trip reactor trip is is required.
required. He He then then must must analyze analyze that that the the control control rods that were rods that were dropped initially dropped initially would would still still be be trippable trippable as as they they were were re-gripped re-gripped by by the the stationary stationary grippers and grippers and should be be free to fall on the trip. He He then must understand understand that that the the EOP networ EOP network k only addres addresses ses rods that do not fully insert insert on a trip by emergency emergency borating using borating using ONOP-46.1, ONOP-46.1, dropped dropped rods are not addressedaddressed unless they fail fail to to insert.
insert.
New Question New Question Response Analys Response Analysis: is:
A.
A. Incorre Incorrect ct becaus because e the reactor would be manua manually tripped.. Plausib lly tripped Plausible because le becaus e Tavg is restore d to Tref Tavg is restored to Tref by borating and by boratin g and reducin reducing g turbine load load inin ONOP ONOP-28.3 -28.3 which which is is used used for droppe dropped d rod recove ry. ONOP recovery. ONOP-028.3 requires
-028.3 require the Rod s the Rod Contro Controll Selecto Selector r Switch Switch to to be be placed placed inin MANU MANUAL. AL.
B.
B. Incorre Incorrect ct becaus because e the the reactor reactor would would bebe manua manually tripped.. Plausib lly tripped Plausible because le becaus e Tavg is restore Tavg is restored to d to Tref Tref by by boratin boratingg and and reducin reducing turbine load g turbine load inin ONOP ONOP-28.3 -28.3 which which isis used used for for droppe dropped d rod rod recove recovery.
ry.
C.
C. Correc Correct t as as the the event event describ described ed was was multip multiple dropped le droppe rods that d rods that were were relatch ed by the norma relatched by the normal operation l operati on of ofthe the station stationary grippers, ary grippe they should rs, they should still still be be trippab trippable le and and fully fully insert insert when when thethe manua manual trip isis ordere l trip ordered.d. TheThe EOPs EOPs only only addres address s rods rods that that are are stuck stuck outout of ofthe the core.
core.
D.
D. Incorre Incorrect ct becaus because e the the EOPs EOPs only onlyaddres address stuck rods s stuck rods and and these these rods rods should should still insert on the reactor still insert on the reactortrip. trip. Plausib Plausible because le becaus the step e the step inin ES-0.1 ES-0.1 directs directs the the operato operator r toto Emerg Emergencyency Borate Borate using using 3-ONO 3-0NOP-046.1 P-046.1 toto compecompensate nsate for for any stuck any stuck rods. rods.
Page164 Page 164
TURKEYPOINT TURKEY POINTNRCNRCEXAM EXAM- 05/09/07 05/09/07 Q #83 Q#83 Operatorsare Operators are increasing increasing Unit Unit 33 power powertoto 100%.
100%.
- With With power powerat at 95%
95% power, power, annunciator annunciator BB 9/3, 9/3, SHUTDOWN SHUTDOWN ROD ROD OFF OFF TOP TOP //
DEVIATION, alarms.
DEVIATION, alarms.
- TheThe RO RO reports reports thatthat control control rod rod H-8 H8 (0 (D Bank)
Bank) has has stopped stopped moving moving and and isis now 14 steps lower now 14 steps lower than than other other 0D Bank Bank control control rods.
rods.
- Subsequent investigation Subsequent investigation reveals reveals H-8 H-8 isis stuck stuck and and untrippable.
untrippable.
Which ONE Which ONE ofof the following describes the following describes the the Tech Tech Spec Spec required required operator operator response response and the and the BASIS BASIS for for the the action?
action?
A.
A. Place Unit Place Unit 33 in in Mode Mode 33 within within 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> hours to ensure adequate to ensure adequate Shutdown Shutdown Margin Margin require ments requirements are met.are met.
B.
B. Place Unit Place Unit 3 in in Mode Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> hours to reduce the effect to reduce effect of the stuck rod rod onon the subseq the subsequentuent Xenon Oscillation.
c.
C. Declare H-8 inoperable Declare inoperable and reduce power to < 75% within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />, confirm all all Bank "0" Bank D rod positions positions are within .:t+/- 12 steps of each other to ensure adequate Shutdown adequate Shutdown Margin requirements requirements are met.
D.
D. Declar Declare e H-8 inoper able and reduce power to << 75% within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />, confirm all inoperable all Bank Bank D "0" rod positio ns are within +/-
positions .:t 18 18 steps of each other to reduce the affect affect of the stuck rod on the subseq subsequentuent Xenon Oscillation.
Page165 Page 165
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09/07
- 05/09/07 Q #83 Q#83 ANSWER:
ANSWER: AA KA:
KA: 000005G.2.2.22 000005G.2.2.22 As it relates As it relates toto the the Inoperable/Stuck Inoperable/Stuck Control Control Rod:Rod: knowledge knowledge of of limiting limiting conditions conditions for operati ons and safety limits.
for operations and safety limits. 3.4/4.1 3.4/4.1 IOCFR55:
10CFR55: 43.b.2 43.b.2
Reference:
Reference:
3-ONOP-028, Step 3-0NOP-028, Step 5.1.4.2 5.1.4.2 Tech Spec 3.1.3.1 Action Tech Spec 3.1.3.1 Action a. a.
O-ADM-536, Section 0-ADM-536, Section 3/4.1.3 3/4.1.3 Cog Level:
Cog Level: 11 Recall Recall New Question New Question Response Analysis:
Response
A.
A. Correct per the reference.
Correct reference.
B.
B. Incorrect because Incorrect because Xenon Oscillations are not the basis for the requirement requirement to to be in MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Plausible be Plausible because because the reactor must be placed in in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Misaligned rods could be an initiating event for Xe MODE Xe oscilla tions which do challen oscillations challenge ge the power distribution limits.
C.
C. Incorrect Incorrect becaus because e the unit must be placed in Mode 3 within 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br />. hours.
Plausib le becaus Plausible because e the rod must be declare declared inoperable d inoper able and reducing power to <75%
to <75% would be be aa correct respon response se ifif the rod rod was trippable. Reducing Reducing power using using boration boration would increas increase e shutdo shutdown margin.
wn margin.
D.
D. Incorrect Incorrect becaus because e the the unit unit must must be be placed placed in in Mode Mode 33 within within 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> hours and and Xenon oscillations Xenon oscillations are are not not the the basis.
basis. Plausib Plausible because le becaus reducing power e reducing power toto
<75%
<75% and and confirming confirming all all rods rods inin the the bank bank are are within within 18 18 steps steps would would reduce reduce peaking peaking factors factors and and would would be be aa correct correct respon responsese ifif the the rod rod were were not not untrippable.
untrippable.
Page166 Page 166
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09/07 05/09/07 Q #84 Q#S4 Unit 44 isis at Unit at SO%
80% power power during during endend of life (EOL) of life (EOL) power power coast coast down down operation.
operation.
- Tavg isis being Tavg being allowed allowed to droop to to "droop" maintain the to maintain the reactor reactor critical critical and and isis presently 3°F presently 3°F BELOW BELOW Tref Tref as directed by as directed by Reactor Reactor Engineering.
Engineering.
The auto The auto function function ofof the running Charging the running Charging pump pump controller controller fails fails causing causing thethe Charging pump Charging pump to operate at to operate at minimum minimum speed.speed.
Which ONE Which ONE of of the the following following identifies identifies thethe correct correct procedure procedure the the Unit Unit Supervisor Supervisor should enter to respond to this failure and the should enter to respond to this failure and the pressurizer levelpressurizer level that that the the Unit Unit Supervisor will Supervisor will direct direct the the RO RO toto maintain?
maintain?
A.
A. 4-ONOP-041 .6, "Pressurizer 4-0NOP-041.6, Pressurizer Level Level Control Control Malfunction" Malfunction 44%.
44%.
B. 4-ONOP-047.1, "Loss 4-0NOP-047.1, Loss of Charging Flow in Modes 1I Through 4" 4 44%.
C. 4-ONOP-041.6, "Pressurizer 4-0NOP-041.6, Pressurizer Level Control Malfunction" Malfunction 47%.
D. 4-ONOP-047.1, "Loss 4-0NOP-047.1, Loss of Charging Flow in Modes 1 1 Through 4" 4 47%.
Page 167 Page 167
TURKEYPOINT TURKEY POINTNRCNRCEXAM EXAM- 05109/07
- 05/09/07 Q #84 Q#84 ANSWER:
ANSWER: AA KA:
KA: 000028AA2.08 000028AA2.08 Able to Able to determine determine and and interpret interpret thethe following following asas they they apply apply toto Pressurizer Pressurizer LevelLevel Malfunction: PRZ level as a function Malfunction: PRZ level as a function of of power power level.
level. 3.1/3.5 3.1/3.5 IOCFR55:
10CFR55: 43.b.5 43.b.5
Reference:
Reference:
4-ONOP-041 .6, Step 4-0NOP-041.6, Step 4.24.2 && Enclosure Enclosure 1, 1, SD-009 pages SD-009 pages 88 & & 99 Cog Level:
Cog Level: 33 Application Application // Analysis Analysis Level 33 because Level because the the SRO SRO mustmust recognize recognize thatthat the the automatic automatic pressurizer pressurizer levellevel control control system would have been maintaining level have been maintaining level lower lower based based on on the the lower lower than than normal Tavg normal Tavg for for the the present powerpower level.
level. HeHe must must calculate the programmed pressurizer level for the given plant conditions pressurizer conditions and relate that Tavg is being maintained at 3°F below Tref and that prz maintained Prz level reference signal is generated from Tavg Tavg and not from power. Tref at 80% power would normally be 568.6°F which would demand 47% pressurizer level but since Tavg is 3°F low, the required would pressurizer level would be 44%. Calculation: 22% to 53% level. 80% X 31 % %
program level span =
program = 25%. 25% + 22% = = 47% for 80% power but Tavg is not on program so the pressurizer level must be maintained at 44% to equate to the program 565.6°F Tavg.
New Question
Response
Response Analysis:
A.
A. Correct because the correct procedure the Unit Supervisor Supervisor should enter to to respond to to this this failure failure isis 4-ONOP-041 4-0NOP-041.6, and the pressurizer
.6, and pressurizer levellevel that the Unit Unit Supervisor Supervisor will directdirect the the RORO toto maintain maintain is is 44%.
44%.
B.
B. Incorrect Incorrect because because the the Unit Unit Supervisor Supervisor should should enter enter 4-ONOP-041 4-0NOP-041.6. .6.
Plausible because Plausible because 44% 44% is is the the correct correct value value for for pressurizer pressurizer level.
level.
C.
C. Incorrect Incorrect because because the the correct correct value value for for pressurizer pressurizer level level is is 44%.
44%. Plausible Plausible because because the the Unit Unit Supervisor Supervisor shouldshould enter enter 4-ONOP-041 4-0NOP-041.6. .6.
D.
D. Incorrect Incorrect because because the the Unit Unit Supervisor Supervisor should should enter enter 4-ONOP-041 4-0NOP-041.6, and the
.6, and the pressurizer pressurizer level level that that the the Unit Unit Supervisor Supervisor willwill direct direct the the RORO to to maintain maintain isis 44%.
44%. Plausible Plausible because because 47% 47% isis the the normal normal programmed programmed level level for for this this power power level level and and oneone charging charging pumppump at at minimum minimum speed speed approximates approximates the the entry entry conditions conditions forfor ONOP-047.1 ONOP-047.1. .
Page 168 Page 168
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09107
- 05/09/07 Q #85 0#85 With reactor With reactor power power at at 80%,
80%, PRMS-R-15 PRMS-R-1 5 alarmsalarms andand count-rate count-rate increases increases rapidly rapidly and stabilizes and stabilizes atat 5,000 5,000 cpm.
cpm.
Operators enter Operators enter 3-0NOP-071.2, 3-ONOP-071 .2, "Steam Steam Generator Generator Tube Tube Leakage,"
Leakage, and and attempt attempt to to quantify the leakage using the R-1 quantify the leakage using the R-15 Primary to 5 Primary to Secondary Secondary Leak Leak Rate Rate Graph Graph in the in the Plant Plant Curve Curve Book.
Book.
Unit 33 Condenser Unit Condenser air air in-leakage in-leakage isis constant constant atat 77 scfm.
scfm.
All of All of the the S/G SIG tube tube leakage leakage isis coming coming from from the the 3B 3B S/G.
S/G.
Which ONE Which ONE of of the the following following is correct regarding is correct regarding the the Tech Tech Spec Spec limits limits and and the the directions the directions the SRO SRO should should give give based based on the above on the above plant plant conditions?
conditions?
The RCS The RCS primary primary to secondary leakage to secondary leakage has:
has:
A.
A. NOT exceeded the Tech. Spec. limit. Be in in Mode Mode 3 in ~ 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
B.
B. NOT exceeded the Tech. Spec. limit. Be in Mode 3 in ~ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C. exceeded the Tech. Spec. limit. Be in Mode 3 in ~ 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
D.
D. exceeded the Tech. Spec. limit. Be in Mode 3 in ~ 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
REFERENCE PROVIDED REFERENCE Page 169 Page 169
TURKEY POINT TURKEY POINTNRC NRC EXAM EXAM- 05/09/07 05/09/07 Q #85 Q#85 ANSWER:
ANSWER: CC KA: 000037G2.1.33 KA: 000037G2.1 .33 As itit relates As relates to to Steam Steam Generator Generator Tube Tube Leak:
Leak: Ability Ability to to recognize indications for system recognize indications for system operating operating parameters parameters which which are are entry-level entry-level conditions for conditions for technical technical specifications.
specifications. 3.4/4.0 3.4/4.0 10CFR55:
10CFR55: 43.b.2 43.b.2
Reference:
Reference:
3-ONOP-071 .2, Step 3-0NOP-071.2, Step 7, 7, 9a 9a TS 3.4.6.2.c TS 3.4.6.2.c PCB Section PCB Section 5, Figure 15, 5, Figure 15, Unit Unit 33 R-15 R-1 5 Primary Primary to to Secondary Secondary Leak Leak Cog Level:
Cog Level: Application // Analysis 33 Application Analysis Level 33 because Level because the operator operator mustmust locate locate the correctcorrect point point on on the R-15 R-1 5 curve, curve, read read the value from the curve (which is is less than the TS limit) and then relate the air in-leakage to the need to multiply the value by 7. Then the operator must compare the multiplied value to the TS limit of 500 gpd and determine the TS limit has been exceeded. The operator must then recall the guidance of ONOP-071.2 ONOP-071 .2 to be in Mode 3 within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
New Question Examiner note: ONOP 71.2 and TS have been frozen earlier revision.
=
5000 cpm 122 gpd from graph. Multiply 122 X 7 scfm = 854 gpd which =
exceeds TS limit of 500 gpd from one SIG. S/G.
Provide PCB Section 5, Figure 15 15 as a reference Response Analysis:
A.
A. Incorrect because S/G tube leakage has exceeded the Tech. Tech. Spec.
Spec. limit and the unit unit must be in Mode be in Mode 33 in in :::; 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
hour. Plausible Plausible because because ifif thethe curve curve isis read directly directly without multiplying multiplying by by 7,7, the S/G S/G tube leakage leakage will not not have have exceeded exceeded the the Tech.
Tech. Spec.
Spec. limit limit and and aa Mode Mode 33 shutdown shutdown is is required.
B.
B. Incorrect Incorrect because because S/G S/G tube tube leakage leakage has has exceeded exceeded the the Tech.
Tech. Spec.
Spec. limit limit and and the unit must be in Mode the unit must be in Mode 33 in in :::; 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
hour. Plausible Plausible because because ifif thethe curve curve isis read read directly directly without without multiplying multiplying by by 7,7, the the S/G S/G tube tube leakage leakage willwill not not have have exceeded exceeded the the Tech.
Tech. Spec.
Spec. limit limit and and aa Mode shutdown isis required.
Mode 33 shutdown required.
C.
C. Correct Correct perper the the reference.
reference. The The RCS RCS primary primary toto secondary secondary leakage leakage hashas exceeded exceeded the the Tech.
Tech. Spec.
Spec. limit limit and and thethe unit unit must must be be placed placed in in Mode Mode 33 inin :::; I1 hour hour per per 3-ONOP-071 3-0NOP-071.2. .2.
D.
D. Incorrect Incorrect because because the the unit unit must must be be inin Mode Mode 33 inin :::; 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />.
hour. Plausible Plausible because because S/G tube S/G tube leakage leakage has has exceeded exceeded the the Tech.
Tech. Spec.
Spec. limit.limit.
Page 170 Page 170
TURKEY POINT TURKEY POINT NRCNRC EXAM EXAM - 05109107
- 05/09/07 Q#86 Q#86 Unit 33 isis in Unit in Mode Mode 33 with with the reactor trip the reactor trip breakers breakers open.
open.
- A A cooldown cooldown to to Mode Mode 44 has has been been initiated.
initiated.
- 3A3A RCPRCP breaker breaker is is racked racked out out for for corrective corrective maintenance.
maintenance.
- 3B RCP is in operation.
3B RCP is in operation.
stopped.
A Normal A Normal Containment Containment Cooler Cooler (NCC)
(NCC) fails, fails, resulting resulting in in the the 3B 38 RCP RCP stator stator temperature increasing temperature increasing to 250°F.
250°F.
Which ONE Which ONE of of the following describes the following describes thethe directions directions the the SRO SRO should should give give to to the the operators operators regarding RCP operation based based on 3B RCP stator temperature reaching reaching 250°F?
A. Stop 3B RCP in accordance with 3-0NOP-041 3-ONOP-041 .1, "Reactor Reactor Coolant Pump Off-Normal" Off-Normal and close the associated pressurizer spray valve.
Suspend all operations involving RCS dilution.
B. Stop 3B RCP in accordance with 3-0NOP-041.1, 3-ONOP-041 .1, "Reactor Reactor Coolant Off-Normal. Immediately start the 3C Pump Off-Normal". 30 RCP in accordance with 3-0P- 3-OP-041 .1, "Reactor 041.1, Reactor Coolant Pump."Pump.
C. Contact the Electrical Maintenance Supervisor to authorize continued 3B 38 RCP operations. Make preparations to start 3C 30 RCP in accordance with 3-OP-041 .1, "Reactor OP-041.1, Reactor Coolant Pump."
Pump.
D. Contact the System Engineer and Operations Supervision to authorize continued 3B RCP operations. Verify 3B 4KV Bus voltage is between 3740 and 4580 volts Page 171 Page 171
TURKEY POINT TURKEY POINT NRCNRC EXAM EXAM - 05/09/07
- 05/09/07 Q #86 Q#86 ANSWER:
ANSWER: AA KA: 003A2.03 KA: 003A2.03 Ability Ability to to (a) predict the (a) predict the impacts impacts of of the the following following malfunctions malfunctions or or operations on operations on the the RCP; RCP; andand (b)
(b) based based onon those those predictions, predictions, useuse procedures procedures toto correct, control, correct, control, oror mitigate mitigate the the consequences consequences of of those those malfunctions malfunctions or or operations:
operations:
Problems associated Problems associated with RCP motors, with RCP motors, including including faulty faulty motors motors and and current, current, and and winding and bearing temperature winding and bearing temperature problems. problems. 2.7/3.1 2.7/3.1 100FR55:
10CFR55: 43.b.5 43.b.5
Reference:
Reference:
3-ONOP-041.1, Step 3-0NOP-041.1, Step 44, FOEQ page page - Step
- Step 11 &&5 SD-29, Page SD-29, Page 10 10 and and Fig.
Fig. 1I Cog Level: 22 comprehension..,
comprehension Level 22 because the SRO must
- must recognize that NCCs provide cooling to the RCP NCCs provide cooling RCP motor motor compartments compartments thereby cooling the stator and not the pump bearings. He then must understand that two NCCs cannot maintain the containment ambient temperature constant at full power, and that an increase in containment temperature will cause an increase in the stator temperatures of the RCPs, he then must recall the threshold temperature to take action and the correct action to take, New Question Response Analysis:
A. Correct per the reference.
B. Incorrect because If stator temperatures exceed 248°F, operators should stop all RCPs. They would not start the available RCP with out NCCs operating. Plausible because RCP stator temperatures will start to rise and 248°F is the temperature requiring operators to take action.
C. Incorrect because the Electrical Supervisor may only authorize operation in excess of limits for stator temperature ifif the authorization authorization isis given given before starting the RCP. IfIf stator temperatures exceed 248°F, 248°F, operators should stop all RCPs. They would not start the available RCP with out NCC operating.
operating.
D.
D. Incorrect Incorrect because because the the Electrical Electrical Supervisor Supervisor may may only only authorize authorize operation operation inin excess excess of of limits for stator limits for stator temperature temperature ifif the the authorization authorization isis given given before before starting the RCP.
starting the RCP. IfIf stator stator temperatures temperatures exceedexceed 248°F, 248°F, operators operators should should stop all stop all RCP5.
RCPs. They They would would notnot start the available start the available RCP RCP with with out out NCC NCC operating.
operating.
Page 172 Page 172
TURKEYPOINT TURKEY POINT NRC NRC EXAM EXAM - 05/09107
- 05/09/07 Q #87 Q#87 Operators are Operators are performing performing 3-EOP-ECA-1.1, 3-EOP-ECA-1 .1, "LossLoss of of Emergency Emergency Coolant Coolant Recirculation, in Recirculation," in response response to to aa LOCA LOCA and and failure failure of of both both RHR RHR pumps.
pumps.
As directed As directed by 3-EOP-ECA-1 .1, both by 3-EOP-ECA-1.1, both Containment Containment SpraySpray pumps pumps (CSPs)
(CSPs) have have been been stopped.
stopped.
The STA The reports Containment STA reports Containment pressure pressure is is 22 22 psig.
psig.
Which ONE Which ONE ofof the following describes the following describes the the correct correct procedural procedural direction direction and and the the associated BASIS?
BASIS?
A. Continue performing ECA-1.1.
ECA-1.1.
Maintain CSPs stopped in accordance with the guidance of ECA-1.1. ECA-1 .1.
Maximizes Maximizes availability of the RWST inventory RWST inventory for injection injection flow.
B. Continue performing ECA-1.1.
Start CSPs in accordance with the guidance of FR-Z.1.
Containment barrier protection is a higher priority than injection flow as long as RWST level is > 60,000 gallons.
C. Transition to FR-Z.1, "Response Response to High Containment Pressure."Pressure.
Start CSPs in accordance with the guidance of FR-Z.1.
Containment barrier protection is a higher priority than injection flow as long as RWST level is is>> 60,000 gallons.
D. Response to High Containment Pressure."
Transition to FR-Z.1, "Response Pressure.
Maintain CSPs stopped in accordance with the guidance of ECA-1.1. ECA-1 .1.
Maximizes availability of the RWST inventory for injection flow.
Page 173 Page 173
TURKEY POINT TURKEY POiNT NRC NRC EXAM EXAM - 05/09107
- 05/09/07 Q #87 Q#87 ANSWER:
ANSWER: DD KA:
KA: 006G2.4.6 006G2.4.6 As itit relates As relates to Emergency Core to Emergency Core Cooling:
Cooling: Knowledge Knowledge of of symptom symptom basedbased EOP EOP mitigation strategies.
mitigation strategies. 3.1/4.0 3.1/4.0 IOCFR55:
10CFR55: 43.b.5 43.b.5
Reference:
Reference:
3-EOP-ECA-1 .1, Step 3-EOP-ECA-1.1, Step 88 3-EOP-FR-Z.1, CAUTION 3-EOP-FR-Z.1, CAUTION Prior Prior to Step Step 8 Cog Level:
Level: 3 Analysis Level 3 because the situation will require the SRO to analyze competing priorities for the remaining remaining RWST RWST injection injection water and determine that even though a higher higher priority procedure (FR-Z-1) would start the CSPs the EOP mitigating strategy to follow is to conserve the RWST inventory to protect the core. The SRO must must understand that a transition to FR-Z.1 is required but that a caution in FR-Z.1 states that the CSPs should be operated iaw the requirements of ECA-1.1. ECA-1 .1. The SRO must relate the plant conditions and determine that maintaining the reduced injection flow established in ECA-1.1ECA-1 .1 is more of a priority than running the CSPs under these conditions even though an Orange path on the containment exists.
New Question Response Analysis:
A. Incorrect because the Orange path on containment integrity must be addressed but the EOP mitigating strategy will not run a CSPs if recirculation is not available in order to maintain injection flow for as long as possible.
B. Incorrect because the Orange path on containment integrity must be addressed but the CSPs will not be run if recirculation is not available in order to maintain injection flow for as long as possible.
C.
C. Incorrect Incorrect because the OrangeOrange path on containment integrity must be be addressed addressed but but the CSPs CSPs will not not be be run if if recirculation is not is not available available in in order order toto maintain maintain injection injection flow for asas long long asas possible.
possible. Plausible Plausible because because transition transition will be be made made toto FR-Z.1 FR-Z.1 which which will will direct direct that that the the CSPs CSPs toto be be started started unless unless the the RWST RWST is is needed needed forfor injection injection flow.
flow.
D.
D. Correct Correct per the reference per the reference Page 174 Page 174
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM- 05/09/07
- 05/09/07 Q#88 0#88 Operators are Operators are responding responding to to aa reduced reduced Intake Intake Cooling Cooling Water Water (ICW)
(ICW) flow flow due due to to Intake Cooling Intake Cooling Water Water System System leakage.
leakage.
Which ONE Which ONE of of the following describes the following describes the the effect effect (if (if any) any) on on the the Normal Normal Containment Containment Coolers (NCC5) ability to remove Coolers (NCCs) ability to remove heat heat from from the the Containment, Containment, the consequences of the consequences of that effect, that effect, and and the correct operator the correct operator response?
response?
The NCCs The NCC5 ability ability to to remove remove heat heat is:
is:
A. Containment temperatures will INCREASE degraded. Containment INCREASE toward the TS limit limit of of 125°F and 125°F and equipment equipment environmental environmental qualifications qualifications WILL WILL bebe challenged.
challenged.
Initiate Containment Initiate Containment Purge Purge in accordance with O-OP-053, "ContainmentContainment Purge System."
System.
B. degraded. Containment temperatures will INCREASE toward the TS limit of environmental qualifications 125°F and equipment environmental qualifications WILL be challenged.
Isolate the affected portion of the ICW system and establish at least one operable ICW JCW header.
C. unaffected. Containment temperatures will NOT CHANGE and equipment environmental qualifications environmental qualifications will NOT be challenged. Initiate Containment Purge in accordance with O-OP-053, "Containment Containment Purge System."
System.
D. unaffected. Containment temperatures will NOT CHANGE and equipment environmental qualifications environmental qualifications will NOT be challenged. Isolate the affected portion of the ICW system and establish at least one operable ICW header.
Page 175 Page 175
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07 Q #88 Q#88 ANSWER:
ANSWER: BB KA:
KA: 022A2.04 022A2.04 Ability to Ability to (a) predict the (a) predict impacts of the impacts the following of the following malfunctions malfunctions or or operations operations onon the the CCS; and (b) based on those predictions, CCS; and (b) based on those predictions, use use procedures procedures to to correct, correct, control, control, or or mitigate the mitigate the consequences consequences of of those those malfunctions malfunctions or or operations:
operations: Loss Loss of of service service water. 2.9/3.2 water. 2.9/3.2 10CFR55:
10CFR55: 43.b.5
Reference:
Reference:
3-ONOP-019, Step 3-0NOP-019, Step 55 RNO, RNO, SO-029, Page 8, SD-029, Page 8, SO-040, SD-040, Page Page 77 Tech Specs 3.6.1.5 & Basis Cog Level: 2 comprehension comprehension Level 2 because the operator must recognize that the ICW system provides heat removal for the CCW system which provides heat removal for containment via the Normal Containment coolers and the Control Rod Drive Mechanism coolers. The actions of several ONOPs will reduce heat loads on the system but ultimately the CCW temperatures will rise causing the containment temperature to rise.
New Question Response Analysis:
A. Incorrect because there is no procedural direction to initiate a Containment Purge. Plausible because the NCCs ability to remove heat is degraded and Containment temperatures will increase toward the TS limit of 125°F 125°F and equipment environment environmental al qualification qualificationss will be challenged and because initiating aa containment purge would reduce containment temperatures temperatures..
B. Correct per the reference C. Incorrect because the NCCs NCCs ability to remove heat heat is is degraded.
Containment Containment temperatures temperatures will increase increase andand equipment equipment environment environmental al qualification qualifications s will be be challenged and and because because there is is no no procedural procedural direction direction to initiate a Containment to initiate a Containment Purge. Purge. Plausible Plausible because because initiating initiating aa containment containment purge purge would would reduce reduce containment containment temperatures temperatures D.
O. Incorrect Incorrect because because the the NCCs NCCs ability to remove ability to remove heatheat is is degraded.
degraded. Containment Containment temperatures temperatures will will increase increase and and equipment equipment environment environmental qualifications al qualification will s will be challenged.
be challenged. Plausible Plausible because because operators operators will will Isolate Isolate thethe affected affected portion portion of the ICW of the ICW system system and and establish establish atat least least one one operable operable ICW ICW header.
Page 176 Page 176
TURKEYPOINT TURKEY POINT NRC EXAM - 05/09/07 NRC EXAM - 05/09/07 Q #89 0#89 Both units Both units are are at at 100% power with 100% power with all all systems systems inin normal normal alignment.
alignment.
- 0-OSP-075.1 1, "Auxiliary 0-OSP-075.11, Auxiliary Feedwater Feedwater Inservice Inservice Test,"
Test, is is being being performed performed toto test the test the "A" A AFW AFW pump.
pump.
RPM.
Which ONE ONE of of the the following following describes describes the correct correct Shift Manager response?
Shift Manager response?
Declare the Declare A AFW pump:
the "A" pump:
A. operable and return it to service.
service.
A AFW pump Verify "A" pump is is aligned to Train 1I to ensure compliance with the TS LCO.
B. available and return it to service A AFW pump is aligned to Train 11 to ensure compliance with the TS Verify "A" LCO.
C. inoperable and remove it from service.
Align "c" C AFW pump to Train 1I to extend the AFW TS action time from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 30 days.
D. inoperable and remove it from service.
Align "B" B AFW pump to Train 2 to extend the AFW TS action time from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 30 days.
Page 177 Page 177
TURKEY POINT TURKEY POINT NRCNRC EXAM EXAM - 05109107
- 05/09/07 Q #89 Q#89 ANSWER:
ANSWER: CC KA:
KA: G2.2.22 061 G2.2.22 061 As itit relates As relates to to the the AFW AFW system:
system: knowledge knowledge of of limiting limiting conditions conditions for for operations operations and and safety limits. 3.4/4.1 safety limits. 3.4/4.1 IOCFR55:
10CFR55: 43.b.2 43.b.2
Reference:
Reference:
3-OP-075, Section 3-0P-075, Section 7.1 7.1 0-OSP-075.1 1, Step 7.1.6.1 0-OSP-075.11, TS 3.7.1.2 TS 3.7.1.2 Actions Actions 11 and and 33 comprehension Cog: Level: 2 comprehension Level 2 because Level because the operator must must recognize recognize that 5800 RPM RPM and 300 300 gpm do not not meet the criteria for a SAT test. and the pump must be declared inoperable. Then the operator must recognize that even though either "8" B or "C" C AFW pump can be aligned to Train 1, OP-075 directs that "C" C AFW pump be aligned to Train 11 and finally it is this action that will restore 2 independent AFW trains and increase the Action Time to 30 days.
New Question Response Analysis:
A. Incorrect because the A "A" AFW pump failed to develop enough flow and must be declared inoperable and taken OOS. Plausible because the "A" A AFW pump was OOS during the Inservice Test and would normally be returned to service to Train 1 I if the test had been SAT.
B.
- 8. Incorrect because the A "A" AFW pump failed to develop enough flow and must be declared inoperable and taken OOS. Plausible because the A "A" AFW pump must be restored to service but it will be to train 11 not Train 2.
C. Correct per the reference. Operators will declare declare the A "A" AFW pumppump inoperable inoperable and remove it from service and then align C "C" AFW pumppump to Train 11 to to extend the AFW TS AFW TS action time action time from 72 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> hours to to 30 30 days.
days.
D.
D. Incorrect Incorrect because because operators operators need need toto align align C "C" AFW AFW pumppump to to Train Train I1 to to extend extend thethe AFW AFW TS TS action action time time from from 72 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> hours to to 30 30 days.
days. B AFW pump "8" AFW pump is is already already aligned aligned to to Train Train 22 but but until until C "C" pump pump is is aligned aligned to to Train Train 1,1, the the TS TS Action Action Time Time is is still still 7272 hours0.0842 days <br />2.02 hours <br />0.012 weeks <br />0.00277 months <br />.
hours. Plausible Plausible because because B AFW pump "8" AFW pump is is normally normally aligned aligned to to Train Train 2..
2 ..
Page 178 Page 178
TURKEYPOINT TURKEY POINTNRC NRCEXAM EXAM- 05/09107
- 05/09/07 Q #90 Q#90 Unit 44 isis inin Mode Unit Mode 1I with with all all systems systems operable, operable, when when the the sample sample inlet inlet temperature temperature toto Containment particulate Containment particulate and and gas gas monitors, monitors, PRMS-11/12, PRMS-11112, increases increases toto 125°F.
125°F.
Which ONE Which ONE of of the following describes the following describes the the Tech Tech Spec Spec implications implications (if (if any) any) of of this this event?
event?
The elevated inlet The elevated inlet temperature:
temperature:
A.
A. did NOT did NOTaffectop erabilityofR-affect operability 11 or of R-11 orR-12.
R-12.
The applicable The applicable Tech Tech SpecSpec LCO LCO isis satisfied.
satisfied.
B.
B. disabled R-11 disabled R-1 1 only.
only.
Verify R-12 Verify R-12 isis operable operable andand the the associated associated Tech Tech Spec Spec LCO LCO will will be be satisfied.
satisfied.
C.
C. disabled R-12 disabled R-12 only.
only.
Verify R-11R-1 1 is operable and and the associated associated Tech Spec Spec LCO LCO will be be satisfied.
D. disabled both R-11 and R-12.
Until operability of R-11 R-1 1 or R-12 R-1 2 is restored, comply with the applicable Tech Spec Action Statement.
Page 179 Page 179
TURKEY POINT NRC EXAM - 05/09/07
- 05/09/0 7 Q #90 Q#90 ANSWER: D KA: 073G2.i.33 073G2.1.33 As it relates to Process Radiation Monitoring: Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications. 3.4/4.0 10CFR55:
10CFR55: 43.b.2
Reference:
SD-068, Page 27 and Figure 20 TS 3.4.6.1 Cog Level: 2 comprehension Level 2 because the operator must recognize that skid inlet temperature rising to 125°F triggers the high temperature alarm and closes the inlet and outlet valves and stops the sample pumps. Because the sample flows through both R-11 R-1 1 and R12 R-1 1 and R-12 Ri 2 in series, both R-11 R-1 2 have lost sample flow. The TS Action Statement applies if both R-11 R-i1 and R-12 R-i2 are inoperable. If either R-11 or R-12 are satisfied, the LCO is satisfied.
New Question Response Analysis:
A. Incorrect because the high temperature disabled both R-11 R-1 I and R-12.
Plausible because if the high temperature had not disabled R-11 R-1 I and R-12, R-1 2, the applicable Tech Spec LCO would be satisfied.
B. Incorrect because the high temperature disabled both R-11 and R-12.
Plausible because if R-12 remained operable, the applicable Tech Spec LCO satisfied...
would be satisfied C. Incorrect because the high temperature disabled both R-11 and R-I2. R-12.
Plausible because if R-1R-111 remained operable, the applicable Tech Spec LCO would be satisfied.
D. Correct per the reference. The elevated inlet temperature disabled both R- R R-1 2. Until operability of R-11 11 and R-12. R-1 I and R-12 R-1 2 is restored, comply with the applicable Tech Spec Action Statement.
180 Page 180
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09/07
- 05/09/07
- 91 Q #91 Q
Unit 33 is Unit at 100%
is at power with 100% power with all systems in all systems in normal normal alignment alignment and and control control rods rods fully fully withdrawn.
withdrawn.
- Annunciator F F 4/6, RPIS RPIS POWER POWER TROUBLE, alarms.
- 3D01 supply The field operator reports that the 3D01 supply breaker breaker to the RPI RPI inverter has tripped open.
has open.
Predict the impact of this failure on the rod position indication (RPI) system and the actions required.
RPls will be powered from the GVT: CVT:
A. automatically, and the RPI indication may have changed.
3-ONOP-028.1, "RGG Initially implement 3-0NOP-028.1, RCC Misalignment."
Misalignment.
Then transition to 3-0NOP-028.2, 3-ONOP-028.2, "RGG RCC Position Indication Malfunction."
Malfunction.
B. after manual transfer, and the RPI indication may have changed.
3-ONOP-028.2, "RGG Initially Implement 3-0NOP-028.2, RCC Position Indication Malfunction."
Malfunction.
C.
G. automatically, and the RPI indication will NOT change.
3-ONOP-028.2, "RGG Initially Implement 3-0NOP-028.2, RCC Position Indication Malfunction."
Malfunction.
D. after manual transfer, and the RPI indication will NOT change.
3-ONOP-028.1, "RGG Initially implement 3-0NOP-028.1, Misalignment.
RCC Misalignment."
Then transition to 3-ONOP-028.2, 3-0NOP-028.2, RCC "RGG Position Indication Malfunction."
Malfunction.
Page 181 Page 181
TURKEY POINT NRC EXAM - 05/09107
- 05/09/07 Q #91 ANSWER: A KA: 014A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: loss of power to the RPls. 3.1/3.6 IOCFR55:
10CFR55: 43.b.5
Reference:
SD-006 Page 11 and Figure 5, SO-006 3-ONOP-028.1, Step 1.1, 5.6 3-0NOP-028.1, 3-ONOP-028.2, Step 1.1, 5.3 3-0NOP-028.2, 3-ARP-097.CR, F 4/6 3-ONOP-028.2 Basis - NOTE before Step 5.3 and Step 5.3 3-0NOP-028.2 Cog Level: 1 Recall 1
New Question Response Analysis:
A. Correct per the reference B. Incorrect because the RPI power supply has auto-transferred from the inverter to the CVT. Plausible because the RPls may indicate different than before the power interruption and operators will Initially implement 3-0NOP-3-ONOP-RCC Misalignment,"
028.1, "RCC Misalignment, then transition to 3-0NOP-028.2, 3-ONOP-028.2, "RCCRCC Position Malfunction.
Indication Malfunction."
C. Incorrect because ONOP-028.2 is not a direct entry procedure and station CE has demonstrated that the output voltage of the CVT is different than the OE inverter resulting in all RPls indicating differently after transfer. Operators must first perform actions of ONOP-028.1 and then transition to ONOP-028.2 when directed. Plausible because The RPI power supply has auto- auto C\IT.
transferred from the inverter to the CVT.
D.
O. Incorrect because the RPI power supply has auto-transferred from the inverter to the CVT and because OE CE has demonstrated that the output voltage of the CVT is different than the inverter resulting in all RPls RPIs indicating differently after transfer .
Page 182
TURKEY POINT TURKEY POINT NRC NRC EXAM EXAM - 05/09107
- 05/09/07 Q #92 0#92 The following event occurs:
- . ARMS Channel 15, Aux Bldg North N/S Corridor, alarms.
Which ONE of the following describes the correct order of response directed by the SRO?
A. Evacuate persons in the affected area.
Silence the alarm.
Verify the alarm is valid at the ARMs control panel.
Notify HP to survey the area.
B. Verify the alarm is valid at the ARMs control panel.
If the alarm is valid then evacuate persons in the affected area.
Notify HP to survey the area.
Silence the alarm.
C. Silence the alarm.
Verify the alarm is valid at the ARMs control panel.
If the alarm is valid then evacuate persons in the affected area.
Notify HP to survey the area.
D. Notify HP to survey the area.
Silence the alarm.
Verify the alarm is valid at the ARMs control panel.
If the alarm is valid then evacuate persons in the affected area.
Page 183 Page 183
TURKEY POINT NRC EXAM - 05/09/07 Q #92 Q#92 ANSWER: B KA: 072G2.1.14 As it relates to Area Radiation Monitoring: Knowledge of system status criteria which require the notification of plant personnel. 2.5/3.3 IOCFR55:
10CFR55: 43.b.4, 43.b.5
Reference:
O-ONOP-066, Steps 2, 3, 5, and 7 0-ONOP-066, Cog Level: I Recall 1
New Question Response Analysis:
A. Incorrect because the alarm should be verified valid before evacuating persons from the area and we don't dont silence the alarm until after HP has surveyed the area. Plausible because we do verify the alarm is valid and evacuate persons before HP is dispatched to survey and before the alarm is silenced.
B. Correct per the references. The SRO will direct the RO to verify the alarm is valid at the ARMs control panel. If the alarm is valid then operators will evacuate persons in the affected area and then notify HP to survey the area and finally silence the alarm.
C. Incorrect because the alarm is valid. Plausible because the alarm may be silenced if the alarm is determined to not be valid and because Radiation Protection will subsequently be called to survey the area.
D. Incorrect because the alarm is valid. Plausible because the alarm may be silenced if the alarm is determined to not be valid and because Radiation Protection will subsequently be called to install a portable radiation monitor.
Page 184
TURKEY POINT NRC EXAM - 05/09107 05/09/07 Q #93 Q#93 Operators are responding to a large break LOCA when the ST A reports the STA following QSPDS Core Exit Thermocouple readings:
Quad 1 1 Quad 2 Quad 3 Quad 4 CET Temp CET Temp CET Temp CET Temp R7 660 K5 1250 H8 415 Ku K11 666 P8 590 K3 ??? F9 835 N15 680 N6 604 J2 2300 E8 ??? H13 602 N4 625 G6 675 BlO B10 905 H9 615 Mu M11 ??? GI G1 1560 B5 660 E14 622 M9 ??? F5 2300 E12 688 L8 670 F3 1780 Which ONE of the following describes the core condition and the direction the SRO will give to the crew?
CET5 J2 and F5:
CETs A. should be included in the core condition evaluation.
A Red Path exists.
Response to Inadequate Core Cooling."
Transition to 3-EOP-FR-C.1, "Response Cooling.
B. should be included in the core condition evaluation.
An Orange Path exists.
Transition to 3-EOP-FR-C.2, "Response Response to Degraded Core Cooling."
Cooling.
C. should NOT be included in the core condition evaluation.
A Red Path exists.
Transition to 3-EOP-FR-C.1, "Response Response to Inadequate Core Cooling."
Cooling.
D. should NOT be included in the core condition evaluation.
An Orange Path exists.
Transition to 3-EOP-FR-C.2, "Response Response to Degraded Core Cooling."
Cooling.
Page 185
PO1ISJT NRC EXAM - 05/09/07 TURKEY POINT - 05/09/0 7 Q #93 Q#93 ANSWER: A KA: 017A2.02 017 A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the ITM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Core Damage 3.6/4.1 IOCFR55:
10CFR55: 43.b.5
Reference:
3-EOP-F-0, Enclosure 2 and Basis Page 20 Cog Level: 3 Analysis Level 3 because the operator must analyze all of the core temperature data and then recall that the evaluation is based on the five highest CETs including the failed CETS and that threshold for Red Path is 1200°F (Orange Path = = 700°F). Review of the QSPDS readings reveals that including the failed CETs reveals a Red Path Condition and FR-C.1 needs to be implemented. This must be determined even CET5 are not included, five CETs are greater than 700°F though that if the failed CETs and the operator will conclude erroneously that only an Orange Path exists.
New Question Response Analysis:
A. Correct per the references B. Incorrect because a Red Path exists and transition should be made to 3EOP-FR-C.1, "Response 3-EOP-FR-C.1, Response to Inadequate Core Cooling."
Cooling. Plausible because EOP-FRC.2 is the correct the conditions for an Orange Path also exist and EOP-FR-C.2 procedure to transition for an Orange Path.
C. Incorrect because the failed CETs should be included in the evaluation.
Plausible because a Red Path exists and operators should transition to 3-Response to Inadequate Core Cooling."
EOP-FR-C.1, "Response Cooling.
D. CET5 should be included in the evaluation.
Incorrect because the failed CETs Plausible because the conditions for an Orange Path also exist and EOP-EOP FR-C.2 is the correct procedure to transition for an Orange Path.
Page 186
TURKEY POINT NRC EXAM - 05/09107
- 05/09/07 Q #94 Q#94 With Unit 3 at 80% power, operators are responding to a Xenon oscillation. The RD reports the following values of Axial Flux Difference (AFD):
- N-41 N-41:: +13
- N-42: +12
- N-43: +16
- N-44: + 17
+17 reactors AFD and the Which ONE of the following describes the condition of the reactor's direction the SRO should give the RO RD regarding these conditions?
The reactor AFD is:
A. within the operational space.
Operation at this power level may continue indefinitely.
B. within the operational space.
Use dilution and manual rod control to restore AFD to within the operational space on all power range channels within 15 minutes.
c.
C. outside the operational space.
Use dilution and manual rod control to restore AFD to within the operational space on at least 3 power range channels within 15 minutes.
D. outside the operational space.
Use boration and manual rod control to restore AFD to within the operational space on at least 3 power range channels within 15 minutes.
REFERENCE PROVIDED Page 187
TURKEY POINT NRC EXAM - 05/09107
- 05/09/07 Q #94 Q#94 ANSWER: C KA: G2.1.7 G2.I.7 Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation. 4.4 IOCFR55:
10CFR55: 43.b.5
Reference:
PCB Section 5, Figure 1AIA &
& Section 7, Figure 1 I O-ADM-536, Attachment 1, Section 3/4.2 3-ARP-097.CR, G G 5/1 5/I
- 3-ONOP-059.4, Step 2 3-0NOP-059.4, Cog Level: 2 comprehension Level 2 because the operator will have to plot the given AFD values on the reference provided. Then the operator will have to recognize that 2 values are outside the operational space. 2 of the 4 values outside implies that AFD is out of the operational space. The operator will then have to recall that dilution and rod control are the prescribed methods to return to the operational space when out on the high side.
New Question Provide PCB Section 5, Figure 1 IA as references 1 & 1A Response Analysis:
A. Incorrect because the AFD is outside the operational space. Plausible because 2 of the four AFD values are within the operational space and if AFD was within the operational space, operation at this power level may continue indefinitely.
B. Incorrect because the AFD is outside the operational space. Plausible because dilution and rod control would be the prescribed method to restore all channels within the operational space if out on the high side.
C. Correct per the references. The reactor AFD is outside the operational space. Operators will use dilution and manual rod control to restore AFD to within the operational space on at least 3 power range channels within 15 minutes.
D. Incorrect because dilution and rod control is the prescribed method to restore AFD within the operational space when out on the high side. Plausible because the AFD is outside the operational space.
Page 188
TURKEY POINT NRC EXAM - 05/09107
- 05/09/07 Q #95 Q#95 The following plant conditions exist:
- 400° F.
Unit 3 RCS temperature is 400°F.
- 31 0°F.
Unit 4 RCS temperature is 310°F.
For the above conditions, which ONE of the following identifies the minimum required water inventory in the Condensate Storage Tank system and describes the basis for that required inventory?
A. 210,000 gallons.
Ensures sufficient water to maintain Unit 3 at Hot Standby condition for a minimum of 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />.
B. 210,000 gallons.
Ensures sufficient water to maintain Unit 4 at Hot Standby condition for a minimum of 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />.
C. 420,000 gallons.
This is sufficient water to maintain both Units at these conditions for a minimum of 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> and then cool down both reactor coolant systems to Mode 4.
D. 420,000 gallons.
This is sufficient water to maintain both units at these conditions for a minimum of 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />.
Page 189
TURKEY POINT NRC EXAM - 05/09/07 Q#95 ANSWER: A KA; G2.1.32 Ability to explain and apply all system limits and precautions. 3.8 100FR55:
10CFR55: 43.b.2
Reference:
3-OP-018.1, Step 4.2 3-0P-018.1, Tech Specs Table 1.2 and 3.7.1.3 0-ADM-536, Section 3/4.7.1.3 Cog Level: 2 Comprehension V Level 2 because the operator must evaluate the RCS temperatures provided and determine that Unit 3 is in Mode 3 and Unit 4 is in Mode 4. Only after this determination is made can the operator apply the correct Tech. Specs.
New Question Response Analysis:
A. Correct per the reference B. Incorrect because there is sufficient water to maintain only Unit 3 at these hours: Unit 4 would be on RHR at this conditions for a minimum of 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.
temperature and its AFW system valved out. Plausible because 210,000 gallons is the required amount of water inventory in the CSTs.
C. Incorrect because only 210,000 gallons is the required amount of water inventory in the CSTs and Unit 3 is the only unit that would need CST water because Unit 4 would be on RHR at this temperature and its AFW system valved out. Plausible because the numbers shown are the numbers provided by the Tech Spec Basis document.
D. Incorrect because only 210,000 gallons is the required amount of water CST5 and Unit 3 is the only unit that would need CST water inventory in the CSTs because Unit 4 would be on RHR at this temperature and its AFW system valved out. Plausible because the numbers shown are the numbers provided by the Tech, Tech Spec Basis document.
Page 190
TURKEY POINT NRC EXAM - 05/09/07 Q #96 0#96 Both Units are at 100% power.
The 3A EDG is out of service and a 14 day Tech Spec Action Statement is in effect for Unit 3.
ECO requests have been submitted by Maintenance to remove the following equipment from service:
- 3A Containment Spray Pump
- 3A Emergency Containment Filter
- 3A Residual Heat Removal Pump
- Pressurizer Heater Control Group If taken out of service, which ONE of the following components from the list above would reduce the Unit 3 effective Tech Spec Action Time from the current 14 days to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />?
A. 3A Containment Spray Pump B. 3A Emergency Containment Filter C. 3A Residual Heat Removal Pump D. Pressurizer Heater Control Group Page 191
TURKEY POINT NRC EXAM - 05/09/07 Q#96 Q #96 ANSWER: B B
KA: G2.2.24 Ability to analyze the effect of maintenance activities on LCO status. 3.8 10CFR55:
10CFR55: 43.b.2
Reference:
TS 3.8.1.1, Action d.1 O-OSP-023.3, Step 6.1.2 and Attachment 2 Step 8 Cog Level: 2 comprehension Level 2 because the operator must recognize that the 3A ECF is a Train B B safety component and then determine the impact of that piece of equipment being out of service during the maintenance activity. The SRO must analyze that this reduced the Action time to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> if the operators placed a Train B safety component OOS while the 3A EDG is OOS.QOS.
New Question Response Analysis:
A. Incorrect because 3A Containment Spray Pump is Train A equipment and being out of service will not shorten the TS Action time from the 14 days associated with the EDG to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Plausible because taking the 3A CSP QOS will introduce an additional TS Action time to comply with but it will be OOS 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, not 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
B. Correct per the reference C. Incorrect because 3A Residual Heat Removal Pump is Train A equipment and being out of service will not shorten the TS Action time from the 14 days associated with the EDG to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Plausible because taking the 3A RHRP OOS will introduce an additional TS Action time to comply with but it will be 7 days, not 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
D. Incorrect because the pressurizer control group heaters are Train A equipment and being out of service will not shorten the TS Action time from the 14 days associated with the EDG to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Plausible because while the control group heaters do not have a Tech Spec LCO, the BU Group "An A heaters which are also Train "An A equipment do and taking the BU Group "An A heaters OOS DOS will introduce an additional TS Action time to comply with but it will be 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, not 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Page 192
TURKEY POINT NRC EXAM - 05/09/07 Q #97 Q#97 Which ONE of the following activities REQUIRES direct supervision by a licensed Senior Reactor Operator?
A. Underwater TV camera surveillance in the refueling cavity B. Reactor vessel irradiation specimen removal C. Lower internals removal D. Control rod unlatching Page 193 193
TURKEY TURKEY POiNT POINT NRC NRC EXAM 05/09/07 EXAM - 05/09/07 Q#97 Q #97 ANSWER: D D
KA: G2.2.27 Knowledge of the refueling process. 3.5 10CFR55:
100FR55: 43.b.6/b.7 43.b.61b.7
Reference:
4-0P-038.1, Step 4.1 &
4-OP-038.1, & Section 4.6 Cog Level: I1 recall Bank Question Response Analysis:
A. Incorrect because underwater TV camera surveillance in the refueling cavity is not considered a Core Alteration and as such does not require direct supervision by an SRO. Plausible because this activity typically occurs directly over the core while the upper internals are removed and irradiated fuel in place.
B. Incorrect because reactor vessel irradiation specimen removal is not considered a Core Alteration and as such does not require direct supervision by an SRO. Plausible because this activity occurs directly over the reactor while the reactor head is removed.
C. Incorrect because lower internals removal is not considered a Core Alteration and as such does not require direct supervision by an SRO.
Plausible because this activity occurs directly over the reactor while the reactor head and upper internals are removed.
D. Correct per the reference Page 194 Page 194
TURKEY POINT NRC EXAM - 05/09107
- 05/09/07 Q #98 Q#98 Core off-load is in progress on Unit 3.
- One fuel assembly is latched on the manipulator crane.
- Another fuel assembly is vertical in the upender on the Spent Fuel Pit side.
A refueling cavity seal failure occurs and cavity level begins decreasing rapidly.
Which ONE of the following describes the correct directions the SRO should give to the refueling operators?
A. Insert the assembly on the manipulator into the core and leave it latched.
Lay the assembly in the upender down and leave it in the transfer cart.
B. Insert the assembly on the manipulator into the core and unlatch it.
Relatch the assembly in the upender and move it to a fuel rack.
C. Do NOT Insert the assembly on the manipulator into the core but move it to the edge of the core and leave it suspended.
Lay the assembly in the upender down and leave it in the transfer cart.
D. Do NOT Insert the assembly on the manipulator into the core but move it to transfer canal.
Relatch the assembly in the upender and move it to a fuel rack.
Page 195
TURKEY POINT NRC EXAM 05109/07 EXAM - 05/09/0
- 7 Q#98 Q #98 ANSWER: A KA: G2.3.10 G2.3.1O Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure. 3.3 10CFR55:
IOCFR55: 43.b.41b.7 43.bA/b.7
Reference:
3-0NOP-033.2, Step 5.1.2, 5.1.3 & NOTE Prior to Step 5.2.4 3-ONOP-033.2, Cog Level: 11 Recall New Question Response Analysis:
A. Correct per the reference.
B. Incorrect because the operator should lay the assembly in the upender down and leave it in the transfer cart. Plausible because operators should insert the assembly on the manipulator into the core but should leave it latched.
C. Incorrect because operators should insert the assembly on the manipulator into the core and leave it latched. Plausible because the operator should lay the assembly in the upender down and leave it in the transfer cart.
D. Incorrect because operators should insert the assembly on the manipulator into the core and leave it latched and because the operator should lay the assembly in the upender down and leave it in the transfer cart. Plausible because unlatch the assembly held by the manipulator and relatching the assembly in the upender and move it to a fuel rack are both workable options open to the operators but neither is directed by ONOP-033.2.
196 Page 196
TURKEY POINT NRC EXAM - 05/09/07 0#99 Q #99 Unit 33 has experienced aa loss of offsite power (LOOP).
- 3A EDG locked out and can NOT be restarted.
- SI was NOT required and did NOT occur.
- Pressurizer level is stable.
- Reactor head and plenum RVLMS indicates full.
The SM has determined the Unit must be placed in MODE 5.
Which ONE of the following describes the mitigation strategies that should be implemented by the SRO per the EOP network for the present plant conditions?
A. 3-EOP-ES-O.2,, "Natural Transition to 3EOP-ES-0.2 Natural Circulation Cooldown.
Cooldown".
Limit cooldown rate to 25°F/hr and maintain RCS subcooling ~ 80°F to avoid the possibility of thermal shocking the reactor vessel.
B. Natural Circulation Cooldown.
3-EOP-ES-O.2, "Natural Transition to 3-EOP-ES-0.2, Cooldown".
Limit cooldown rate to 25°F/hr and maintain RCS subcooling ~ 226° 226°FF to avoid the possibility of reactor vessel head void formation.
C. Transition to 3-EOP-ES-O.3, Natural Circulation Cooldown with Steam Void 3-EOP-ES-0.3, "Natural in Vessel (with RVLMS)".
RVLMS).
Limit cooldown rate to 1 OO°F/hr and maintain RCS subcooling ~ 80°F to 100°F/hr avoid the possibility of thermal shocking the reactor vessel.
D. Transition to 3-EOP-ES-O.3, 3-EOP-ES-0.3, "Natural Natural Circulation Cooldown with Steam Void in Vessel (with RVLMS)".
RVLMS).
OO°F/hr and maintain RCS subcooling ~ 226°F to Limit cooldown rate to 1100°F/hr limit reactor vessel head void growth.
197 Page 197
TURKEY POiNT TURKEY POINT NRC NRC EXAM - 05/09/07 EXAM - 05/09/07 Q#99 Q #99 ANSWER:
ANSWER: BB KA KA G2.4.7 G2.4.7 Knowledge of of the event event based based EOPEOP mitigation strategies. 3.83.8 10CFR55:
10CFR55: 43.b.5 43.b.5
Reference:
10.a, 17.a.RNO, 3-EOP-ES-0.2, Step 1O.a, 17.a.RNO, 18 18 bb & c Cog Level: 22 Comprehensive Cog Comprehensive Level 22 because the SRO must relate the loss loss of the 3A 4KV bus to the present plant conditions and determine that only one CRDM cooling fan is available. He then must relate this knowledge to the effects the CRDM cooling fans have on aa natural circulation cooldown and determine that the lower cooldown rates and much higher subcooling numbers must be applied for the given plant conditions as heat removal from the reactor head is diminished with only one CRDM fan.. fan ..
New Question Response Analysis:
A. Incorrect because operators should maintain RCS subcooling ~ 226°F 226° F to avoid the possibility of reactor vessel head void formation. Plausible because operators should limit the RCS cooldown rate to 25°F/hr.
B. Correct per the reference C. Incorrect because operators should limit the RCS cooldown rate to 25°F/hr and maintain RCS subcooling ~ 226°F to avoid the possibility of reactor subcooling>
vessel head void formation. Plausible because maintaining subcooling >
80°F is an appropriate strategy if both CRDM coolers are in operation and 100°F/hour is the normal cooldown rate limit.
D. Incorrect because operators should limit the RCS cooldown rate to 25°F/hr Plausible because operators should maintain RCS subcooling ~ 226°F to 100°F/hour is avoid the possibility of reactor vessel head void formation and 100°F/hour the normal cooldown rate limit.
Page 198 Page 198
TURKEY POiNT TURKEY POINT NRC NRC EXAM 05109/07 EXAM - 05/09/07 Q#100 Q#100 Unit 44 has Unit has experienced experienced aa large break LOCA.
large break LOCA.
damage.
There is no indication of current or projected severe core damage.
The RO reports containment pressure has peaked at 28 psig.
Emergency Coordinator (EC) has NOT yet received any indication of potential The Emergency radioactive releases from Containment.
Which ONE of the following describes the Protective Action Recommendation (PAR) the EC should make during initial contact with the State?
A. No PAR should be made until confirmation of aa radioactive release is made.
B. Shelter all persons within aa 22 mile radius of the site and shelter all persons out to 55 miles in the downwind sectors.
C. Evacuate all persons within a 22 mile radius of the site and shelter all persons out to 55 miles in the downwind sectors.
D. Evacuate all persons within a 2 mile radius of the site and evacuate all persons out to 5 miles in the downwind sectors.
REFERENCE PROVIDED 199 Page 199 Page
TURKEYPOINT TURKEY POINTNRC EXAM - 05/09/07 NRCEXAM -
05/09107 QQ #100
- 100 ANSWER:
ANSWER: BB KA:
KA: G2.4.44 G2.4.44 Knowledge of of Knowledge emergency emergency plan plan protective action recommenda protective action recommendations. tions. 4.04.0 10CFR55:
100FR55: 43.b.5 43.b.5
Reference:
Reference:
3-EPIP-201 01, 3-EPIP-2010 Enclosure 1, 1, Enclosure 1, Category (General Emergency)
Category 11 (General Emergency) 3-EPIP-201 01, Step 3-EPIP-20101, Step 5.1.4 5.1.4 3-EPIP-201 01, 3-EPIP-2010 Attachment 3, 1, Attachment Page 11 of 3, Page of 66 Cog Level:
Cog Level: 22 comprehensi comprehension on Level 22 because Level because the the operator operator must determine that must determine combination of the combination that the large break of aa large break LOCA with LOCA with 28 28 psig inside inside containment containment as as classifiable classifiable as as a a General General Emergency.
Emergency.
Then the operator must must recall that the minimum classification for aa GE, GE, even "Shelter all persons within aa 22 mile radius of the site and shelter without aa release is Shelter without all persons out to 55 miles in downwind sectors.
in the downwind sectors."
Provide EPIP-20101, Enclosure I1 as aa Reference Provide New Question New Question Response Analysis:
A.
A. Incorrect because the EC should issue the PAR to shelter all persons within a 2 mile radius of the site and shelter all persons out to 5 miles in the downwind sectors. Plausible Plausible because there is no indication of potential Containment.
radioactive releases from Containment.
B.
B. Correct Correct perper the the reference.
reference. Minimum Minimum PARs PARs for a GE should be made: Shelter be made:
all all persons persons within within aa 22 mile mile radius radius of the site of the and shelter site and all persons shelter all persons out to 55 out to miles in miles in the the downwind downwind sectors sectors C.
C. Incorrect Incorrect because because the the ECEC should issue the should issue PAR to the PAR shelter all to shelter all persons within persons within aa 22 mile mile radius radius of of the the site site and and shelter shelter all out to 5 miles persons out to 5 miles in the all persons in the downwind downwind sectors.
sectors. Plausible Plausible because because evacuation evacuation could be could considered more be considered more conservative conservative than sheltering inin the than sheltering event of a General the event of a General Emergency. Emergency.
D.
D. Incorrect Incorrect because because the the EC EC should issue the should issue PAR to the PAR shelter all to shelter all persons within persons within aa 22 mile mile radius radius of of the the site site and and shelter shelter all persons out all persons out to 5 miles in to 5 miles in the the downwind sectors.
downwind sectors. Plausible Plausible because because evacuation evacuation could could be considered more be considered more conservative conservative than than sheltering the event sheltering inin the of General Emergency.
event of aa General Emergency.
200 Page200 Page