ML101590396: Difference between revisions

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{{#Wiki_filter:NRC DRAFT                              07/24/07 07124/07 Q#1 0#1 100% power with all systems in normal alignment except for 3A S/G Unit 3 is at 100%                                                                SIG level transmitter, LLT-3-474 T-3-474 (red channel) which has failed LOW.
{{#Wiki_filter:}}
3-ONOP-049.1, Operators have tripped associated bistables in accordance with 3-0NOP-049.1, Deviation "Deviation  or  Failure of Safety Related or Reactor  Protection Channels.
Channels."
Subsequently, 3A S/G feed flow transmitter, FT-3-477 (blue channel), fails LOW.
Which ONE of the following describes the correct operator response?
A.                3-ONOP-049.1 again and trip all bistables associated with Perform 3-0NOP-049.1 FT-3-477.
B.                3-ONOP-049.1 again and trip all bistables associated with FT-3-477 Perform 3-0NOP-049.1 FW to SF Mismatch Logic" except for the "FW                    Logic bistable, BS-3-478B-1.
BS-3478B-1.
C.      Declare Unit 3 is in TS 3.0.3 and be in Hot Standby within 7 hours.
D.                                                      Reactor Trip or Safety Trip the reactor and transition to 3-EOP-E-0, "Reactor Injection Injection"
 
NRC DRAFT NRC      DRAFT                                  07/24/07 07/24/07 QQ#1
  #1 ANSWER:
ANSWER:            DD KA: 000007EA2.02 KA:    000007EA2.02 Able to Able  to determine determine or  or interpret interpret following following as as 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 IOCFR55:
10CFR55:          41.b.5, 41.b.7, 41.b.5,    41.b.7, 41.b.10 41.b.1O
 
==Reference:==
5610-T-L1, 5610-T-L    1, Sheet 22 5610-T-L1, 5610-T-L      Sheet 19 1, Sheet  19 5610-T-D-17    , Sheet 1 5610-T-D-17,Sheet1 3-ONOP-049.1, Pages 3-0NOP-049.1,        Pages 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-EO.
EOP-E-O. Plausible, because this is the normal response to aa failure of FT-3-477 if a reactor trip signal had not been generated  generated.
B.      Incorrect because the reactor should have tripped. Operators should transition to EOP-E-O. Plausible, because this is the response to aa failure of FT-3-477 following aa failure of    of LT-3-474 LT-3-474 ifif aa reactor trip signal hadhad not not been been generated.
generated.
C.
C.      Incorrect Incorrect because because the the reactor should should have have tripped.
tripped. Operators Operators should should transition transition to to EOP-E-O.
EOP-E-O. Plausible, Plausible, because because the  the unit unit would would be    in TS be in  TS 3.03 3.03 ifif the the reactor had      not tripped.
had not  tripped.
D.
D.      Correct Correct per      the references.
per the  references. TheThe reactor reactor should should havehave tripped tripped as as aa result result ofof the  Low    S/G  level with  steam the Low S/G level with steam flow/feedflow/feed flow flow mismatch mismatch signal signal generated generated by  by the FT-3-477 the  FT-3-477 failure.
failure.
92
 
NRC DRAFT NRC      DRAFT                            07/24/07 07/24/07 Q#2 0#2 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      performing 3-EOP-ES-1.2, are performing    3-EOP-ES-1 .2, "Post Post LOCA LOCA Cooldown Cooldown andand Depressuriza tion.
Depressurization.
**  RCS subcooling RCS  subcooling isis less less than than the  minimum required.
the minimum    required.
**  With RCS With  RCS T-hot T-hot less less than than 350°F, 350° F, operators operators start start one one RHR    pump and RHR pump    and stop stop one one HHSI pump.
HHSI  pump.
following describes Which ONE of the following        describes the effect of starting starting the the RHR RHR pump pump andand stopping the HHSI HHSI pump?
pump?
A.
A.      Secondary heat sink will be improved by RHR flow collapsing reactor head voids after stopping the HHSI pump.
B.      RCS subcooling will decrease after stopping the HHSI pump until the RHR pumps injects into the RCS.
C.      Subsequent steam generator U-tube cooldown will be enhanced by the addition of RHR flow through the steam generators.
D.      RCS subcooling will NOT be affected by stopping the HHSI pump because the RHR pump is already injecting into the RCS.
33
 
NRC DRAFT NRC        DRAFT                                  07/24/07 07/24/07 Q#2 Q#2 ANSWER:
ANSWER:        BB KA:
KA:              000008AK3.05 000008AK3.05 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 PRZ PRZ vapor  space  accident: ECCS vapor space accident:        ECCS terminating terminating or  or throttling throttling criteria.
criteria. 4.0/4.5 4.0/4.5 IOCFR55:
10CFR55:        41.b.5, 41.b.7, 41.b.5,    41.b.7, 41.b.8, 41.b.8, 41.b.10 41.b.10
 
==Reference:==
 
==Reference:==
3-EOP-ES-1.2, Step 3-EOP-ES-1.2,      Step 17 17 BOBD Cog Level:
Cog  Level:    2 Comprehension Comprehension Level 2 because the operator must analyze plant conditions and apply thermodynamic principles thermodynamic      principles to determine the effect starting and stopping various 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 reason given 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.
C.      Incorrect because the addition of RHR flow will not            not significantly increase increase flow though though thethe S/Gs  and this is S/Gs and          is not not the the reason givengiven by  by the reference.
Plausible because S/G  S/G U-tube U-tube cooldown would  would be  be enhanced enhanced by  by additional additional cooling cooling  flow.
D.
O.      Incorrect Incorrect because because the the pressure pressure mustmust drop drop until until itit is is less less than than the the RHR RHR pumppump shutoff shutoff head.
head. Thus Thus subcooling subcooling must must decrease decrease whenwhen the  the HHSI HHSI pump pump is is shut shut off.
off.
44
 
NRC DRAFT NRC      DRAFT                                07124/07 07/24/07 Q#3 Q#3 Operators are Operators    are responding responding to to aa large large break break LOCA LOCA on    Unit 4.4.
on Unit
** When When thethe BOP BOP attempts attempts to to reset reset 81 SI on on VPB, VPB, aa circuit circuit failure failure occurs occurs andand the the 81 SI signal CANNOT signal  CANNOT be    be reset.
reset.
**  Operators have Operators    have transitioned transitioned to to 4-EOP-E8-1.3, 4-EOP-ES-1 .3, "Transfer Transfer to to Cold Cold Leg Leg Recirculation    and    expect Recirculation" and expect to    to subsequently subsequently establish establish "piggy-back" piggy-back recirc recirc alignment.
alignment.
Which ONE Which  ONE of of the the following following describes describes the the effect effect of  being unable of being    unable to to reset reset 81?
SI?
A.
A.      The running The  running RHR RHR pump(s) pump(s) can can NOT NOT be  stopped preventing be stopped    preventing operators operators from from closing RHR closing  RHR pump pump suction suction valves, valves, MOV-4-862A MOV-4-862A &    & B.B.
B.
B.      Once stopped, Once    stopped, thethe RHR RHR pump(s) can NOT    NOT bebe restarted until until the 81 SI signal isis reset.
C.      RHR discharge to cold leg isolation valves, MOV-4-744A &                & B, can NOT be closed requiring local closure of BOTH RHR heat exchanger manual outlet valves, 4-759A & B.
D.      RHR discharge to cold leg isolation valves, MOV-4-744A &                & B, can NOT be closed requiring local closure of EITHER RHR heat exchanger manual outlet valve, 4-759A or B.
55
 
NRCDRAFT NRC        DRAFT                                    07/24/07 07/24/07 Q#3 Q#3 ANSWER:
ANSWER:          CC KA:
KA:              00001IEA2.0 000011      EA2.022 Able to Able  to determine determine and  and interpret interpret the the following following as  as they they apply apply toto aa LBLOCA:
LBLOCA:
Consequence Consequences to    s  to RHR RHR of of not not resetting resetting SI.
SI. 3.3/3.7 3.3/3.7 10CFR55:
10CFR55:          41.b.7 41.b.7
 
==Reference:==
 
==Reference:==
4-EOP-ES-1.3, Step 4-EOP-ES-1.3,            Step 19 19 RNO RNO 5613-M-3050, Sheet 5613-M-3050,            Sheet 11 5610-T-L1, 5610-T-L          Sheet 11 1, Sheet      11 Cognitive Level:
Cognitive    Level: 22 Comprehension Comprehension Level 22 because Level      because the  the operator operator must must understand understand integrated integrated plant plant operations, operations, interlocks interlocks    and  response not response      not obtained actions to recognize  recognize the effect of not    not being able to reset SI. Once recognized that the 744 valves cannot be closed, the able operator must determine the correct response to close both RHR HX outlet valves operator EOP-ES-1 .3, Step 19.
per EOP-ES-1.3, New Question New
 
===Response===
Response Analysis:
A.      Incorrect becaus because  e the running RHR pumps can be stopped by placing their control switches in Pull-to-Lock Pull-to-Lock.. Plausible, because there is aa continuous start start signal    to the RHR pumps as aa result of            of the active SI signal present.
B.
B.      Incorrect Incorrect becaus because  e the the running RHR  RHR pumps pumps can be    be manually manually started from VPB.
VPB. Plausible, Plausible, because because the  the RHR RHR pumps pumps can  can be be stopped stopped by  by placing placing their their control  switches      in  Pull-to-Lock control switches in Pull-to-Lock..
C.
C.      Correct Correct per per thethe references.
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-E EOP-ES-  S 1.3, 1.3, Step Step 19 19 RNO RNO requires requires closure closure of of bothboth RHR RHR heat heat exchanger exchanger outletoutlet valves.
valves.
D.
D.      Incorrect Incorrect becaus because  e IfIfthe the valves valves cannot cannot be  be closed, closed, EOP-ES-1.3, EOP-ES-1.3, Step  Step 19 19 RNO RNO requires requires closure closure of of both both RHRRHR heatheat exchanger exchanger outlet outlet valves, valves, not notjust just one.
one.
Plausible Plausible becaus because  e IfIfSISI 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.
66
 
NRCDRAFT NRC      DRAFT                              07/24/07 07/24/07 Q#4 0#4 Unit33 isisatat100%
Unit              100% power powerwhen  when annunciator annunciator8B2/5, 2/5, RCP RCP 8B OIL OIL RESERVOIR RESERVOIRHIILO    HI/LO LEVE    L, alarms LEVEL, alarms..
Which ONE Which      ONE of ofthe thefollowing following describes describes thethe correct correct operator operator response?
response?
the cause IfIfthe  cause isis verified verified toto be be from from a:a:
A.
A.        Low reservoir Low    reservoir level, level, plot plot 38 3B RCP RCP motor motor bearing bearing temperatures temperatures everyevery 15 15 minutes.
minutes.
B.
: 8.        Low reservoir Low    reservoir level, level, stop stop the the 383B RCP RCP and and isolate isolate CCW CCW flow flow to to the the oil oil coolers coolers within  30  minute within 30 minutes.      s.
C.
C.        High reservoir High    reservoir level, level, plot plot 38 3B RCP RCP motor motor and and shaft shaft vibration vibration every every 1515 minute minutes. s.
D.
D.        High reservoir High    reservoir level, level, stop the 38  3B RCP RCP and increase increase CCW flowflow to the oiloil coolers within 30 minutes.
coolers                  minutes.
77
 
NRCDRAFT NRC      DRAFT                                07/24/07 07/24/07 Q#4 Q#4 ANSWER:
ANSWER:        AA KA:
KA:              00001 5/1 7AAI .02 000015/17AA1.02 Able to  operate  and/ormonitor Able to operate and/or      monitorthe the following following asas they theyapply applyto to the the RCP RCP Malfunctions Malfunctions (Loss of  RC  flow):  RCP  Oil  Reserv  oir (Loss of RC flow): RCP Oil Reservoir level and  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.
3-ARP-097.CR,        Ann. B2/5 B2/5 3-ONO    P-041.
3-0NOP-041.11,, StepsSteps 88 and and 43 43 Cognitive Level:
Cognitive  Level: 11 Recall Recall New Question New  Question Response Analysis:
Response    Analysis:
A.
A.      Correct per 3-0NOP-041.1, Correct        3-ONOP-041 .1, Step 43.
B.
B.      Incorrect because Incorrect  because this is the action to be taken if high reservoir  reservoir level is discov  ered, discovered,    not  low  reservoir level as stated in the response.
reservoir                              response. Plausible Plausible because this would be the correct action if the problem was discovered because                                                                      discovered to  to be be high  reservo high reservoir ir level.
C.
C. Incorrect Incorrect becaus because  e bearing temper      atures should be plotted, not vibration.
temperatures Plausib Plausiblele becaus because  e this is the correct freque frequency ncy of monitoring.
D.
D. Incorrect Incorrect becaus because  e this is is the the incorrect respon response    for high se for  high reservo reservoir  level. COW ir level. CCW flow flow should should bebe isolated, isolated, not not increas increased    Plausible ed Plausib        because    CCW    flow le because COW flow to the  to  the oil oil coolers coolers must must be be altered altered within within 3030 minute minutes    in the s in  the event event ofof high high reservo reservoir ir level..
level..
88
 
NRCDRAFT NRC        DRAFT                            07/24/07 07/24/07 Q#5 0#5 Unit33 isis atat 100%
Unit              100% power powerwithwith all all systems systems inin normal normal alignment.
alignment. 3A 3A Charging Charging pump pump isis operating.
operating.
3-267, 3A 3-267,          Chrg pump 3A Chrg      pump suct, suct, isolation isolation valve, valve, experiences experiences aa body-to-bonnet body-to-bonnet leakleak resulting    in  a  loss  of charging resulting in a loss of 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.
A.        Verify all Verify          charging pumps all charging    pumps are  are stopped stopped andand then then close close valve valve 3-268, 3-268, Chrg Chrg Pump Suct Pump        Suct HdrHdr X-Conn X-Conn valve, valve, because because no no charging charging pumps pumps can deliver flow can  deliver  flow to  the to the RCS. RCS.
B.
: 8.        Stop the Stop      the 3A3A Charging Charging pumppump andand start start the the 38 3B Charging Charging pump pump after after closing closing valve 3-268, valve      3-268, Chrg Chrg Pump Pump Suct Suct Hdr Hdr X-Conn X-Conn valve, valve, because because only  38  Charging only 3B Charging pump can pump        can deliver deliver flow flow to the RCS.RCS.
C.      Stop the 3A Charging pump and start 3C              30 Charging pump after closing valve 3-268, Chrg Pump Suct Hdr X-Conn valve, because              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 Suct Hdr X-Conn valve, because          because either 38  3B or 3C Charging pump can deliver flow to the RCS.
REFERENC REFERENCE          E PROVIDED 99
 
NRC DRAFT NRC      DRAFT                            07/24/07 07/24/07 Q#5 Q#5 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 toto the  Loss of the Loss of Reactor Coolant Reactor  Coolant Makeup:
Makeup: Isolating Isolating charging.
charging. 3.0/3.2 3.0/3.2 IOCFR55:
10CFR55:      41.b.5, 41.b.10 41.b.5,    41.b.10
 
==Reference:==
3-ONOP-047.1, Step 4.1 3-0NOP-047.1, 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 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. Incorrect because the 3B Charging pump            is disabled as well as the 3A pump is Charging pump. Plausible because the 3A Charging pump needs to be stopped and valve 3-268 should be closed.
C.
C. Correct Correct because the 3A    3A Charging Charging pump pump needs needs to be be stopped andand only the 3C Charging 3C  Charging pumppump can deliver deliver flow but but only only after after valve valve 3-268 3-268 isis closed.
closed.
D.
D. Incorrect Incorrect because because the    3B Charging the 3B  Charging pump pump is is disabled disabled as as well well as as the the 3A 3A Charging    pump. Plausible    because Charging pump. Plausible because the 3C    the  3C Charging Charging pump pump cancan deliver deliver flow but only but only after after valve valve 3-268 3-268 isis closed.
closed.
10 10
 
NRC DRAFT NRC      DRAFT                          07124/07 07/24/07 Q#6 Q#6 Unit 44 isis inin Mode Unit              Mode 44 andand onon RHR RHR cooling.
cooling.
** AA Loss Loss of    of Off-Site Off-Site Power Power (LOOP)
(LOOP) occurs.
occurs.
** The The 4A  4A sequencer sequencer failsfails to to start start its its components.
components.
Which ONE Which      ONE of  of the the following following describes describes the the correct correct operator operator response response regarding regarding restoration of restoration        of CCW CCW pump pump andand RHR RHR pumppump operation?
operation?
The operator The  operator will:  will:
A.        NOT have NOT      have to    start any to start  any CCW 0GW pumps pumps or    RHR pumps.
or RHR  pumps.
B.        NOT have to start any CCW        00W pumps but will start one RHR pump.
C.        have to start one CCW pump and will NOT have to start any RHR pumps.
D.      have to start one CCW    COW pump and start one RHR pump.
1111
 
NRC DRAFT NRC      DRAFT                                07/24/07 07/24/07 Q#6 Q#6 ANSWER:
ANSWER:        DD KA:
KA:            000025AA1.04 000025AA1.04 Able to Able  to operate operate and/or and/or monitor monitor the the following following asas they they apply apply to to the the Loss Loss ofof RHR RHR System:    Closed cooling System: Closed      cooling water water pumps.
pumps. 2.8/2.6 2.8/2.6 IOCFR55:
10CFR55:        41.b.7 41.b.7
 
==Reference:==
 
==Reference:==
4-ONOP-004, Steps 4-0NOP-004,      Steps 77 and and 88 5614-T-L1, Sheet 5614-T-L1,    Sheet 12A&
12A & 12B12B Cog Level:
Cog  Level: 22 Comprehension Comprehension Level 22 because Level    because the the operator operator must must evaluate evaluate thethe effect effect of of the the loss loss of of the the 4A 4A sequencer on on the final CCW and and RHR RHR pumppump configuration and  and then the operator operator must recall the CCW COW and RHR RHR pump pump requirements of ONOP-004.
New Question Response Analysis:
A.      Incorrect because the operator will have to start one CCW        COW pump and start one RHR pump. Plausible because if the sequencer had operated properly, the operator would not have had to start any CCW        COW pumps.
B.      Incorrect because the operator will have to start one COW        CCW pump and start one RHR pump. Plausible because ifif the sequencer had operated properly, the operator would not have had to start any      any COW CCW pumps and the operator will have will have to to start start one one RHR RHR pump.
pump.
C.
C. Incorrect Incorrect because the operator operator will have have to to start start one one RHR RHR pump.
pump. Plausible Plausible because because the the operator operator will will have have toto start start one one COWCCW pump.
pump.
D.
D. Correct Correct because because thethe operator operator will will have have toto start start one one COW CCW pumppump andand start start one one RHR    pump.
RHR pump.
1212
 
NRC DRAFT NRC      DRAFT                                  07/24/07 07/24/07 Q#7 0#7 Operators are Operators    are responding responding to  to aa main main steam steam line line break break inside inside Unit Unit 33 containment.
containment.
**  Containment pressure Containment      pressure peaked peaked at at 26  psig and 26 psig  and isis now now 1515 psig.
psig.
**  The  3B  SG  WR  level  is  15%  and The 3B SG WR level is 15% and lowering. lowering.
**  No  charging pumps No charging    pumps areare running running
**  Step  10  of 3-EOP-E-1, Step 10 of 3-EOP-E-1, "Loss  Loss ofof Reactor Reactor or      Secondary Coolant,"
or Secondary      Coolant, directs directs establishment of establishment    of maximum maximum charging charging flow.
flow.
**  Seal Water Seal  Water Return Return temperatures temperatures are  are at at 245°F.
245°F.
**  The  Unit  Supervisor    orders    closure  of The Unit Supervisor orders closure of the local  the  local seal seal injection injection valves, valves, 297 297 AlBIC, A/B/C, before starting before  starting the  first charging the first  charging pump.
pump.
Which ONE of the following describes why the local          local seal seal injection injection valves areare closed this time?
at this A.      CCW flow to the thermal barriers has been lost.
RCP seals already have elevated temperatures and initiation of cold seal injection flow will cause RCP damage.
B.      CCW flow to the thermal barriers has been lost.
RCP seal temperatures are still in the allowed range and maximum charging flow to the RCS loops via the normal charging path is required.
C.      CCW flow to the thermal barriers has NOT been interrupted.
Seal injection is NOT needed to maintain seal integrity and maximum charging flow to the RCS loops via the normal charging path is required.
D.      CCW flow to the thermal barriers has NOT          NOT been interrupted.
Seal injection is NOTNOT needed to maintain seal integrity and        and initiation of of cold seal injection flow will cause RCP  RCP damage.
damage.
13 13
 
NRC DRAFT NRC      DRAFT                            07/24/07 07/24/07 Q#7 Q#7 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 CCW: Guidance      contained in  in EOP EOP forfor loss loss of of CCW.
CCW. 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 5610-T-L1, Sheet 5610-T-L1,      Sheet 11  11 5613-M-3030, Sheet 5 5613-M-3030, Cog Level:    1I 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 flow to the thermal barriers has been lost.
C. Incorrect because CCW flow to the thermal barriers has been lost. Plausible because maximum charging flow to the RCS loops          loops via the normal charging path is required.
D.
D. Incorrect Incorrect because because CCWCCW flow to  to the thermal thermal barriers barriers has has been been lost.
lost. Plausible Plausible because initiation initiation of of cold seal injection flow will cause RCP damage.
damage.
14 14
 
NRC DRAFT NRC      DRAFT                              07/24/07 07/24/07 Q#8 Q#8 Unit 44 is Unit      is initially initially at at 70%
70% power power with with all all systems systems in    automatic except in automatic  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 the the effect effect of  this event of this  event on on the the RCS RCS and and the the correct  operator response?
correct operator        response?
The resulting turbine runback runback will initially initially cause RCS RCS temperature to:
A.        increase resulting in expansion of reactor coolant into the pressurizer causing RCS pressure to increase.
The RO RO will drive the PC-4-444J controller output higher (toward 100%) to stabilize pressure.
B.        increase resulting in expansion of reactor coolant into the pressurizer causing RCS pressure to increase.
The RO will drive the PC-4-444J controller output lower (toward 0%) to stabilize pressure.
C.        decrease resulting in contraction of reactor coolant from the pressurizer causing RCS pressure to decrease.
The RO will drive the PC-4-444J controller output higher (toward 100%) to stabilize pressure.
D.      decrease resulting in contraction of reactor coolant from the pressurizer causing RCS pressure to decrease.
The RO will drive the PC-4-444J controller output lower (toward 0%) to stabilize pressure.
15 15
 
NRC DRAFT NRC      DRAFT                                    07/24/07 07/24/07 Q#8 Q#8 ANSWER:
ANSWER:          AA KA:
KA:              000027AK1.02 000027AK1.02 Knowledge of Knowledge      of the  operational implications the operational    impl!cations of    the following of the  following concepts concepts as  as they they apply apply to to the pressurizer    pressure  control  malfunctions the pressurizer pressure control m'alfunctions:: Expansion  Expansion of  of liquids liquids as as temperature temperature increases. 2.8/3.1 increases. 2.8/3.1 10CFR55:
10CFR55:          41.b.5, 41.b.7, 41.b.5,    41.b.7, 41.b.10, 41.b.10, 41.b.14 41.b.14
 
==Reference:==
 
==Reference:==
4-ONOP-041 .5, Step 4-0NOP-041.5,      Step 1.a l.a RNO RNO SD-009, Figure SO-009,    Figure 22 22 Cog Level:
Cog  Level: 22 Comprehension 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 RO will drive the PC-4-444J controller output higher (toward 100%)
100%) to stabilize pressure. Plausible because the resulting turbine runback will initially cause RCS temperature to increase      increase resulting in expansion of  of reactor coolant into into the the pressurizer causing causing RCS pressurepressure to to increase.
C.
C.      Incorrect Incorrect because because the the resulting turbine turbine runback will initially initially cause cause RCSRCS temperature temperature to      increase to increase resulting resulting in in expansion expansion of  of reactor reactor coolant coolant into into the the pressurizer pressurizer causing causing RCS RCS pressure pressure to to increase.
increase. Plausible Plausible because because the the RO RO will  drive  the PC-4-444J    controller will drive the PC-4-444J controller output  output higher higher (toward (toward 100%)100%) to to stabilize stabilize pressure pressure D.
O. Incorrect Incorrect because because the the resulting resulting turbine turbine runback runback will will initially initially cause cause RCSRCS temperature temperature to  to increase increase resulting resulting in in expansion expansion of  of reactor reactor coolant coolant into into the pressurizer the  pressurizer causing causing RCS RCS pressure pressure to  to increase increase and and thethe RO RO will will drive drive the the PC-4-444J PC-4-444J controller controller output output higher higher (toward (toward 100%)
100%) to to stabilize stabilize pressure.
pressure.
Plausible Plausible the the response response isis consistent consistent ifif the the operator operator doesdoes notnot realize realize that that aa turbine turbine runback runback causes causes the the RCS RCS temperature temperature to    to increase.
increase.
16 16
 
NRC DRAFT NRC        DRAFT                              07124/07 07/24/07 Q#9 0#9 Unit 44 was Unit      was at at 100%    power with 100% power        with all all systems systems inin normal normal alignment alignment when when the the following following events    occurred:
events occurred:
** 4C4C S/G    faulted outside SIG faulted    outside containment.
containment.
** The The reactor reactor failed failed to to trip trip automatically automatically or        manually.
or manually.
**  All other All  other safeguards safeguards systems systems actuated actuated as    as required.
required.
Operators are Operators      are performing performing Step Step 14 14 of of 4-EOP-FR-S.1, 4-EOP-FR-S.1, "Response Response toto Nuclear Nuclear Power Power Generation/A    TWS,    which    directs Generation/ATWS," which directs them to        them        Verify steam to "Verify  steam supply supply aligned aligned to to both both trains of trains    of AFW AFW pumps pumps fromfrom intact intact S/G(
S/G(s).
s )."
Which ONE Which      ONE of    the following of the  following describes describes the  the correct correct operator operator response?
response?
(Note: AFSS-4-006 and (Note:                      and AFSS-4-007 AFSS-4-007 are    are AFW AFW steam supply crosscross connect connect valves.)
Direct the NSO Direct        NSO to locally:
A.
A.        open AFSS-4-006 only.
B.
B.        open AFSS-4-007 only.
C.
C.        close AFSS-4-007 and then open AFSS-4-006        AFSS-4-006..
D.
D.        open AFSS-4-007 and then close AFSS-4-006        AFSS-4-006..
1717
 
NRC DRAFT NRC      DRAFT                            07124/07 O7/24/7 Q#9 Q#9 ANSWER:
ANSWER:            0D KA:
KA:                  000029G2.1.30 000029G2.1.30 As itit relates As      relates toto the  ATWS event:
the ATWS      event: Able Able to to locate locate and and operate operate components, components, including including local controls.
local    controls. 3.9/4.0 3.9/4.0 I OCFR55:
10CFR55:            41 .b.4, 41.b.7,41.b.10 41.b.4,    41 .b.7, 41 .b.10
 
==Reference:==
 
==Reference:==
4-EOP-FR-S.1, Step 4-EOP-FR-S.1,      Step 14.d.RNO 14.d.RNO 5614-M-3075, Sheet I 5614-M-3075,Sheet1 Cog Level:
Cog      Level:    22 Comprehension Comprehension Level 2 because the operator must        must recognize that the goal is to restore steam supply from two intact steam generator trains and to maintain train separation and maintain steam supply during the process. The correct way to achieve this is to AFSS-4007 and then close AFSS-4-006.
locally open AFSS-4-007                              AFSS-4-006.
New Question Response Analysis:
A.          Incorrect because the RO    RD will direct the NSO to open AFSS-4-007 and then close AFSS-4006 AFSS-4-006      lAW  EOP-FR-S.1 EOP-FR-S.1,, Step 14.d.RNO.
14.d.RNO. Plausible because the procedure step does not specify the desired position of AFSS-4-006 AFSS-4-006.. It merely directs operators to manipulate AFSS-4-006AFSS-4-006..
B.        Incorrect Incorrect because the RD    RO will direct the NSO to open AFSS-4-007 and then close close AFSS-4-006 lAW    lAW EOP-FR-S.1 EOP-FR-S.1,, Step Step 14.d.RNO.
14.d.RNO. Plausible Plausible because because itit is is correct (but not not complete) to locally locally open AFSS-4-007 AFSS-4-007..
C.
C.        Incorrect Incorrect because because thethe RD RO will direct direct the the NSO NSO toto open open AFSS-4007 AFSS-4-007 and and then then close  AFSS-4-006 close AFSS-4-006 lAW    lAW EOP-FR-S.1 EOP-FR-S.1,, StepStep 14.d.RNO.
14.d.RNO. Plausible Plausible because because the procedure the  procedure step      does not step does    not specify specify the the desired desired position position of of AFSS-4006 AFSS-4-006 or  or AFSS-4-006      . It merely  directs operators AFSS-4-006. It merely directs operators to        to manipulate manipulate AFSS-4-006 AFSS-4-006 and  and AFSS-4-006 AFSS-4-006..
D.
D.        Correct    per the Correct per    the references references 18 18
 
NRC    DRAFT NRC DRAFT                                07/24/07 07/24/07 Q#1O Q#10 Operators are Operators    are performing performing 3-EOP-E-3, 3-EOP-E-3, "Steam Steam Generator Generator Tube Tube Rupture."
Rupture.
** All All RCPs RCPs areare stopped.
stopped.
After dumping After  dumping steam steam fromfrom intact intact S/Gs S/Gs to to increase increase subcooling, subcooling, the the RO RO has has been been directed to directed  to open open oneone pressurizer pressurizer PORV.
PORV.
Which ONE Which    ONE ofof the the following following describes describes the the effect effect of of opening opening the the PORV PORV on on pressurizer  level,  RCS    subcooling  and pressurizer level, RCS subcooling and S/G tube  SIG  tube break break flow flow rate?
rate?
Pressurizer level Pressurizer    level              RCS subcooling RCS  subcoolinq          S/G S/G break break flow flow A.
A.      Decreases Decreases                          Decreases Decreases                      Increases Increases B.      Increases                        Decreases                      Decreases Decreases C.      Increases                        Increases                      Increases D.      Decreases                        Increases                      Decreases 19 19
 
NRC DRAFT NRC    DRAFT                            07/24/07 07/24/07 Q#10 Q#10 ANSWER:
ANSWER:        BB KA:
KA:              000038 EKI .02 000038EK1.02 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 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 3-EOP-E-3,      NOTE prior prior to to Step Step 25, 25, Step Step 25 25 3-EOP-E-3, Step 3-EOP-E-3,      Step 25 25 BO BD Cog  Level: 1I recall Cog Level:      recall New Question New 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.
O. Incorrect because pressurizer level will increase, not decrease and subcooling will decrease, not increase. Plausible because break flow will decrease decrease 20 20
 
NRC DRAFT NRC      DRAFT                                07/24/07 07/24/07 QQ#11
    #11 Unit 44 isis at Unit          at 50%    power when 50% power      when aa large large main main steam steam line line break break outside outside containment containment downstream (turbine downstream          (turbine side) side) of of the the 4B 4B MSIV MSIV and and non-return non-return check check valve valve occurs.
occurs.
Which ONE Which      ONE of of the the following following describes describes thethe response response of  of the the Unit Unit 44 MSIVs MSIVs and and the the reason    for  that  response?
reason for that response?
A.
A.        None of None    of the the Unit Unit 44 MSIVs MSIVs will will automatically automatically close close as as NO NO protective protective signal signal isis generated generated for  for this this condition.
condition.
B.
B.        4B MSIV 4B    MSIV will    automatically close will automatically    close due due to to high high steam steam flow flow on on the the 4B 4B S/G SIG with with aa low 4B low        SIG pressure.
4B S/G    pressure. 4A  4A and and 4C4C MSIVs MSIVs will will NOT NOT automatically automatically close.
close.
C.        All of All  of the Unit Unit 44 MSIVs MSIVs will automatically automatically close close due due to high high steam steam flow with low Tavg or low SG pressure sensed on all S/Gs.          S/Gs.
D.
D.        All of the UnitUnit 4 MSIVs MSIVs will automatically close due to high differential pressure between each S/G        SIG and the main steam header.
2121
 
NRC DRAFT NRC        DRAFT                              07124/07 07/24/07
    #11 QQ #11 ANSWER:
ANSWER:        CC KA:
KA:            000040AK2.O1 000040AK2.01 Knowledge of Knowledge    of the the interrelations interrelations between between the  the steam steam line ilne rupture rupture and and the the following:
following:
Valves. 2.6/2.5 Valves. 2.6/2.5 10CFR55:
10CFR55:        41.b.4, 41.b.7, 41.bA,    41.b.7, 41.b.8 41.b.8
 
==Reference:==
 
==Reference:==
5610-T-L1, 5610-T-L      Sheet 11 1, Sheet    11 5610-T-L1, 5610-T-L        Sheet 19 1, Sheet    19 5614-M-3072, Sheet I 5614-M-3072,Sheet1 Cog Level:      2 Comprehension Comprehension Level 2 because the operator must recognize that the location of the break determines the response of the MSIVs. Because the break is downstream of the MSIV/non-return check valve, it does not matter that it is located on the 4B header.
MSIV/non-return All S/Gs will feed the break and all MSIVs will close.
New Question Response Analysis:
A.      Incorrect because all Unit 4 MSIVs will close. Plausible because the stem implies the problem is associated with only the 4B steam header. If the problem was really associated with only one header, no protective signal would be generated.
B.
B.      Incorrect Incorrect because because allall Unit Unit 44 MSIVs MSIVs will close.
close. Plausible Plausible because because the the break break is is located located on the 4B 4B steam header header aridand 4B4B MSIV MSIV will automatically automatically close.
close.
C.
C.      Correct Correct per per the the references D.
D.      Incorrect Incorrect because because high high steam steam lineline /1S/G S/G pressure pressure differential differential does does notnot close close MSIVs. Plausible  because MSIVs. Plausible because all      all of of the the MSIVs MSIVs will will automatically automatically close close 22 22
 
NRC DRAFT NRC      DRAFT                            07/24/07 07/24/07
    #12 QQ #12 With Unit Unit 33 critical critical at at 10- 8 amps I 08 With                              amps IR IR power, power, 3A 3A main main feedwater feedwater header headersheared sheared immediately      outside Unit immediately outside          Unit 33 containment.
containment.
Which ONE Which    ONE of      the following of the  following describes describes the the effect effect on on Unit Unit 3?
3?
3A S/G 3A  SIG will:
will:
A.
A.      NOT depressurize.
NOT      depressurize.
SI  will NOT SI will  NOT actuate.
actuate.
B.
B.      NOT depressurize.
NOT      depressurize.
Low    pressurizer Low pressurizer pressure pressure reactor reactor trip trip and and SISI will will occur.
occur.
c.
C. depressurize.
depressurize.
Low pressurizer Low    pressurizer pressure pressure reactor reactor trip trip and and SI SI will occur.
occur.
D.
D.      depressurize.
depressurize.
Hi Steam Line ~p    AP SI will actuate.
23 23
 
NRC DRAFT NRC    DRAFT                              07/24/07 07/24/07
    #12 QQ #12 ANSWER:
ANSWER:          D D
KA:
KA:              000054AK1.O1 000054AK1.01 Knowledge of Knowledge      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      Main FW:
of Main  FW: MFW      line break MFW line    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 IOCFR55:
10CFR55:        41.b.4, 41.b.7, 41.bA,    41.b.7, 41.b.8 41.b.8
 
==Reference:==
 
==Reference:==
561 O-T-L 561  O-TL1,  Sheet 11 1, Sheet    11 5610-T-L1,    Sheet 19 561 O-T-L 1, Sheet    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 depressurization will be sensed on location will depressurize the 3A S/G and the depressurization the 3A steam header which will result in the High steamline L'1P        AP logic (1/3 S/Gs) being initiated which is not blocked at low power levels.
New Question Response Analysis:
A.      Incorrect because 3A S/G will depressurize and SI will actuate. Plausible because the SI protection is needed for aa steam line break, not aa feed line break.
B.
B.      Incorrect Incorrect because 3A  3A S/G S/G will depressurize depressurize and the low  low pressurizer pressurizer pressure trip is blocked and the 3A s/g will depressurize. PlausiblePlausible because SI  SI would be be expected expected subsequently subsequently C.
C.      Incorrect Incorrect because because the the low low pressurizer pressurizer trip  is blocked.
trip is  blocked. Plausible Plausible because because the the S/G S/G will will depressurize depressurize and    SI would and SI  would be be expected expected subsequently subsequently D.
D.      Correct Correct perper the the references.
references.
24 24
 
NRC DRAFT NRC      DRAFT                                07/24/07 07/24/07
    #13 QQ #13 Operators are Operators      are performing performing 4-EOP-ECA-0.0, 4-EOP-ECA-O.0, "Loss    Loss ofof All All AC AC Power" Power and and are are inin the the process of process        depressurizing all ofdepressurizing  all intact    SIGs to intact S/Gs    to 180 180 psig.
psig.
What isis the What        the consequence consequence ifif the the SGSG depressurization depressurization isis NOTNOT stopped stopped until until 50 50 psig?
psig?
A.
A.          reactor vessel AA reactor    vessel head head void void could could become become largelarge enough enough to to partially partially uncover uncover the  core.
the core.
B.
B.      AA Nitrogen Nitrogen gas gas bubble bubble in in the the pressurizer pressurizer could could cause cause aa loss loss of of pressure pressure control.
control.
C.
C.      The pressurizer The    pressurizer would would go go water-solid water-solid resulting resulting in in aa loss loss of of pressure pressure control.
control.
D.
D.      Nitrogen could Nitrogen    could enter enter the    SIG U-tubes the S/G    U-tubes disrupting disrupting natural natural circulation.
circulation.
25 25
 
NRC DRAFT NRC      DRAFT                              07124/07 07/24/07
  #13 QQ #13 ANSWER:
ANSWER:        DD KA:
KA:              000055EK1 .02 000055EK1.02 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 the station the  station blackout:
blackout: Natural Natural Circulation Circulation Cooling.
Cooling. 4.1/4.4 4.1/4.4 IOCFR55:
10CFR55:        41.b.3, 41.b.4, 41.b.3,  41.b.4, 41.b.7 41.b.7
 
==Reference:==
 
==Reference:==
3-EOP-ECA-0.0 BD, 3-EOP-ECA-O.O      BD, CAUTION CAUTION before before Step Step 26 26 Cog Level:
Cog  Level:      Recall 1I Recall New Question New    Question Response Analysis:
 
===Response===
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, 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 depressurization will cause a head void.
B.      Incorrect because nitrogen accumulating in the pressurizer will not result in aa loss of pressure control which is being provided by the PORVs (no spray or heaters) and this is not the reason given by the reference. Plausible because nitrogen is expected to migrate to the pressurizer (RCS high point).
C.      Incorrect because the pressurizer would be expected to empty under these conditions. Plausible because large pressurizer level changes are expected and aa loss  of pressurizer pressure control is loss of                                  is expected expected ifif the pressurizer empties.
D.
D.      Correct Correct per per the references.
26 26
 
NRC DRAFT NRC    DRAFT                              07124/07 07/24/07 Q#14 0#14 Unit 33 isis at Unit          at 100%
100% power power when when the the following following events events occur:
occur:
**  Unit 33 reactor Unit      reactor automatically automatically trips.
trips.
**  Unit    3  MSIVs    automatically Unit 3 MSIVs automatically close. close.
**  Unit 33 annunciators Unit      annunciators go go dark.
dark.
Which ONE Which      ONE of  of the the following following identifies identifies the the procedure procedure operators operators will will implement implement after after the unit    is stabilized  using 3-EOP-ES-0      .1, Reactor the unit is stabilized using 3-EOP-ES-0.1, "Reactor Trip        Trip Response"?
Response?
A.
A.        3-ONOP-005.4, "4KV 3-0NOP-005.4,        4KV Bus Bus 3A, 3B3B or  3D Ground" or 3D  Ground B.        3-ONOP-003.9, "Loss 3-0NOP-003.9,        Loss of 120 120 VAC Vital Instrument Panel 3P09"3P09 C.        3-ONOP-003.5, "Loss 3-0NOP-003.5,        Loss of DC Buses 3023  3D23 and 3D23A (3B)
D.        3-ONOP-003.4, "Loss 3-0NOP-003.4,        Loss of DC Bus 3001 3D01 and 3D01A 3DO1A (3A) 27 27
 
NRC DRAFT NRC      DRAFT                              07/24/07 07/24/07 Q#14 Q#14 ANSWER:
ANSWER:          DD KA:
KA:                000058G2.4.4 000058G2.4.4 As  it  relates As it relates to 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    operating    parameters  which  are for system operating parameters which are entry levelentry  level conditions conditions for for emergency emergency and abnormal and    abnormal operating operating procedures.
procedures. 4.0/4.3 4.0/4.3 10CFR55:
10CFR55:          41.b.7, 41.b.1O 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 New    Question Response Analysis:
 
===Response===
A.        Incorrect because Incorrect  because operators are directed to enter ONOP-003.4 immediately immediately following EOP-ES-0.1. Plausible because a reactor trip, MSIV closure or loss of annunciators could be related to various grounds.
B.
B.        Incorrect because operators are directed to enter ONOP-003.4 immediately following EOP-ES-0.1. Plausible because the first step of ONOP-003.9 procedure checks for a reactor trip and analyzes if one is needed and loss of 3P09 previously required a reactor trip.
C.        Incorrect because all of the symptoms listed are indicative of aa loss of 3D01, not 3D23. Plausible because the reactor will automatically trip and MSIVs will automatically close upon aa loss of 3D23 D.
D.        Correct per the references 28 28
 
NRC DRAFT NRC        DRAFT                                07124/07 07/24/07 Q#15 0#15 Operators are Operators      are responding responding to to aa line line break break inin the the Instrument Instrument Air Air (IA)
(IA) system.
system.
**  IA  pressure as IA pressure    as seen seen by  P1-3-1444 (VPA) by PI-3-1444      (VPA) isis 91 91 psig psig and and lowering.
lowering.
** All All available available IA IA compressors compressors are  are running running andand crossties crossties are are open.
open.
The NSO The  NSO isis sent sent to    investigate and to investigate    and reports reports the the following following local local IA IA pressure pressure indications:
indications:
P1-3-1516, Turbine PI-3-1516,    Turbine Area:
Area:                                      86 86 psig psig lowering lowering P1-3-1517,    Containment PI-3-1517, Containment Area:    Area:                                75 75 psig psig lowering lowering P1-3-1518, PI-3-1518, Aux      Bldg, Intake Aux Bldg,    Intake Area, Area, Control Room:Room:          88 psig psig lowering lowering Which ONE of the following describes the correct operator response?
A.
A.        Isolate IA to the Containment.
Containment. Trip the reactor and perform 3-EOP-E-O, Reactor Trip or Safety Injection."
        "Reactor                      Injection.
B.                            Containment. If IA pressure continues to decrease, then Isolate IA to the Containment.
trip the reactor and perform 3-EOP-E-O, "Reactor    Reactor Trip or Safety Injection".
Injection.
C.      Do NOT isolate IA to the Containment.
Containment. Trip the reactor and perform Reactor Trip or Safety Injection."
3-EOP-E-O, "Reactor                              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-O, Reactor      "Reactor Trip or Safety Injection.
Injection".
29 29
 
NRC      DRAFT NRC DRAFT                                  07/24/07 07/24/07 Q  #15 Q #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 and and 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 IOCFR55:
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 17 RNO, FO Page Unit Trip Criteria Cog Level:          Comprehension 2 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 isolating IA to containment should isolate the leak, mitigating the event.
C.        Incorrect because IA  IA must be isolated to containment when its pressure drop exceeds 10 10 psi. Plausible because the reactor must be tripped under      under these conditions.
D.
D.        Incorrect Incorrect because IA  IA must must bebe isolated to containment containment when its  its pressure pressure drop drop exceeds exceeds 10    psi. Plausible 10 psi. Plausible because because the the reactor must    be tripped must be  tripped under under these these conditions.
conditions.
30 30
 
NRC DRAFT NRC    DRAFT                                  07124/07 07/24/07
    #16 QQ #16 Unit 33 operators Unit    operators are  are performing performing 3-EOP-ECA-1.2, 3-EOP-ECA-1 .2, "LOCA LOCA OutsideOutside Containment."
Containment.
* After closing After  closing thethe RHR RHR Discharge Discharge to  Cold Leg to Cold  Leg Isolation Isolation valves,      MOV-3-744A &
valves, MOV-3-744A          & B, B,
and SI and  SI to  Cold Leg to Cold    Leg Isol Isol valves, valves, MOV-2-843A MOV-2-843A && B,  B, RCSRCS pressure pressure isis still still decreasing.
decreasing.
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 the  response?
for the response?
A.
A.        Return to Return    to Step Step 1I of of 3-EOP-ECA-1.2, 3-EOP-ECA-1 .2, "LOCA LOCA Outside Outside Containment,"
Containment, and  and perform the perform    the isolation isolation steps steps again again as as the the leak leak isis NOT NOT isolated.
isolated.
B.
B.      Transition to Transition        3-EOPES-1 .2, "Post to 3-EOP-ES-1.2,      Post LOCA LOCA Cooldown Cooldown and  and Depressurization" Depressurization as  the  steps  in ECA-1 as the steps in ECA-1.2      .2 have have been been successful successful in  in isolating isolating the the leak leak so so subsequent cooldown subsequent      cooldown and  and depressurization depressurization will be    be required required to gogo onto RHR onto    RHR cooling.
cooling.
C.      Transition to step in effect in 3-EOP-E-1, "Loss    Loss of Reactor or Secondary Coolant as the steps in ECA-1.2 Coolant"                        ECA-1 .2 have NOT been successful and the completion of 3-EOP-E-1 will mitigate the situation.
completion D.
D.                        3-EOP-ECA-1 .1,, "Loss Transition to 3-EOP-ECA-1.1            Loss of Emergency Coolant Recirculation" Recirculation as the steps in ECA-1.2 ECA-1 .2 have NOT been successful so the ECA-1.1        ECA-1 .1 actions to prolong injection from the RWST will be required.
31 31
 
NRC DRAFT NRC        DRAFT                            07/24/07 07/24/07
  #16 Q #16 Q
ANSWLR:
ANSWER:          DD KA:
KA:                W/EO4EA2.1 W/E04EA2.1 Able to Able      determine and to determine      and interpret interpret the the following following as as they they apply apply to to the the LOCA LOCA OC: DC:
Facility  conditions    and  selection Facility conditions and selection of        appropriate procedures of appropriate  procedures during during abnormal abnormal and and emergency operations.
emergency      operations. 3.4/4.3 3.4/4.3 IOCFR55:
10CFR55:          41.b.5, 41.b.1O 41.b.5,41.b.10
 
==Reference:==
 
==Reference:==
3-EOP-ECA-1 .2:
3-EOP-ECA-1.2:          Step 3.a.RNO Step    3.a.RNO Cog Level:        1I Recall New Question New Response Analysis:
A.      Incorrect because the correct transition is to go to EOP-ECA-1.1 EOP-ECA-1 .1 if pressure is still stable or decreasing. Plausible because returning to step 11 implies another effort to identify and isolate the leak which is reasonable under these circumstances.
circumstances.
B.      Incorrect because the correct transition is to go to EOP-ECA-1.1 EOPECA-1 .1 if pressure is still stable or decreasing. Plausible because the stem implies operators is are responding to a LOCA and with pressure still stable, EOP-ES-1.2  EOP-ES-1 .2 is a logical choice to deal with an active LOCA.
C.      Incorrect because the correct transition is to go to EOP-ECA-1 EOP-ECA-1.1    .1 if pressure is still stable or decreasing. Plausible because per the same procedure step, the transition would be to EOP-E-1 if pressure were increasing.
D.      Correct per the references 32 32
 
NRC DRAFT NRC      DRAFT                                07124/07 07/24/07
  #17 Q #17 Q
Upon entry Upon  entry into into 4-EOP-ECA-1.1, 4-EOP-ECA-1 .1, "Loss  Loss ofof Emergency Emergency Coolant Coolant Recirculation" Recirculation the the RO reports RO  reports Unit Unit 44 RWST RWST levellevel has has decreased decreased to    59,000 gallons.
to 59,000  gallons.
Which ONE Which  ONE of of the the following following describes describes thethe correct correct operator operator response?
response?
A.
A.      Depressurize all Depressurize      all intact intact S/Gs SIGs toto atmospheric atmospheric pressure pressure at at aa rate rate NOT NOT to to exceed    an  RCS    cooldown      rate of exceed an RCS cooldown rate of 100°F/hour to  100°F/hour    to ensure ensure the the Unit Unit 44 Accumulators fully Accumulators        fully inject.
inject.
B.
B.      Stop the Stop  the running running UnitUnit 44 HHSI, HHSI, RHRRHR andand CS CS pumps.
pumps.
Align and Align  and start    one Unit start one    Unit 33 HHSI HHSI pump pump to    deliver flow from Unit to deliver              Unit 33 RWST.
RWST.
C.      Stop the running Unit 4 RHR and CS pumps.
Stop Continue to run one Unit 4 HHSI    HHSI pump for as long as it will deliver flow from 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.
33 33
 
DRAFT NRC DRAFT                                  07/24/07 07/24/07 Q#17 Q#17 ANSWER:
ANSWER:        B B
KA:
KA:            W/EIIEK2.2 W/E11EK2.2 Knowledge of Knowledge    of the interrelations interrelations between between the lossloss of emergency coolant recirc recirc and facilitys heat removal systems incl the following: facility's                            md primary coolant, emergency coolant, the decay coolant,      decay heat    removal systems, heat removal  systems, and and relations relations between between the proper proper operation of these systems operation              systems to the operation operation of of the facility. 3.9/4.3 3.9/4.3 IOCFR55:
10CFR55:        41.b.7, 41.b.10 41.b.7,41.b.10
 
==Reference:==
 
==Reference:==
4-EOP-ECA-1 .1:
4-EOP-ECA-1.1:        Steps 1, 1, 30, 31, 32 Cog Level:        Comprehension 2 Comprehension Level 2 because the operator must link the knowledge that RWST level <              < 60,000 gallons requires stopping the safety pumps. The 60,000 criteria is provided in            in Step 1I 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 unit's  units HHSI pump. Plausible depressurizing S/Gs is a subsequent procedure step but if done it because depressurizing will be performed at the maximum rate.
B.      Correct per the references C.      Incorrect because all safety pumps are stopped, including HHSI pumps.
Plausible because the RHR and CS pumps are stopped and continuing to run HHSI HHSI pumps would continue to provide core cooling flow.
D.      Incorrect because the safety pumps need to be stopped now. Plausible because the charging pumps are probably already running (but at maximum speed) and and will be be allowed to to run until until RWST level drops drops to 20,000 20,000 gallons.
gallons.
34 34
 
NRC DRAFT NRC    DRAFT                              07/24/07 07/24/07 Q  #18 Q #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 to to restore restore AFW AFW flow flow when when the the RO RO reports reports the the following following S/G SIG levels:
levels:
            **  3A  SIG:
3A S/G:        35%
35%    WR WR        lowering lowering
            **  3B SIG:
3B S/G:        25%
25%    NR NR        lowering lowering
            **  3C  SIG:
30 S/G:      30%    NR NR      lowering lowering The BOP BOP is is unable unable to immediately immediately restore restore secondary heatheat sink.
The STA reports containment temperature has increased  increased to 190&deg;F.
Which ONE of the following describes the correct operator response?
A.      Maintain RCPs running. Continue to perform procedure steps to restore secondary heat sink.
B.                  RCP5 running.
Maintain RCPs                Immediately initiate bleed and feed.
C.      Stop RCPs. Continue to perform procedure steps to restore secondary heat sink.
D.              RCP5. Immediately initiate bleed and feed.
Stop RCPs.
35 35
 
NRC      DRAFT NRC DRAFT                                07/24/07 07/24/07 Q  #18 Q #18 ANSWER:
ANSWER:        DD KA:
KA:            W/EO5EKI .2 W/E05EK1.2 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 the Loss the  Loss of of secondary secondary heat heat sink:
sink: Normal, Normal, abnormal abnormal and    emergency    operating and 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.10 41.b.10
 
==Reference:==
 
==Reference:==
3-EOP-FR-H.1::
3-EOP-FR-H.1          CAUTION prior CAUTION    prior to to Step Step 2, 2, Step Step 12 12 Comprehension Cog Level: 2 Comprehension Level 2 because the operator must evaluate the S/G levels provided based on adverse containment conditions (>180&deg;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. Plausible because operators will continue efforts to restore secondary heat sink.
B. Incorrect because RCPs need to be tripped immediately. Plausible because operators will immediately initiate bleed and feed.
C. Incorrect because bleed and feed needs to be established immediately.
Plausible because RCP5 RCPs need need to be stopped.
D.
D. Correct per the references 36 36
 
NRC DRAFT NRC      DRAFT                                07/24/07 07/24/07
    #19 QQ #19 Unit 44 isis inin Mode Unit                Mode 66 whenwhen the the RO RD isis notified notified that that aa spent spent fuel fuel element element hashas dropped dropped onto the onto  the Region Region IIII fuel fuel racks.
racks.
Which ONE Which      ONE of    of the  following identifies the following  identifies control control room room indications indications that that can can bebe used used to to determine        if the  fuel  element determine if the fuel element cladding    cladding has has been been breached?
breached?
A.
A.        CVCS Letdown CVCS          Letdown PRMSPRMS R-20 R-20 monitor monitor alarms alarms B.
B.        Spent Fuel Spent        Fuel Building Building Area Area rad rad monitors monitors alarm alarm C.
C.        Containment Building Containment            Building Area Area rad rad monitors monitors alarm alarm D.
D.        Containment Atmosphere PRMS Containment                          PRMS R-11R-1 1 or or R-12 R-1 2 monitors monitors alarm alarm 37 37
 
DRAFT NRC DRAFT                              07/24/07 07/24/07
  #19 Q #19 Q
ANSWER:
ANSWER:        BB KA:
KA:              000036AA2.O1 000036AA2.01 Able to Able  to determine determine and and interpret interpret the the following following as as they they apply apply to to the the fuel fuel handling handling incidents: ARM system incidents:          system indications.
indications. 3.2/3.9 3.2/3.9 IOCFR55:
10CFR55:        41.b.1O, 41.b.11 41.b.10,
 
==Reference:==
4-ONOPO33.3:
4-0NOP-033.3:          Section 2.2 Cog Level:      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 C.      Incorrect because the event did not occur in containment. Plausible because the question does not state that the event occurred in the Spent Fuel Pool area.
D.      Incorrect because the event did not occur in containment. Plausible because the question does not state that the event occurred in the Spent Fuel Pool area.
38 38
 
NRC DRAFT NRC    DRAFT                              07/24/07 07/24/07 Q #20 Q#20 Unit 44 isis 100%
Unit          100% power power with with all all systems systems inin normal normal operation operation when when aa tube tube leak leak occurs occurs in the in        4A S/G.
the 4A    SIG.
The tube The    tube leak leak increases increases to to 250 250 gpm    over aa period gpm over      period of of 55 minutes.
minutes.
Which ONE Which      ONE of of the  following describes the following    describes the the effect effect on on charging charging and and letdown letdown flow flow rates rates as  the  leak  starts  (before  operator as the leak starts (before operator response)  response) and and AFTER AFTER operators operators have have performed performed the prompt the    prompt actions actions of of 4-EOP-E-0, 4-EOP-E-0, Reactor Reactor Trip Trip or or Safety Safety Injection?
Injection?
Early in Early  in S/G    Tube Leak SIG Tube    Leak Event Event              After After Prompt Prompt Actions Actions Complete Complete Chging    Flow Chqinq Flow                Ltdwn Flow Ltdwn    Flow          Chging Chging Flow Flow          Ltdwn Ltdwn Flow Flow A.        Unchanged                  Unchanged              Zero                    Unchanged Unchanged B.        Increasing                Decreasing              Maximum                Zero C.        Increasing                Unchanged              Zero                    Zero D.      Unchanged                  Unchanged              Zero                    Unchanged 39 39
 
NRC DRAFT                                    07124/07 07/24/07 Q #20 Q#20 ANSWER: C ANSWER:          C KA:
KA:              000037AK3.03 000037  AK3.03 Knowledge for the reasons for the following responses Knowledge                                          responses as they apply to the SGTL:
makeup flow and letdown comparison of makeup                  letdown flow for various modesmodes of operation.
operation.
3.1/3.3 10CFR55: 41.b.7 10CFR55:
 
==Reference:==
4-ONOP-071.2, FO Page Item 1.b, 4-0NOP-071.2,                      1.b, 561  O-T-L 1, Sheet 32A 5610-T-L1, SD009, Page 37, SO-013, SO-009,              SD-013, Page 18  18 Cog Level:      2 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 charging pump speed will increase before operators respond and letdown will isolate following SI    SI/actuation
                                                            /actuation as a result of Phase A isolation. Plausible because letdown 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 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 charging pumps will trip when SI        SI actuates.
actuates. Letdown flow will initially  be unaffected initially be unaffected and letdown letdown flow will isolate isolate following Phase A actuation.
D.
O.      Incorrect because charging pump speed will increase before operators respond andand letdown      isolate following SI letdown will isolate            SI actuation as as aa result of of Phase Phase A A
isolation.
isolation. Plausible  because Letdown Plausible because    Letdown flow will initially    be unaffected initially be unaffected andand charging charging pumps pumps will trip trip when SISI actuates.
actuates.
40 40
 
NRC DRAFT NRC      DRAFT                                  07/24/07 07/24/07 Q #21 Q#21 Operators are Operators    are performing performing 3-0NOP-100, 3-ONOP-100, "Fast  Fast Load Load Reduction" Reduction inin response response to to rapidly dropping rapidly  dropping condenser condenser vacuum.
vacuum.
**  Unable to Unable      recover vacuum, to recover    vacuum, operators operators trip trip the the unit unit and and enter enter the the EOPs.
EOP5.
CC 8/3, 8/3, STEAM STEAM DUMP DUMP ARMED ARMED // ACTUATED, ACTUATED, has    has alarmed.
alarmed.
Two minutes Two  minutes after after the the unit    trip and unit trip        with the and with  the plant plant stable stable at at 545&deg;F, 545&deg;F, the the BOP BOP notes notes annunciator C annunciator    C 8/3 8/3 has has cleared.
cleared.
Which ONE Which    ONE ofof the  following describes the following    describes thethe reason reason for for annunciator annunciator C  C 8/3 8/3 clearing clearing AND the status of the SteamSteam Dump Dump to to Condenser Condenser (SDTC)(SDTC) System?
System?
The SDTC arming signal cleared when:
A.      vacuum dropped below  below 20".20.
The SDTC System is disabled.
B.      vacuum dropped below 20".      20.
The SDTC System remains fully functional.
C.      Tavg dropped to the low Tavg setpoint.
The SDTC System is disabled.
D.      Tavg dropped to the low Tavg setpoint.
The SDTC System remains fully functional.
41 41
 
NRC DRAFT NRC        DRAFT                                07/24/07 07/24/07 Q#21 Q#21 ANSWER:
ANSWER:        A A
KA:
KA:            000051AK3.01 000051AK3.01 Knowledge Knowledge for 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 condenser vacuum:
condenser    vacuum: loss loss of of steam steam dump dump capability capability, upon upon loss    of condenser    vacuum.
loss of condenser vacuum.
2.8/3.1 2.8/3.1 100FR55:
10CFR55:        41.b.4, 41.b.5 41.bA,41.b.5
 
==Reference:==
 
==Reference:==
0-T-L1, 561 O-T-L  1, Sheet 22A Cog Level:      2 Comprehension Comprehension Level 2 because the operator must recognize Level                                      recognize that 20" 20 is is aa condition that maymay bebe expected for this situation and is a signal that disables the SDTC while the 545&deg;F Tavg is a condition that could also be expected for this situation but does not disable the SDTC. Additionally the operator must recognize that the alarm may extinguish because the system has been disabled or has merely been reset and in this case the alarm is out because the system has been disabled.
New Question Response Analysis:
A.      Correct per the references B.      Incorrect because the SDTC system has become disabled. Plausible because it became disabled when vacuum dropped below 20.              20".
C.      Incorrect because even though Tavg did drop below the no-load Tavg under the influence of the SDTC system, no-load Tavg is not aa signal that disables the system. Plausible because Tavg did drop to no-load Tavg following the trip and the system has has been disabled.
disabled.
D.      Incorrect because the SDTC SDTC system has  has been disabled. Plausible Plausible because Tavg Tavg did did drop  below the no-load drop below        no-load Tavg setpoint following the trip. trip.
42 42
 
NRCDRAFT NRC      DRAFT                                07/24/07 07/24/07 Q #22 0#22 TheShift The  ShiftManager Managerdirects directsevacuation evacuation ofofthe thecontrol control room.
room.
** AtAtthe the Alternate Alternate Shutdown Shutdown PanelPanel (ASP),
(ASP), thethe RO RO inserts inserts handles handles into into the the yellow yellow bordered switches bordered    switches and and places placesthem them inin the the LOCAL LOCAL position.
position.
Which ONE Which    ONE ofofthe the following following describes describes thethe purpose purpose of ofthe the transfer transfer switches switches associa  ted with  the  AFW    flow  control associated with the AFW flow control valves    valves (FCVs)?
(FCVs)?
A.
A.      transfers control transfers  control ofof Train Train 22 FCVs FCVs to to the the ASP ASP B.
B.      enables local enables    local control control ofof Train Train 22 FCVs FCV5 C.
C.      aligns "8" aligns  B train train electrical electrical control control to  Train 11 FCVs to Train      FCVs D.
D.      aligns backup aligns  backup nitrogen nitrogen toto the the Train Train 1I FCVs FCVs 4343
 
NRC DRAFT NRC  DRAFT                            07/24/07 07/24/07 Q#22 Q#22 ANSWER:
ANSWER:          AA KA:
KA:              000068G2.1.28 000068G2.1.28 As itit relates As      relates to to the the control control room room evacuation evabuation event:
event: Knowledge Knowledge of of the the purpose purpose and and function of function    of major major system system components components and and controls.
controls. 3.2/3.3 3.2/3.3 IOCFR55:
10CFR55:          41.b.4, 41.b.7, 41.b.8 41.b.4,
 
==Reference:==
O-ONOP-1 05, Attachment 3, NOTE prior    prior to Step 6, Step 6 SD-I SD-153, 53, Page Page 41, Figure Figure 4C, 40 4D Cog Level:        11 Recall New Question Response Analysis:
A.        Correct per the reference B.        Incorrect because local control of the AFW valves is independent of the transfer switch. Plausible because these are the same Train 2 FCVs.
C.        Incorrect because the affected valves are Train 2 not Train 1. Plausible because the transfer switches transfer electrical control.
D.        IN correct because transfer of backup nitrogen is independent of the transfer switch. Plausible because Train 1    1 FCVs have backup nitrogen.
44 44
 
NRC DRAFT NRC    DRAFT                              07124/07 07/24/07 Q#23 Q#23 The crew The crew isis doing doing aa post post LOCA LOCA cooldown cooldown and and depressurization depressurization inin accordance accordance withwith 4-EOP-ES-1 .2, "Post 4-EOP-ES-1.2,    Post LOCA LOCA Cooldown Cooldown andand Depressurization."
Depressurization.
      **  4B RCP 4B    RCP has has been been started started for for forced forced cooling cooling and  RCS pressure and RCS    pressure control.
control.
      **  Two ECCs Two    ECC5 are    running are running
      **  All NCCs All  NCCs areare operating operating Containment pressure Containment    pressure just increased increased greater greater than than 20 20 psig.
psig.
Which ONE of the following following describes actions actions associated associated with operation operation of the Normal Containment Normal  Containment Coolers Coolers (NCCs)
(NCCs) AND AND thethe bases bases for for those those actions?
actions?
A. Continue Operation of the NCCs to maintain RCP operation and to assist          assist in pressure reduction.
containment pressure      reduction.
B. Continue operation of the NCCs NCC5 to maximize containment cooling and atmosphere circulation to prevent stratification and eliminate pockets of hydrogen.
C. Stop all NCCs to start the 3rd Emergency Containment Coolers without violating CCW System load requirements.
requirements.
D. Stop all NCCs because the 4B RCP must be secured and to prevent violating CCW System load requirements.
requirements.
45 45
 
DRAFT NRC DRAFT                          07/24/07 07/24/07 Q #23 Q#23 ANSWER:
ANSWER:        D D
KA:
KA:            WIEI4EK3.3 W/E14EK3.3 Knowledge for the reasons Knowledge            reasons for the following responses responses as they apply to the high high containment pressure: manipulation of controls required to obtain desired operating results during results  during abnormal abnormal andand emergency emergency situations.
situations. 3.5/3.5 3.5/3.5 I OCFR55:
10CFR55:        41 .b.7, 41.b.8, 41.b.7,  41 .b.8, 41.b.10 41 .b.1O
 
==Reference:==
4-EOP-F-O, Enclosure 5 4-EOP.-FR-Z.1, Step 1I 4-EOP-FR-Z.1, 4-EOP-FR-Z.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 NCCsNCC5 and RCPs have to be stopped per EOP-FR-Z.1.
Plausible because running NCCs  NCC5 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.1. Plausible because running NCCs would help to maximize containment air circulation.
C.      Incorrect because procedural limitations restrict operators from running three ECC. Plausible because an additional ECC would help with the containment pressure reduction.
D.      Correct, the NCCs NCCs are required to be stopped lAWlAW FR-Z.1 guidance.
46 46
 
NRC DRAFT NRC      DRAFT                                  07/24/07 07/24/07 Q#24 0#24 3-EOP-FR-C.2, "Response 3-EOP-FR-C.2,      Response to        Degraded Core to Degraded          Cooling, directs Core Cooling,"    directs operators operators to to depressurize the depressurize    the RCS RCS to to inject inject the the accumulators accumulators into into the the RCS.
RCS.
Which ONE Which    ONE of of the  following describes the following    describes how how the the RCS RCS will will be be depressurized depressurized to  to inject inject the accumulators    and the accumulators and how  how operators operators will will prevent prevent accumulator accumulator nitrogen nitrogen injection?
injection?
A.
A.      Open one Open          pressurizer PORV one pressurizer              until RCS PORV until    RCS pressure pressure is  is less less than than 180 180 psig.
psig.
Isolate accumulators Isolate  accumulators when  when RCS RCS pressure pressure isis less less than than 350 350 psig.
psig.
B.
B.      Open both Open          pressurizer spray both pressurizer      spray valves until  RCS pressure until RCS    pressure is  is less less than 180180 psig.
psig.
Isolate accumulators Isolate  accumulators when  when RCS RCS pressure pressure isis less less than than 350 350  psig.
psig.
C.              steam from intact S/Gs Dump steam                      S/Cs until SG SC Pressure is less than 180    180 psig.
psig.
Isolate Isolate  accumulators      when RCSRCS CET CET subcooling is    is less less than 30&deg;F.
30&deg;F.
D. Dump steam from intact S/Gs    S/Cs until S/G S/C pressure is less than 80 psig.
Isolate accumulators when RCS hot leg temperatures are less than 340&deg;F.                340&deg; F.
47 47
 
NRC DRAFT NRC    DRAFT                              07124/07 07/24/07 Q #24 Q#24 ANSWER:
ANSWER:        D D KA:
KA:              WIEO6EKI.1 W/E06EK1.1 Knowledge Knowledge of  of the  operational implications the operational  implications of of the the following following concepts concepts asas they they apply apply to to the  degraded core the degraded          cooling: components, core cooling:  components, capacity capacity andand function  of emergency function of emergency systems. 3.6/4.0 systems. 3.6/4.0 IOCFR55:
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 13  and 15 13 and  15 Cog Level:
Cog  Level:        Recall 1I Recall New Question Analysis:
Response Analysis:
A.      Incorrect because RCS pressure is reduced by dumping steam from intact SIGs. Plausible because opening a PORV is a method often used during S/Gs.
implementation to depressurize the RCS.
EOP implementation B.      Incorrect because RCS pressure is reduced by dumping steam from intact S/Gs. Plausible because opening pressurizer spray valves is a method often implementation to depressurize the RCS.
used during EOP implementation C.      Incorrect because the parameter used to judge when to stop dumping steam is S/G pressure, the stopping criteria in ECA-0.0 ECA-O.O is S/G Pressure at l8opsig.
180psig.
Plausible because reducing subcooling implies reducing RCS pressure also D.
D. Correct Correct perper the reference 48 48
 
NRC DRAFT NRC      DRAFT                              07/24/07 07/24/07 Q #25 Q#25 In accordance In  accordance with with 3-EOP-ES-1.1, 3-EOP-ES-1 .1, "SI    SI Termination,"
Termination, which which ONE ONE ofof the the following following describes why describes    why seal seal return return isis restored restored toto the the VCT VCT AND AND why why RCS RCS pressure pressure must must be be greater    than  100  psi above    VCT greater than 100 psi above VCT pressure    pressure before before establishing establishing seal seal return return flow?
flow?
Seal return Seal  return isis restored restored to to the the VCT VCT to:
to:
A.
A.      stop ## 1I sealleakoff stop        seal leakoff flow flow from from flowing flowing to  the PRT.
to the PRT.
RCS pressure RCS    pressure must must be      higher than be higher    than VCT VCT pressure pressure to to prevent prevent Hydrogen Hydrogen intrusion from the VCT into the      the RCS.
RCS.
B.
B.      stop ## 1I sealleakoff seal leakoff flow from flowing to the PRT. PRT.
RCS    pressure  must be higher than VCT pressure to prevent    prevent reverse flow from the VCT into the RCS.
C.      reinitiate # 11 seal leakoff flow.
RCS pressure must be higher than VCT pressure to prevent Hydrogen intrusion from the VCT into the RCS.
D.      reinitiate # 1I sealleakoff seal leakoff flow.
RCS pressure must be higher than VCT pressure to prevent reverse flow from the VCT into the RCS    RCS..
49 49
 
NRC DRAFT                                07124/07 07/24/07 Q #25 Q#25 ANSWER:
ANSWER:        BB KA:
KA:            W/EO2EK3.l W/E02EK3.1 Knowledge for the reasons Knowledge            reasons for the following responses as they they apply to the SI termination: Facility operating characteristics termination:                        characteristics during transient conditions, including coolant chemistry coolant  chemistry and and the effects effects of of temperature, pressure, pressure, and and reactivity reactivity changes changes and operating and  operating limitations limitations and reasons reasons for these operating characteristics.
characteristics. 3.3/3.6 3.3/3.6 10CFR55:
10CFR55:      41.b.2, 41.b.3, 41.b.10
 
==Reference:==
3-EOP-ES-1 .1, Step 20 BO 3-EOP-ES-1.1,                BD 5613-M-3047, 5613-M-3047,Sheet3 Sheet 3 Cog Level:    11 Recall New Question 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 C. Incorrect because stopping seal return flow to the PRT is the reason for restoring normal seal return. Note that even though seal return was isolated,
      #1 seal  leakoff still existed to the PRT. Plausible because Hydrogen is sealleakoff present in the VCT which can find its way to the RCS if aa flow path is established.
D.
O. 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,
      #1 seal  leakoff still existed to the PRT. Plausible because the stated reason sealleakoff for the required 100 100 psi differential in the Basis document document isis to prevent backf low from VCT to RCS, backflow 50 50
 
NRC DRAFT NRC      DRAFT                                07124/07 07/24/07 Q #26 Q#26 AA RCS RCS leak leak has has occurred occurred that    required aa manual that required    manual reactor reactor trip trip based based on on the the inability inability to  maintain Pressurizer to maintain  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 Depressurization.
Depressurization."
The US The  US directs directs the  RO to the RO      depressurize the to "depressurize    the RCS RCS to to refill refill the the pressurizer."
pressurizer.
ONE of Which ONE      of the the following identifies identifies the preferred preferred order order of  of methods methods toto depressurize the the RCS RCS asas directed directed by  4-EOP-ES-1 .2?
by 4-EOP-ES-1.2?
A.      1) Normal Spray
: 1)            Spray          PRZPORV
: 2) PRZ    PORV                    Spray
: 3) Aux Spray B.      1) Normal Spray          2) Aux Spray            3) PRZ PORV C.      1) Aux Spray                PRZPORV
: 2) PRZ    PORV          3) Steam Dump D.      1) Aux Spray            2) Normal Spray            PRZPORV
: 3) PRZ      PORV 51 51
 
NRC DRAFT NRC    DRAFT                            07124/07 07/24/07 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 asas they they apply apply to to LOCA    Cooldown    and  Depressurization: annunciators LOCA Cooldown and Depressurization:          annunciators andand 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 10CFR55:
10CFR55:                          41.b.1O 41.b.3, 41.b.7, 41.b.10
 
==Reference:==
 
==Reference:==
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-i    ES-1.2.2 and aa 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.
ES-1.2.
52 52
 
NRC DRAFT NRC      DRAFT                              07/24/07 07/24/07 Q #27 0#27 In  accordance with In accordance          4-EOP-FR-P.1, "Response with 4-EOP-FR-P.1,        Response to      Imminent Pressurized to Imminent  Pressurized Thermal Thermal Shock    Condition, which Shock Condition",      which ONE ONE of  of the the following following describes describes thethe purpose  of starting purpose of starting an an RCP  while responding RCP while      responding to  to aa pressurized pressurized thermal thermal shock shock condition?
condition?
An RCP An  RCP is is started started to:
to:
A.
A.      minimize the minimize          time to the time      reach Mode to reach    Mode 55 by by allowing allowing aa faster faster cooldown cooldown rate rate with with forced cooling forced    cooling than than with with natural natural circulation.
circulation.
B.
B.      restore normal restore              pressurizer spray normal pressurizer        spray capability to subsequently subsequently reduce reduce RCSRCS pressure    to the  right  of the  60&deg;/hr pressure the right of the 60&deg; Ihr cooldown    cooldown curve.
curve.
C.      mix the cold SI water with warm RCS water and decrease the likelihood of a PTS likelihood          PTS condition.
D.      mix the water in the vessel and loops to ensure boron concentration is equal throughout the reactor coolant system. system 53 53
 
NRC DRAFT NRC      DRAFT                            07124/07 07/24/07 Q #27 Q#27 ANSWER:
ANSWER:      CC KA:
KA:          WW/E08G2.1    .28 IE08G2.1 .28 RCS  overcooling - PTS, RCS overcooling    PTS, As As itit relates relates to to the the PTS PTS event:
event: Knowledge Knowledge ofof the the purpose purpose and function  of major and function of  major system system components components and  and controls.
controls. 3.2/3.3 3.2/3.3 100FR55:
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, Step 3-EOP-FR-P.1,        Step 27 BDBD Cog Level:    1I Recall New Question New Response Analysis:
A. Incorrect because starting an RCP does not allow a faster cooldown rate in FR-Ri. Plausible because the normal cooldown rate limit with RCPs is FR-P.1.
1100&deg;F/hr OO&deg;F/hr and without RCPs is 25&deg;F/hr.
B. Incorrect because RCS pressure will be subsequently maintained within a band between the minimum subcooling curve and the 200&deg;F      200&deg; 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 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 benefit.
54 54
 
NRC DRAFT NRC      DRAFT                              07/24/07 07/24/07 Q #28 0#28 Operators are Operators      are cooling cooling down down the the plant plant in in accordance accordance with with 3-GOP-305, 3-GOP-305, "HotHot Standby Standby to Cold to  Cold Shutdown".
Shutdown. 3B  3B RCP RCP pump      bearing temperature pump bearing      temperature has has been been slowly slowly increasing increasing and has and  has just just reached reached the the alarm alarm setpoint setpoint value.
value.
The present The  present plant plant conditions conditions are are as as follows:
follows:
            **  RCS pressure RCS  pressure isis 600 600 psig.
psig.
            **  3B RCP    #1 seal  AP  is 3B RCP #1 seal llP is >> 400 400 psid.
psid.
* 3B RCP 3B RCP seal seal injection flow is 10 10 gpm.
gpm.
            **  3B RCP 3B RCP #1 sealleakoff seal leakoff flow is  is 0.9 0.9 gpm.
gpm.
            **  3B RCP RCP # 11 sealleakoff seal leakoff isol isol valve, CV-3-303B, CV-3-303B, isis open.
Which ONE of the following describes the correct operator response?
A.      Increase seal injection flow to the 3B RCP to greater than 13 gpm.      gprn.
B.      Open the RCP Seal Bypass Valve, CV-3-307.
C.      Close the 3B RCP #1 seal leakoff isol valve, CV-3-303B.
D.      Increase CCW flow through the 3B RCP thermal barrier.
55 55
 
NRC DRAFT NRC    DRAFT                              07124/07 07/24/07 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  control room the control 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:==
 
==Reference:==
3-GOP-305, Step 3-GOP-305,      Step 5.3.5.9.d 5.3.5.9.d 3-ONOP-041 3-0NOP-041.1        Step 35
                              .1,, Step  35 Level:
Cog Level:      2 Comprehension Comprehension Level 2 because Level      because the operators mustmust evaluate plant plant conditions and determine that opening the bypass valve would improve the RCP 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 sealleakoff seal leakoff flow rate is low and the RCP bearing temperature is increasing.
B.      Correct per the reference.
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, (GOP-305, Step 5.19.14,9.b) and would terminate the flow of hot  hot water to the VCT D.      Incorrect Incorrect because the required procedural response is to open the RCP Seal Bypass    Valve, CV-3-307.
Bypass Valve,    CV-3-307. Plausible Plausible because increasing increasing CCW CCW through through the thermal thermal barrier barrier would would be be beneficial to to pump pump bearing bearing cooling ifif seal seal injection injection flow was was lost.
lost.
56 56
 
NRC DRAFT NRC    DRAFT                              07/24/07 07/24/07 Q #29 0#29 Unit 33 is Unit    is at at 100%  power when 100% power    when VCT VCT level level transmitter, transmitter, LLT-3-1 T-3-115, 15, fails fails high.
high.
Which ONE ONE of      following describes the effect of the following                effect on the plant plant assuming assuming NO  NO operator action?
action?
level will:
VCT level A.      decrease.
Auto-makeup will NOT occur.
Auto-swap to the RWST will occur.
B:
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-1 ISA will auto-divert to the CVCS HUT.
LCV-115A D.      increase.
automatically.
Auto-makeup will start but NOT stop automatically.
LCV-1 ISA will auto-divert to the CVCS HUT.
LCV-115A 57 57
 
DRAFT NRC DRAFT                              07/24/07 07/24/07 Q #29 Q#29 ANSWER:
ANSWER:      BB KA:
KA:          004K11.23 004K  .23 Knowledge of Knowledge  of the physical physical connection and/or cause-effect relationships between the CVCS 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.
C. Incorrect because VCT level will decrease and auto-makeup will not occur.
LCV-1 1 5A will auto-divert to the CVCS HUT.
Plausible because LCV-115A D. Incorrect because VCT level will decrease and auto-makeup will not occur.
Plausible because LCV-I  1 5A will auto-divert to the CVCS HUT.
LCV-115A 58 58
 
NRC DRAFT NRC      DRAFT                              07/24/07 07/24/07 Q #30 Q#30 Unit 33 isis operating Unit          operating at at 75%  power when 75% power  when an      Instrument Air an Instrument    Air System System leak leak reduces reduces the the IA  pressure to IA pressure      to 60  psig on 60 psig  on both both units.
units.
Operator actions Operator      actions are    unsuccessful in are unsuccessful    in restoring restoring IA IA pressure.
pressure.
Which ONE Which      ONE of  of the the following following describes describes the the effect effect of  this event of this event on on Unit Unit 33 pressurizer pressurizer level  and    the  correct  operator level and the correct operator response?response?
Pressurizer level Pressurizer      level will:
A.        decrease.
decrease.
Trip the reactor and perform EOP-E-O,EOP-E-0, "Reactor Reactor Trip or Safety Injection."
Injection.
B        decrease.
Start additional charging pumps and increase speed using 3-0P-047,      3-OP-047, "cvcs CVCS Charging and Letdown."
Letdown.
C        increase.
Trip the reactor and perform EOP-E-O,EOP-E-0, "Reactor Reactor Trip or Safety Injection."
Injection.
D.        increase.
Open additional letdown orifice isolation valves using 3-0P-047,  3-OP-047, "cvcs CVCS Letdown.
Charging and Letdown."
59 59
 
NRC DRAFT NRC      DRAFT                              07/24/07 07/24/07 Q#30 Q#30 ANSWER:
ANSWER:          C C
KA:
KA:              004A2.11 004A2.11 Ability to Ability  to (a)
(a) predict predict the the impacts impacts of of the the following following malfunctions malfunctions or    operations on or operations  on the the CVCS; and CVCS;    and (b)
(b) based based onon those those predictions, predictions, useuse procedures procedures to to correct, control, or correct,  control,  or mitigate  the consequences mitigate the    consequences of  of those those malfunctions malfunctions oror operations:
operations: loss loss of of lAS.
lAS.
3.6/4.2 3.6/4.2 10CFR55:
10CFR55:          41.b.4, 41.b.5, 41.b.1 41.bA,          41.b.1O  0
 
==Reference:==
 
==Reference:==
O-ONOP-013, FO 0-ONOP-013,      FO Page Page Cog Level:
Cog                Comprehension 2 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-O.
B.      Incorrect because pressurizer level will increase. Plausible because if level were to decrease, starting additional charging pumps would be the appropriate operator response.
resp~mse.
C.      Correct per the reference D.      Incorrect because opening additional orifice valves is not possible due to the loss of loss  of IA.
IA. Plausible because because pressurizer level level will increase.
increase.
60 60
 
NRC DRAFTDRAFT                              07/24/07 07/24/07
  #31 Q #31 Q
Unit 44 is Unit    is inin Mode Mode 44 with with RHR RHR cooling cooling inin service.
service.
The automatic The  automatic controller controller circuit circuit for for RHR RHR HeatHeat Exchanger Exchanger Bypass Bypass Flow Flow control control valve, valve, FCV-4-605 has FCV-4-605              failed resulting has failed  resulting in in the the FCV FCV going going closed.
closed.
Which ONE Which    ONE of  of the the following following describes describes the the correct correct operator operator response?
response?
Place FCV-4-605 controller in Manual Place                                  Manual and raise flow to:
A.      between 3000 and 3750 gpm.
between IfIf manual control is is NOT NOT possible, possible, direct the NSONSO to locally 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 HCV4-758 to raise flow to between 3000 and 3750 gpm.
control valve, HCV-4-758 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.
61 61
 
NRC DRAFT NRC      DRAFT                        07124/07 07/24/07 Q#31 Q#31 ANSWER:
ANSWER:          AA KA:
KA:                005G2.1.30 005G2.1.30 As itit relates As      relates to  RHR, ability to RHR,  ability to to locate locate and and operate operate components, components, including including local local controls. 3.9/3.4 controls. 3.9/304 IOCFR55:
10CFR55:          41.b.4, 41.b.7, 41.bo4,  41.b.7, 41.b.8, 41.b.8, 41.b.10 41.b.10
 
==Reference:==
 
==Reference:==
4-ONOP-050, Step 77 4-0NOP-050, Cog Level:
Cog    Level:    1I memory memory New Question Response Analysis:
A.        Correct per the reference 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.
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 aa previous revision of ONOP-050 had operators increase flow using HCV-758.
HCV-758.
62 62
 
NRC DRAFT NRC        DRAFT                            07/24/07 07/24/07 Q #32 0#32 The RO The RD manually manually tripped tripped the  reactor due the reactor    due to  decreasing pressurizer to decreasing  pressurizer pressure.
pressure. An An automatic SI automatic  SI occurred occurred on on the the trip trip depressurization.
depressurization.
RCS pressure RCS  pressure isis currently currently 1700 1700 psig psig and and slowly slowly lowering.
lowering.
One minute after One minute  after the the automatic automatic SI SI signal signal actuated, actuated, the the RO RD depressed depressed both both SI SI reset reset pushbuttons  on  VPB.
pushbuttons on VPB.
ONE of the following describes the response Which ONE                                          response of the safety injection injection system?
A. SI immediately SI  immediately reset reset when the the reset  pushbuttons were depressed.
reset pushbuttons        depressed.
B. SI reset occurs one minute after the reset pushbuttons were depressed.
C. SI reset occurs two minutes after the reset pushbuttons were depressed.
D. SI did NOT reset but will reset if the operators push the reset buttons after the 2 minute timer has timed out.
63 63
 
NRC DRAFT DRAFT                              07124/07 07/24/07 Q #32 Q#32 ANSWER:
ANSWER:          BB KA:
KA:              006A4.08 006A4.0B ECCS - Ability to manually ECCS      -          manually operate and/or monitor monitor in the 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:==
561 O-T-L1, 5610-T-L  1, Sheet 11 Level:
Cog Level:          Comprehension 2 Comprehension Level 2 because the operator must recognize that the SI reset logic is different if the initiating event was SI due to automatic actuation or manual actuation. The SI signal automatically actuated, 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 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 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 will reset after one more minute, B.      Correct. There is aa two minute delay so SI will reset within one minute.
C.      Incorrect Incorrect because SI was already reset. ItIt reset one minute minute earlier as the 22 minute minute timer is from initiation signal and not the reset signal. Plausible because the reset logic does useuse aa 22 minute timer and this would be aa correct response if the RO attempted to reset immediately.
D.
D.      Incorrect. The 22 minutes Incorrect. The    minutes must must be be over over before before the reset will work from aa manual manual actuation. Plausible Plausible because because this this would apply      SI was apply ifif SI was manually manually initiated.
initiated.
64 64
 
DRAFT NRC DRAFT                            07/24/07 07/24/07 Q #33 Q#33 Operators are Operators      are preparing preparing to to reduce reduce PRT PRT pressure pressure which which has has approached approached itsits upper upper limit of limit  of 10  psig.
10 psig.
Which ONE of the following describes the processprocess for reducing reducing PRT PRT pressure pressure under these conditions?
Verify the PRTPRT nitrogen    regulator, PCV-3-473, nitrogen regulator, PCV-3-473, is:
is:
A.        aligned to the PRT.
Start a waste gas compressor. Open the PRT vent valve, CV-3-549.
When PRT pressure reaches 6 psig to 8 psig, then close CV-3-549.
B.        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.        isolated from the PRT.
Start a waste gas compressor. Open the PRT vent valve, CV-3-549.
CV3-549.
When PRT pressure reaches 6 psig to 8 psig, then close CV-3-549.
D.        isolated from 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.
65 65
 
NRC DRAFT                            07/24/07 07/24/07 Q #33 Q#33 ANSWER:
ANSWER:        AA KA:
KA:              007A1.02 predict and/or monitor changes in Ability to predict                          in parameters parameters (to prevent prevent exceeding design limits) associated with operating the PRTPRT controls controls including maintaining maintaining PRT PRT pressure. 2.7/2.9 pressure. 2.7/2.9 IOCFR55:
10CFR55:                        41.b.1O 41.b.3, 41.b.4, 41.b.10
 
==Reference:==
3-OP-041.3, Section 7.3.2 3-0P-041.3, Cog Level:      1I Recall New Question Response Analysis:
A.      Correct per the reference B.      Incorrect because PRT pressure must reach 6 to 8 psig before closing CV-549. Plausible because the PRT nitrogen regulator, PCV-3-473, is aligned to the PRT.
C.      Incorrect because the PRT nitrogen regulator, PCV-3-473, is aligned to the PRT. Plausible because when PRT pressure reaches 6 psig to 88 psig, then CV-3-549 is closed.
D.      Incorrect because the PRT nitrogen regulator, PCV-3-473, is aligned to the PRT and because PRT pressure must reach 6 to 8      8 psig before closing CV549.
CV-549. Plausible because vent header pressure is lower than 66 to 88 psig and would represent aa greater pressure reduction than that provided by the procedure instructions.
66 66
 
NRC DRAFT NRC      DRAFT                                  07124/07 07/24/07 Q #34 0#34 Unit 33 operators Unit    operators areare responding responding to to aa Loss Loss ofofAll All AC AC Power Power (LOAAC).
(LOAAC).
** The The BOP BOP isis using using 3-0NOP-004.2, 3-ONOP-004.2, "Loss  Loss of of 3A 3A 4KV 4KV Bus,"
Bus, toto restore restore the the 3A3A 4KV 4KV Bus which Bus  which failed failed to  load onto to load  onto its its EDG EDG because because of        failure of of aa failure      the 3A  sequencer.
of the 3A sequencer.
** AsAs the the BOP BOP verifies verifies 3A3A 4KV 4KV busbus stripping, stripping, he he notes notes that that the the 3A 3A Bus Bus loads loads that that were  running    before were running before the    the LOMC LOAAC stillstill show show breaker breaker closed closed indication indication (red (red light).
light).
** The The BOP BOP places places each each ofof the the 3A 3A Bus Bus components' components control        switches inin the control switches          the STOP STOP position.
position.
Which ONE Which    ONE of    the following of the  following describes describes the the response response of of the the 3A 3A CCWCCW pump pump breaker breaker light indication  on  VPB    after light indication on VPB after the    the BOP BOP places places its its control control switch switch in in STOP?
STOP?
The 3A The    3A CCW CCW pump green light will:
A.
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 out and the red light will go on.
D.      remain on for 30 seconds at which time it will go out and the red light will go on.
67 67
 
NRC DRAFT                                07124/07 07/24/07 Q #34 Q#34 ANSWER:
ANSWER:          C C
KA:
KA:              008A4.08 OOBA4.0B manually operate and/or monitor Ability to manually                    monitor in in the control room: CCW pump control 3.1/3.8 switch. 3.1/3.B 10CFR55:
10CFR55:          41.b.4, 41.b.7 41.b.4,41.b.7
 
==Reference:==
561 0-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 pumps. When the operator takes the 3A CCW 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/bus 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 green light will remain on for only only 10 10 seconds at which time it will go out and the red red light light will come on. Plausible because this is the way 3C CCW pump indication would respond under these conditions and this is is the same same train pump.
pump.
68 68
 
NRC DRAFT NRC    DRAFT                            07/24/07 07/24/07 Q #35 Q#35 Unit 33 is Unit    is at at 70%    power with 70% power          all systems with all systems inin normal normal operation.
operation.
The  control group The control    group ofof pressurizer pressurizer heaters heaters malfunctions malfunctions and and goes goes to to minimum minimum output.
output.
Which ONE Which    ONE ofof the the following following describes describes the    effect on the effect  on the pressurizer pressure the pressurizer  pressure control control system AND system    AND the the operator operator response response required required by by 3-0NOP-041.5, 3-ONOP-041 .5, "Pressurizer Pressurizer Pressure Control Pressure    Control Malfunction"?
Malfunction?
Both groups Both  groups of of backup backup heaters heaters will automatically automatically operate:
operate:
A.        immediately.
immediately.
Dispatch an operator to locally verify the control group heater breakers are closed.
closed.
B.      immediately.
immediately.
Manually cycle backup heaters as needed to maintain pressure at 2235 psig.
C.      when pressurizer pressure drops to 2210 psig.
Dispatch an operator to locally verify the control group heater breakers are closed.
D.      when pressurizer pressure drops to 2210 psig.
Man ually cycle backup heaters as needed to maintain pressure at 2235 psig.
Manually 69 69
 
NRC DRAFT                                07/24/07 07/24/07 Q #35 Q#35 ANSWER:
ANSWER:        C C
KA: 01 KA:  010A2.01-              (a) predict OA2.01- Ability to (a)  predict the impacts impacts of the following malfunctions malfunctions or operations on the PRZ      PCS; and (b)
PRZ PCS;            based on those predictions, (b) based            predictions, use procedures procedures to correct, control, or mitigate the consequences consequences of  of those malfunctions or operations:
Heater failures. 3.3/3.6 Heater            3.3/3.6 10CFR55:
10CFR55:                41.b.4, 41.b.7 41.b.3, 41.bA,
 
==Reference:==
3-ONOP-041 .5, Step 12 3-0NOP-041.5,          12 5610T-D-16B, Sheet 11 5610-T-D-16B, Comprehension Cog Level: 2 Comprehension
.Level 2 because the operator must realize that the Control Group going to
.Level2 minimum will result in a decrease in pressurizer pressure. The operator must then recall that the backup groups will both energize at 2210 psig and the correct response is to check the control group heater status.
New Question Response Analysis:
A.      Incorrect because the backup heaters will not energize until pressure drops to 2210 psig. Plausible because an operator should be dispatched to locally verify the control group heater breakers are closed.
B.      Incorrect because the backup heaters will not energize until pressure drops to 2210 psig and operators are not directed to use the backup heaters to control pressure at 2235 psig. Plausible because normal pressure is 2235 psig and controlling pressure at that value is easily done using the backup heaters.
C.      Correct per the reference D.      Incorrect because operators are not  not directed directed to use the backup heaters to control pressure at 2235 psig. Plausible because the backup heaters will not    not energize until pressure drops to 2210 psig.
70 70
 
NRC DRAFT NRC    DRAFT                                07/24/07 07/24/07 Q #36 Q#36 Operators are Operators      are performing performing aa shutdown shutdown of    Unit 44 reactor.
of Unit    reactor.
**  Power level Power    level isis currently currently 50%.
50%.
**  First  stage    pressure    transmitter, First stage pressure transmitter, PT-4-447,PT-4-447, fails fails 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 aa plant plant shutdown?
shutdown?
At the current current power power level, level, aa turbine turbine trip signal can:
can:
A.      cause aa reactor cause        reactor trip.
When power is      is less than 10%,
10%, turbine trip will be able to cause reactor trip.
B.      cause a reactor trip.
When power is less than 10%, turbine trip will NOT be able to cause reactor trip.
c.
C.      NOT cause a reactor trip.
When power is less than 10%, turbine trip will be able to cause reactor trip.
D.      NOT cause a reactor trip.
When power is less than 10%, turbine trip will NOT be able to cause reactor trip.
71 71
 
NRC DRAFT NRC                                      07124/07 07/24/07 Q #36 Q#36 ANSWER:
ANSWER:        A A
KA:
KA:            012K4.06 012K4.06 Knowledge of Knowledge      the RPS of the  RPS design design feature(
feature(s) s) and/or and/or interlock( s) which interlock(s) which provide provide forfor automatic automatic  or manual  enable/disable manual enable/disable of of RPS RPS trips.
trips. 3.2/3.5 3.2/3.5 100FR55:
10CFR55:      41.b.7
 
==Reference:==
0-T-L1, 561 O-T-L            Sheet 17 1, Sheet 2, Sheet Cog Level:    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 B.      Incorrect because when power is <10%, turbine trip will be able to cause a reactor trip. Plausible because a turbine trip signal can presently cause a reactor trip C.      Incorrect because a turbine trip signal can presently cause aa reactor trip.
Plausible because when power is <10%, turbine trip will be able to cause aa reactor trip.
D.      Incorrect because aa turbine trip signal can presently cause aa reactor trip and because when power is <10%, turbine trip will be able to cause aa reactor trip.
Plausible because the turbine trip is not normally able to cause aa reactor trip below 10%
10% power.
72 72
 
NRC DRAFT NRC      DRAFT                                    07/24/07 07/24/07 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 forfor NIS NIS power range power    range channel channel N-41N-41 which which isis OOS DOS withwith bistables bistables tripped.
tripped.
Subsequently power Subsequently        power range range channel channel N-42N-42 fails fails low.
low.
Which ONE Which    ONE of of the the following following describes describes the the immediate immediate effecteffect of of the the N-42 N-42 failure failure onon the reactor the  reactor trip trip logic?
logic?
A.
A.        The reactor The  reactor trip trip logic logic is is NOT NOT affected affected by  by the the N-42 N-42 failure.
failure.
B.
B.        The RCS The  RCS Loop Loop Low Low Flow Flow reactor reactor trip    logic is trip logic    is disabled disabled byby the the N-42 N-42 failure failure C.
C.            RCS Loop The RCS        Loop Low Low Flow Flow reactor reactor trip logic logic changed changed to 22 of  of 33 flow flow channels channels to trip on 1I of 3 loops.
loops.
D.
D.            reactor trip logic The reactor            logic disables the at-power reactor trips with 2 of 4 channels
        <<10%
10% power.
73 73
 
NRC DRAFT                                07/24/07 Q#37 ANSWER:        A KA:            012K6.02 Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Redundant Channels. 2.9/3.1 IOCFR55:
10CFR55:        41.b.7
 
==Reference:==
5610-T-L1, 561 O-T-L 1, Sheet 2, Sheet 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. This effectively changed the trip logic from 2 of 4 channels on 2 of 3 loops to 11 of 3 channels on 2 of 3 loops. When power above P-8" N-42 failed low it could not 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 trip logic remains the same even though N-42 input has been disabled.
New Question Response Analysis:
A.      Correct per the reference B.      Incorrect because the RCS Loop Low Flow reactor trip logic was not affected by this N-42 failure. Plausible because the N-42 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 was initially changed to I of 3 NIS channels to trip when the N-41 bistables were originally thrown.
1 D.      Incorrect because the at-power trips require 3 of 4 power range channels be below 10% to be disabled. Plausible because the reactor trip logic does disable the at-power reactor trips when <  < 10% power.
74 74
 
NRC DRAFT NRC      DRAFT                              07/24/07 07/24/07 Q #38 0#38 Operators are Operators    are responding responding toto aa main main steam steam line line break break outside outside containment.
containment.
**  All safety All  safety systems systems functioned functioned asas designed.
designed.
**  SI  has  been  reset.
S I has been reset.
**  The BOP The    BOP goes goes behind behind VPB VPB to to reset reset Containment Containment Isolation Isolation Signals.
Signals.
The RO The  RO continues continues toto monitor monitor the  control boards the control  boards and and notes notes the the status status of of annunciator H annunciator    H 5/2, 5/2, CNTMT CNTMT ISOLATION ISOLATION ACTIVATED.
ACTIVATED.
Which ONE ONE ofof the following following correctly correctly describes describes the the status status ofof annunciator annunciator H H 5/2?
5/2?
Before the BOP begins to reset Containment Isolation relays, H 5/2 is:
A.      in alarm, because Phase A and Containment Ventilation Isolation relays are tripped. After the BOP resets relays, H 5/2 is NOT in alarm because Phase A relays          are reset.
B.      in alarm, because Phase A and Containment Ventilation Isolation relays are tripped. After the BOP resets relays, H 5/2 is still in alarm because Containment Ventilation Isolation relays are still tripped.
C.      not in alarm, because Phase B      B relays have not tripped.
After the BOP resets relays, H      H 5/2 is NOT in alarm because Phase B          B relays have NOT tripped and Phase A relays are reset.
D.      NOT in alarm, because Containment Ventilation Isolation relays have NOT tripped. After the BOP resets relays, H        H 5/2 is still in alarm because Phase A relays cannot be reset under these conditions.
75 75
 
NRC DRAFT DRAFT                                  07/24/07 07/24/07 Q #38 Q#38 ANSWER:
ANSWER:        BB KA:
KA:              013A4.02 013A4.02 Ability to Ability    manually operate to manually  operate and/or and/or monitor monitor in in the the control 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:==
4-EOP-E-1, Step 7 4-ARP-097.CR, H    H 5/2 Sht. 11 5610-T-L1, Sht.11 Cog Level:      2 Comprehension Level 2 because the operator must recognize that a steamline break outside containment will trigger Phase A and Containment Ventilation Isolation, but not Phase B. Additionally the operator must recognize that the alarm is active when any of the 3 signals have not been reset. It takes the reset of all 3 signals to clear the alarm.
New Question Response Analysis:
A.      Incorrect because after the BOP resets relays, H      H 5/2 is still in alarm because Containment Ventilation Isolation relays are still tripped. Plausible because before the BOP begins to reset Containment Isolation relays, H            H 5/2 is in alarm, because Phase A and Containment Ventilation Isolation relays are tripped.
B.      Correct per the reference C.      Incorrect because before the BOP begins to reset Containment Isolation relays, HH 5/2 is in alarm, because Phase A and Containment Ventilation Isolation relays are tripped. After the BOP resets relays, H        H 5/2 is still in alarm because Containment Ventilation Isolation relays are still tripped.
Plausible because Phase B      B relays have not tripped and after the BOP resets relays, Phase A relays are reset.
D.      Incorrect because before the BOP begins to reset Containment Isolation          Isolation relays, HH 5/2 is in alarm, because Phase A and Containment Containment Ventilation Isolation relays are tripped.
tripped. After the BOP resets relays, H      H 5/2 5/2 is is still in in alarm  because alarm because Containment Ventilation Isolation relays are Containment    Ventilation  Isolation          are still still tripped.
tripped.
Plausible  because after Plausible because    after the the BOP BOP resets resets relays, H H 5/2 5/2 is is still still in in alarm.
alarm.
76 76
 
NRC DRAFT NRC    DRAFT                          07124/07 07/24/07 Q#39 Q#39 Operators are Operators  are responding responding to to aa simultaneous simultaneous LOOP/LOCA LOOP/LOCA event.
event.
3A EDG 3A EDG failed failed to to start.
start.
Which ONE Which  ONE ofof the  following describes the following  describes the the status  of the status of  the Emergency Emergency Containment Containment Coolers (ECC5)    after sequencing Coolers (ECCs) after      sequencing isis complete?
complete?
3A ECC 3AECC                    3B ECC 3B  ECC                    ECC 3C ECC 3C A.
A. de-energized            running running                running running B. de-energized            stopped              running C. running running                  stopped              de-energized D. running                  running              de-energized 77 77
 
NRC DRAFT                              07124/07 07/24/07 Q #39 Q#39 ANSWER:
ANSWER:        CC KA:            022K2.01 Knowledge of the power supplies to the containment cooling fans. 3.0/3.1 Knowledge IOCFR55:
10CFR55:        41.b.8, 41.b.10 41.b.8,41.b.10
 
==Reference:==
SD-029, Page 15  15 5610-T-E-1591, 561 0-T-E-1591, Sheet 1I 5613-T-L1, 5613-T-L            12B 1, Sheet 128 Cog Level:    2 Comprehension Level 2 because the operator must recognize that the sequencers will auto-start their respective ECCs if power to the bus is available. 3A ECC is powered from the B train (38 "8"        (3B MCC, bkr 30650). 3C ECC is powered from the "A"    A train 3C MCC, bkr 30729). 38 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 38 does not auto-start.
Plausible because 3A safeguards equipment is normally powered from 3A Train which is de-energized.
B.      Incorrect because 3C ECC is de-energized. Plausible because 3A safeguards equipment is normally powered from 3A Train which is de      de-energized.
C.      Correct per the references D.      Incorrect because 3B38 ECC ECC does notnot auto-start. Plausible because 3A  3A ECC ECC is is running and 3C 3C ECC ECC isis de-energized.
78 78
 
NRC DRAFT NRC      DRAFT                            07124/07 07/24/07 Q #40 0#40 Following aa large Following      large break break LOCA, LOCA, operators operators have have transitioned transitioned toto 3-EOP-ES-1.3, 3-EOP-ES-1 .3, Transfer to "Transfer      Cold Leg to Cold    Leg Recirculation,"
Recirculation, andand are are determining determining ifif "piggy-back" piggy-back recirculation will recirculation  will be be required.
required.
The RO The  RO reports reports the the following following information:
information:
**  RHR flow RHR    flow on on FI-3-605 F 1-3-605 isis 2800 2800 gpm gpm
**  Containment pressure Containment      pressure isis 1212 psig.
psig.
**  Containment      temperature Containment temperature is        is 178&deg;F.
178&deg;F.
**  All ECF All ECF spray spray valves valves are are closed.
closed.
ONE of Which ONE      of the following is  is correct regarding regarding subsequent subsequent Containment Containment Spray Spray Pump  (CSP)  operation?
Pump (CSP) operation?
Operators will run:
A.      No CSPs.
CSP5.
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).
79 79
 
NRC DRAFT                                07/24/07 07/24/07 Q #40 Q#40 ANSWER:          C KA:              026K4.0l 026K4.01 Knowledge of the CSS design feature( feature(s)        interlock(s) s) and/or interlock( s) which provide for:
source of water for CSS, including recirculation phase after LOCA 4.2/4.3 IOCFR55:
10CFR55:        *41.b.7, 41.b.8 41.b.7,41.b.8
 
==Reference:==
3-EOP-ES-1.3, Steps 18, 21, 23, 25, 26 Cog Level:        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 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    I 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 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).
80 80
 
NRCDRAFT NRC      DRAFT                                07124/07 07/24/07 Q#41 0#41 Operators are Operators    are performing performing 3-EOP-E-1, 3-EOP-E-1, "LossLoss of of Reactor Reactoror orSecondary Secondary Coolant" Coolant and and thefollowing the  following plant plant conditions conditions exist:
exist:
        **  RCS Pressure RCS    Pressure isis 1000 1000 psig psig
        **  All RCPs are All RCPs    are OffOff
        **  Contai  nment    Tempe Containment Temperature    rature isis 220&deg;F 220&deg;F
        **  Containment Pressure Containment        Pressure isis 19 19 psig psig and and rising rising
        **  Two  ECCs are Two ECCs      are running running
        **  All Available    Charging All Available Charging Pumps  Pumps areare running running
        **  The RCS The  RCS isis saturated saturated
        **  RWST level RWST    level isis 220,000 220,000 gallons gallons Containment Pressure Containment    Pressure has  has just just increased increased to to 2121 psig.
psig. The The operators operators entered entered 3-EOP-FR-Z.1, "Response 3-EOP-FR-Z.1,      Response to    to High High Containment Containment Pressure" Pressure and    are  assessing and are assessing Containment Spray Containment    Spray pumps pumps (CSPs)
(CSP5) status.
status.
Which one of the following describes Which                            describes the correct plant  plant and operator operator response?
response?
A.
A.      Neither CSP auto-started.
auto-started.
Manually Manually start both CSPs.
B.
B.      Neither CSP auto-started.
auto-started.
Manually start one CSP and place the other CSP in Pull-To-Lock Manually                                                          Pull-To-Lock..
C.      Both CSPs auto-st      arted.
auto-started.
Verify both CSPs auto-st        arted.
auto-started.
D.
D.      Both CSPs auto-st      arted.
auto-started.
Manually Manually stop stop one one CSP CSP and and place place itit in in Standb Standby.y.
8181
 
NRC DRAFT DRAFT                            07124/07 07/24/07 Q #41 Q#41 ANSWER:
ANSWER:          A A
KA:
KA:              026A1.O1 026A 1.01 Ability to  predict and/or to predict  and/or monitor monitor changes changes inin parameters parameters (to (to prevent prevent exceeding exceeding design    limits) associated design limits) associated    with operating the CSS operating the  CSS controls controls including including containment containment pressure 3.9/4.2 pressure    3.9/4.2 10CFR55:
10CFR55:          41.b.7, 41.b.8 41.b.7,41.b.8
 
==Reference:==
 
==Reference:==
5610-T-L1, 5610-T-L          11 1, Sheet 11 5613-T-L1, 5613-T-L          12A 1, Sheet 12A 3OEOP-E-O, Attachment 3, Step 12 30EOP-E-0, 3-EOP-FR-Z.1,, Step 8 3-EOP-FR-Z.1 Cog Level: 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.
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.1, Step 8 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 to verify both CSPs are running lAW 3-EOP-FR-Z.1, Step 88 guidance.
D.      Incorrect because neither CSP auto-started. Plausible because operators are directed to manually stop one CSP and place it in Standby if containment pressure is << 1414 psig.
82 82
 
NRC DRAFT NRC      DRAFT                              07/24/07 07/24/07 Q #42 0#42 Operators have Operators  have responded responded to  to aa small small break break LOCA LOCA on on Unit Unit 33 and and are are performing performing 3-EOP-ES-1 .2, Post-LOCA 3-EOP-ES-1.2,      Post-LOCA Cooldown Cooldown and  and Depressurization."
Depressurization.
The RO The RD isis preparing preparing to to initiate initiate an an RCS RCS cooldown cooldown to  Cold Shutdown to Cold  Shutdown by  by dumping dumping steam  from  intact  steam    generators.
steam from intact steam generators.                                  .
Which ONE Which  ONE of of the the following following describes describes why    the RO why the  RO must must limit limit steam steam flow flow rate rate to to maintain the maintain  the allowable allowable coolcool down down rate rate below below 100&deg;F/hr?
100&deg;F/hr?
Excessive steam Excessive  steam flow    rate may flow rate    may result result in:
in:
A. termination of RCS natural circulation flow.
B. challenging the integrity status tree for pressurized 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            SIG levels above 6% which will require stopping the cooldown.
83 83
 
NRC DRAFT DRAFT                            07124/07 07/24/07 Q #42 Q#42 ANSWER:
ANSWER:      BB KA:
KA:            039K5.05 039K5.05 Knowledge of Knowledge  of the the operational operational implications implications of  the following of the following concept concept as as itit applies applies to to the  MRSS:  Basis the MRSS: Basis    for the RCS  cooldown the RCS cooldown limits limits 2.7/3.1 2.7/3.1 IOCFR55:
10CFR55:                41.b.4, 41.b.5, 41.b.10 41.b.3, 41.bA,            41.b.1O
 
==Reference:==
3-EOP-ES-1 .2, Step 6, BD 3-EOP-ES-1.2, Cog Level:    1I Recall New Question Response Analysis:
A. Incorrect because excessive steam flow will not prevent RCS NC flow.
Plausible because excessive steam flow may temporarily retard NC flow.
B. Correct per the reference C. Incorrect because excessive steam flow will not occur under these conditions. Only possible when you cooldown at maximum rate      rate....
D. Incorrect only ECA-O.O requires stopping the cooldown rate if SG level is less than 6% in all SGs.
84 84
 
NRC DRAFT NRC      DRAFT                            07124/07 07/24/07 Q #43 Q#43 Unit 44 is Unit      is at at 80%
80% power power with    all systems with all  systems in in auto auto when when the the 4A 4A S/G SIG pressure pressure transmitter associated transmitter    associated with with the the controlling controlling S/G S/G steam steam flow flow transmitter transmitter fails fails LOW.
LOW.
Which ONE Which      ONE of of the the following following describes describes thethe immediate immediate effect effect on on 4A:
4A:
1)
: 1)        S/G steam S/G  steam flow      signal to flow signal    to the  feed reg the feed      valve controller reg valve  controller 2)
: 2)        feed reg feed    reg valve valve 3)
: 3)        SIG level S/G  level A.
A.        1) steam
: 1)  steam flow flow signal signal decreases decreases
: 2)  feed
: 2) feed regreg valve valve opens.
opens.
SIG level increases.
: 3) S/G B.      1) steam flow signal decreases 1)
: 2) feed reg valve closes.
SIG level decreases.
: 3) S/G C.        1) steam flow signal increases
: 2) feed reg valve opens.
SIG level increases.
: 3) S/G D.        1) steam flow signal increases
: 2) feed reg valve closes.
: 3) S/C S/G level decreases.
85 85
 
DRAFT NRC DRAFT                              07/24/07 07/24/07 Q #43 Q#43 ANSWER:
ANSWER:          B B
KA:
KA:              059K1.03 059K1.03 Knowledge of Knowledge        the physical of the  physical connection connection and/or and/or cause-effect cause-effect relationships relationships between between the  main  feedwater  and  the SIGs.
the main feedwater and the S/Gs. 3.1/3.3 3.1/3.3 IOCFR55:
10CFR55:        41.b.4, 41.b.7
 
==Reference:==
5610-T-D-17, 561  O-T-0-17, Sheet 11 5610-T-D-18B, Sheet 1 5610-T-0-18B,Sheet1 SD-li, Page SO-11,  Page 32 Cog Level:      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 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 C.      Incorrect because for this failure the steam flow signal decreases, the feed reg valve closes and the S/G level decreases. Plausible because this response provides an accurate description of the effect of the pressure input failing high.
high.
D.
O.      Incorrect because for this failure the steam flow signal decreases, the feed reg valve closes and the S/G level decreases. Plausible because the feed reg valve will close and the S/G level will decrease.
decrease.
86 86
 
NRC DRAFT NRC      DRAFT                                07124/07 07/24/07 Q#44 Q#44 Unit 44 is Unit    is operating operating atat 40%
40% power power with with all all systems systems inin automatic automatic operation.
operation.
**  The sensing The    sensing line line for for first first stage stage pressure pressure transmitter, transmitter, PT-4-446, PT-4-446, which which is is selected selected for  control on for control  on VPA, VPA, shears shears offoff at at the the connection connection toto the the pressure pressure transmitter.
transmitter.
**  Several minutes Several    minutes later, later, the  BOP selects the BOP      selects PT-4-447 PT-4-447 as as the the controlling controlling channel channel as as directed by directed    by the the procedure.
procedure.
Which ONE ONE ofof the following following describes describes the response response ofof S/G SIG levels levels assuming assuming they they left in are left  in automatic automatic throughout the entire  entire evolution?
evolution?
SIG levels will:
S/G A.      remain stable at 60%.
remain B.      lower from 60% and stabilize at 50% and then return to 60%.
c.
C.      lower from 60% and remain stable at 50%.
D.      lower from 60% continuously until PT-4-447 is selected and then rise to 50%
87 87
 
NRC DRAFT                            07/24/07 Q #44 Q#44 ANSWER:        B KA:            059A3.02 Ability to monitor automatic operation of the MFW, including programmed levels of SIG. 2.9/3.1 the S/G.
IOCFR55:
10CFR55:        41.b.4, 41.b.7 41.bA,41.b.7
 
==Reference:==
5610-T-D-17 561  0-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 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 PT-446 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 level control system will return level back to 60%.
New Question Response Analysis:
A.      Incorrect because S/G levels will lower from 60% and will stabilize stabIlize at 50%
and then return to 60% when PT  PT-4-447 447 is selected. Plausible because at 40% power the level program has just increased from 50% to 60%.
B. Correct per the reference.
C. Incorrect because S/G levels will lower from 60% and will stabilize at 50%
and then return to 60% when PT-4-447 is selected. Plausible because other SIG levels to rise continuously until a instrument failures will cause S/G                                    a turbine trip occurs.
D. Incorrect because S/C S/G levels will lower from 60% and will stabilize at 50%
and then return to 60% when PT-4-447 is selected. Plausible because other instrument failures will cause SIG S/G levels to lower continuously until aa reactor trip occurs.
88 88
 
NRC DRAFT NRC      DRAFT                                  07124/07 07/24/07 Q #45 Q#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 hand hand switch switch inin the the green-flagged green-flagged position.
position.
Which ONE Which  ONE of  of the the following following describes describes thethe consequences consequences of  of this this discovery?
discovery?
A.
A. An  AFW system An AFW      system auto-start auto-start signal signal hashas been been disabled.
disabled.
B.
B. A condensate condensate pump  pump auto-start auto-start signal has has been been disabled.
disabled.
C.
C. The    running SGFP The running        SGFP can  NOT trip can NOT          as aa result trip as    result of of bus  stripping.
bus stripping.
D. The turbine can  can NOT run back as a result of a SGFP trip.
89 89
 
DRAFT NRC DRAFT                                  07124/07 07/24/07 Q #45 Q#45 ANSWER:
ANSWER:      A A KA:
KA:            061 K4.02 061  K4.02 Knowledge of Knowledge        the AFW of the  AFW design design feature(
feature(s)  and/or interlock(
s) and/or  interlock(s) 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        level, blackout S/G level,  blackout or or SI.
SI. 4.5/4.6 4.5/4.6 IOCFR55:
10CFR55:        41.b.4, 41.b.7 41.bA,
 
==Reference:==
Sheet 15, Notes 1I and 5610-T-L1, Sheet                and 55 Cog Level:    11 Recall Recall New Question Response Analysis:
A. Correct per the reference 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 S/G feed pump trip signal from bus stripping is unaffected. Plausible because green flag indication implies to the AEW      AFW start logic that the SGFP has been manually stopped but it does not input to the bus stripping logic in the same manner.
D. Incorrect because the S/G feed pump trip signal into the turbine runback  run back logic is unaffected. Plausible because green flag indication implies to the AFW start logic that the SGFP has been manually stopped but it does not input to the turbine runback logic in the same manner.
90 90
 
NRC DRAFT NRC        DRAFT                              07124/07 07/24/07 Q #46 Q#46 Unit 33 isis at Unit          at 100%
100% power power with with all all systems systems inin normal normal alignment.
alignment.
The 3C The    30 main main steam steam line line non-return non-return check check valve valve body body ruptures    resulting inin aa large ruptures resulting          large Main    Steam Line Main Steam        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 ofof the the AFW AFW system?
system?
A.
A.        Only 3A Only    3A andand 3B3B AFW AFW pumps pumps startstart and and deliver deliver flow.
flow.
390 gpm 390    gpm total total AFW AFW flow flow will will be  delivered to be delivered  to all all S/Gs.
SIGs.
B.
B.        Only 3A Only    3A andand 3C3C AFW AFW pumps pumps startstart and and deliver deliver flow.
flow.
780  gpm    total  AFW    flow 780 gpm total AFW flow will be    will  be delivered delivered to to all all S/Gs.
S/Gs.
C.
C.        Only 3B Only    3B andand 3C 3C AFW AFW pumps pumps startstart and and deliver deliver flow.
flow.
390 gpm 390    gpm total total AFW flowflow will will be be delivered delivered to to all S/Gs.
SIG5.
D.
D.        All AFW pumps start and deliver flow.
780 gpm total AFW flow will be delivered to all S/Gs.
9191
 
NRC DRAFT DRAFT                            07/24/07 07/24/07 Q #46 Q#46 ANSWER:
ANSWER:        D D
KA:
KA:            061A3.O1 061A3.01 Ability to Ability to monitor monitor automatic automatic operation operation of of the the AFW, AFW, including:
including: AFW AFW startup startup and and flows. 4.2/4.2 flows. 4.2/4.2 IOCFR55:
10CFR55:        41.b.4, 41.b.7, 41.b.8 41.bA,
 
==Reference:==
5613-M-3072, Sheet 1I 5613-M-3072, 5610-T-L11 Sheet 5610-T-L    Sheet 11 11 5610-T-L11 Sheet 15 5610-T-L          15 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/C to blow dry because the 3C S/G                            30 MSIV will close. SI actuates due to Hi steamline flow with low Tavg/ low SG SC pressure when all 3 S/Gs feed the break at the 3C non-MSIV5. Both trains of AFW get a start return valve. This SI signal closes all 3 MSIVs.
signal due to SI. With all 3 S/Gs pressurized, all AFW pumps auto start and provide S/Cs. The AFW flow controllers are preset at 130 gpm each. 130 gpm X flow to all S/Gs.
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 30 3C S/G blows down and 30  3C S/G is providing steam supply to the 30    3C AFW pump.
B.      Incorrect because all AFW pumps start and deliver flow. Plausible if the operator recognizes 3A and 30  3C AFW pumps are in different trains. In    In that case 780 gpm total AFW flow will be delivered to all S/Cs.
S/Gs.
C.      Incorrect because all AFW pumps start and deliver flow. 780 gpm total AFW flow will be delivered to all S/Cs.
S/Gs. Plausible if the operator assumes the faulted 30 3C S/G blows down. 3A AFW pump would lose its      its steam supply and 390 gpm gpm total AFW flow would be delivered to all S/Cs.
S/Gs.
D.      Correct per the references 92 92
 
NRC DRAFT DRAFT                                  07/24/07 07/24/07 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 30 days days ifif its its Startup Startup Transformer Transformer becomes becomes inoperable.
inoperable.
Which ONE Which    ONE ofof the the following following describes describes the the basis basis for for allowing allowing continued continued operation operation at at less than less  than 30%    power?
30% power?
At 30% power:
A.      the two loop low flow / two RCPRCP breaker breaker open reactor reactor trip logic logic has has been been instated providing instated  providing additional reactor reactor protection protection in in the event of a LOOP.
LOOP.
B.      SIG pressure is greater than full power S/G pressure providing additional S/G 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.
D.      decay heat has been reduced, automatic feedwater control can be maintained and the RCPs continue to run.
93 93
 
NRC DRAFT                              07/24/07 07/24/07 Q #47 Q#47 ANSWER:
ANSWER:          DD KA:
KA:                062G2.2.25 062G2.2.25 As itit relates As      relates to  the AC to the  AC Electrical Electrical Distribution:
Distribution: Knowledge Knowledge of of the the bases bases in in Tech Tech Specs for Specs    for LCOs LCOs and and safety  limits. 2.5/3.7 safety limits. 2.5/3.7 10CFR55:
10CFR55:          41.b.1, 41.b.5, 41.b.7, 41.b.8 41.b.1,41.b.5,41.b.7,41.b.8
 
==Reference:==
0-ADM-536, Page 94; Section 3/4.8.1 Cog Level:        11 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 circulation conditions are avoided by staying at power and not shutting down. Plausible because at 30% power, the two loop low flow / two 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        S/C 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 circulation conditions are avoided by staying at power and not shutting down. Plausible because at 30% power, fewer components are loaded onto the 4KV Buses and Load Centers.
D.        Correct per the reference 94 94
 
NRC DRAFT NRC      DRAFT                              07/24/07 07/24/07 Q #48 0#48 Both Units Both  Units are are at at 100%
100% power power with with normal normal system system alignments alignments except    for 40 except for  4D MCC MCC which isis out which          of service.
out of  service.
Subsequently the Subsequently      the feeder feeder breaker breaker to    3C MCC to 3C  MCC trips trips open, open, de-energizing de-energizing 3C  3C MCC.
MCC.
Which ONE Which    ONE ofof the the following following describes describes the  effect on the effect      the Vital on the  Vital DC DC electrical electrical system?
system?
A.
A.      3A DC 3A    DC Bus Bus can can only only be be expected expected to  maintain voltage to maintain    voltage to to shutdown shutdown loads loads above 120 above    120 volts for for four hours.
hours.
B.
B.      3A DC 3A    DC Bus Bus can can only only be  expected to be expected      maintain voltage to maintain    voltage to  shutdown loads to shutdown    loads above 105105 volts for two hours.
C. 3B DC Bus  Bus can only be expected to maintain voltage to shutdown loads above 120 volts for four hours.
D. 3B DC Bus can only be expected to maintain voltage to shutdown loads above 105 volts for two hours.
95 95
 
NRC DRAFT DRAFT                          07124/07 07/24/07 Q #48 Q#48 ANSWER:
ANSWER:        B B
KA:
KA:            063K1 .03 063K1.03 Knowledge of the physical Knowledge            physical connection and/or cause-effect relationships relationships between between DC Electrical the DC  Electrical Distribution and the battery charger and battery. 2.9/3.5 100FR55:
10CFR55:        41.b.4, 41.b.7, 41.b.8
 
==Reference:==
5610-T-E-I 592 Sheet 1I 5610-T-E-1592 SD-I 44, Page 9 SD-144, Cog Level:      2 Comprehension Comprehension Level 2 because the operator must recognize that 4D MCC is the power supply to the 3A2 battery charger and 3C MCC is the power supply to the 3A    3A11 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. Incorrect because the 3A DC Bus is the affected bus. Plausible because 120 120 volts is the approximate normal voltage for all DC buses.
D. Incorrect because the 3A DC Bus is the affected bus. Plausible because 3A DC Bus can only be expected to maintain voltage to shutdown shutdown loads above 105 volts for two hours.
105 96 96
 
NRC DRAFT NRC      DRAFT                              07124/07 07/24/07 Q #49 0#49 Unit 33 isis in Unit          in Mode Mode 33 when when the    input breakers the input  breakers to to vital vital DC DC buses buses 3D23 3D23 and and 3D23A 3D23A trip trip open deenergizing open  deenergizing the    the DCDC buses.
buses.
Which ONE Which      ONE of of the the following following describes describes thethe effect effect on  the Unit on the  Unit 33 EDG(s)?
EDG(s)?
A.
A.        3A EDG 3A    EDG has      lost control has lost    control and  field flashing and field  flashing power.
power.
3A3A EDGEDG does does NOT NOT have have black black start start capability.
capability.
B.
B.        3B EDG 3B    EDG hashas lost lost control control and and field flashing power.
power.
3B    EDG    does    NOT  have  black  start 3B EDG does NOT have black start capability. capability.
C.      3A EDG has lost control and field flashing power.
3A EDG is    is still black start capable.
D.      3B EDG has lost control and field flashing power.
3B EDG is still black start capable.
97 97
 
DRAFT NRC DRAFT                              07/24/07 07/24/07 Q #49 Q#49 ANSWER:
ANSWER:      8B KA:
KA:          064K2.03 064K2.03 EDGs - Knowledge EDGs  - Knowledge of of the the power power supplies supplies to to the the control control power.
power. 2.9/3.3 2.9/3.3 10CFR55:
10CFR55:      41.b.4, 41.b.7, 41.b.8 41.bA,
 
==Reference:==
3-ONOP-003.5, Step 3-0NOP-003.5,      Step 3.5 &
                                        & Attachment 3, 8kr Bkr 3D23A-28 Cog Level:
Level:  11 Recall Recall New Question Response Analysis:
A. Incorrect because 38  3B EDG has lost control and field flashing power.
Plausible because 3A EDG does not have black start capability.
B.
: 8. Correct per the reference C. Incorrect because 38  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 38  3B EDG does not have black start capability. Plausible because 3B38 EDG has lost control and field flashing power.
98 98
 
NRC DRAFT                                    07/24/07 07/24/07 Q #50 0#50 Operators are Operators  are performing performing the the monthly monthly test test run  of the run of  the 3A 3A EDG EDG using using 3-0SP-023.1 3-OSP-023.1,,
Diesel Generator "Diesel  Generator Operability Operability Test."
Test.
BOP is attempting to verify 3A EDG The BOP                                EDG isis in in LAG.
LAG.
He momentarily He  momentarily positions positions the diesel diesel generator generator voltage regulator regulator in 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?
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.
99 99
 
NRC DRAFT                            07/24/07 07124/07 Q #50 Q#50 ANSWER:        A KA:            064G2.1.23 As it relates to the EDG, ability to perform specific system and integrated plant procedures during all modes of plant operation. 3.9/4.0 IOCFR55:
10CFR55:        41.b.4, 41b.7 41.bA,41.b.7
 
==Reference:==
3-OSP-023.1, Step 7.1.2.29.k 3-0SP-023.1, Cog Level:      1I 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.
100 100
 
NRC DRAFT NRC                                    07/24/07 07/24/07 Q  #51 Q #51 Unit 33 is Unit      is at at 100%
100% power power with with all all systems systems in  normal alignment in normal  alignment wherJ when the the following following occur; occur;
**  Annunciator H Annunciator    H 1/6, 1/6, PRMS PRMS CHANNEL CHANNEL FAILURE, FAILURE, alarms.
alarms.
**  Steam Generator Steam      Generator Liquid Liquid Sample Sample Monitor, Monitor, R3-19, R3-19, fail lamp lamp on on the the PRMS PRMS drawer drawer is illuminated is  illuminated
**  R3-19 display and recorder reading are failed LOW
* R3-19 warning and high alarm lamps are off.
Which ONE of the following describes the plant  plant response and the correct initial initial response?
operator response?
A.        S/G blowdown does NOT automatically isolate.
Manually secure Blowdown.
B.        S/G blowdown does NOT automatically isolate.
Maintain blowdown in operation but 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 tank to canal level control valve, LCV-3-6265B are closed.
D.        S/G blowdown has automatically isolated.
Verify S/G blowdown isolation valves, MOV-6275 A, B, & C and S/G liquid MOV-1 425/1 426/1 427 are closed.
sample valves MOV-1425/1426/1427 101 101
 
NRC DRAFTDRAFT                            07/24/07 07/24/07
  #51 Q #51 Q
ANSWER:
ANSWER:          AA KA:
KA:              073A2.02 073A2.02 to (a)
Ability to      predict the (a) predict the impacts impacts ofof the the following following malfunctions malfunctions oror operations operations on on the the PRMS      and  (b)  based  on  those  predictions,  use PRMS and (b) based on those predictions, use procedures  procedures toto correct, correct, control, control, oror mitigate the mitigate  the consequences consequences of      those malfunctions of those  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.10,  41 .b.1 1, 41.b.12, 41 .b.12, 41.b.13 41 .b.13
 
==Reference:==
 
==Reference:==
3-ONOP-071 .2, Step 3 RNO 3-0NOP-071.2, 3-ARP-097.CR, H1/6, Step 2f.
Cog Level:      1I Recall New Question Response Analysis:
A.      Correct per the references B.      Incorrect because blowdown needs to be manually secured. Plausible because blowdown is still in service and operator may think that with it aligned to the condenser (recent plant modification does not allow flow to condenser) continued operation is acceptable.
C.      Incorrect because S/G  SIG blowdown has not automatically isolated. Plausible because verifying the blowdown flow control valves are closed is an expected response if blowdown automatically isolates due to high radiation as stated on the meter.
D.      Incorrect because S/G blowdown has not automatically isolated. Plausible because verifying the blowdown flow control valves are closed is an expected response if blowdown automatically isolates due to Phase A.
102 102
 
NRC DRAFT NRC      DRAFT                              07/24/07 07/24/07 Q#52 Q#52 Unit 44 operators Unit    operators are are responding responding to      loss of to aa loss      Intake Cooling of Intake  Cooling Water Water (ICW).
(ICW).
Which ONE Which    ONE of of the  following identifies the following  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  hot air  temperature increases air temperature    increases to:to:          80&deg;C B.
B.      Turbine bearing Turbine    bearing temperature temperature increases increases to: to:    160&deg;F C.
C.        CCW temperature CCW    temperature increases increases to:
to:                  130&deg;F D.
D.      TPCW temperature increases increases to:                  105&deg;F 103 103
 
NRC DRAFT                                07/24/07 07124/07 Q #52 Q#52 ANSWER:        C KA:            076A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Service Water controls including reactor and turbine building closed cooling water temperatures. 2.6/2.6 10CFR55:        41.b.4, 41.b.5, 41.b.8 41.bA,
 
==Reference:==
4-ONOP-019 FO 4-0NOP-019    ED Page Cog Level:      I Recall 1
New Question Response Analysis:
A.      Incorrect because reactor trip is not required until exciter air temperatures increase beyond 90&deg;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&deg;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&deg;F. Plausible because TPCW temperatures should increase during this event.
104
 
NRC DRAFT NRC      DRAFT                                07124/07 07/24/07 Q #53 0#53 Unit 33 operators Unit    operators are  are responding responding to to decreasing decreasing Instrument Instrument AirAir (IA)
(IA) Pressure.
Pressure.
Which ONE Which    ONE of  of the the following following describes describes the the use use of    Service Air of Service  Air as as backup backup to to the the IA IA System?
System?
Service Air Service      Air valves valves may may be    opened:
be opened:
A.
A.      regardless of regardless          IA pressure of IA  pressure but  only after but only after all all available available instrument instrument air air compressors have    have been been started.
started.
B.
B.      ifif IA IA pressure pressure drops drops below below 95 95 psig psig regardless regardless of  of the the number number of  of available available instrument air compressors started.
c.
C.      ifif IA IA pressure pressure drops below below 95 psig psig and after after all available instrument instrument air compressors have been started.
D.      as backup to IA without restrictions associated with IA pressure or starting of available IA compressors.
105 105
 
NRC DRAFT                              07/24/07 07/24/07 Q #53 Q#53 ANSWER:
ANSWER:        CC KA:
KA:            078K1 .02 078K1.02 Knowledge of the physical connection and/or cause-effect Knowledge                                        causeeffect relationships relationships between between Instrument air and the the Instrument          the service air. 2.7/2.8 IOCFR55:
10CFR55:        41.b.4, 41.b.10 41.b.4,41.b.10
 
==Reference:==
O-ONOP-013, Steps 3 and 4 Cog Level:    1I Recall New Question Response Analysis:
A.      Incorrect because service air valves may be opened only if IA pressure drops below 95 psig and after any available instrument air compressors have been 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 after any available instrument air compressors have been started. Plausible because service air valves may be opened if IA pressure drops below 95 psig.
C.      Correct per the references.
D.      Incorrect because service air valves may be opened only if IA pressure drops below 95 psig and after any available instrument air compressors have been started. Plausible because service air valves are opened as backup to instrument air.
106 106
 
NRC NRC DRAFT                                  07/24/07 07/24/07 Q #54 0#54 The plant The  plant was was operating operating at at 100%
100% power power when:
when:
**  A small A  small break break LOCA LOCA has has occurred.
occurred.
**  SI SI  was  manually  actuated due to decreasing manually actuated due      decreasing pressurizer pressurizer level.
level.
**  Phase A Phase      was NOT A was  NOT manually manually actuated actuated following following the the manual manual SI SI actuation.
actuation.
**  Containment pressure Containment    pressure has has risen risen to 17 17 psig.
psig.
* The RCS is is saturated.
* Two ECCs and 3 ECFs are operating.
performing EOP-E-O, While performing    EOP-E-0, containment isolation signals were reset as directed by .
All Attachment 3 actions were completed before transitioning from EOP-E-O.EOP-E-0.
After the transition to EOP-E-1, the LOCA break size increased and containment pressure increased to 24 psig.
Based upon the above conditions which ONE of the following describes the status of the containment isolation signals?
A.      Only Phase A containment isolation has occurred and has been reset.
B.      Only Phase B containment isolation has occurred and has been reset.
C.      Both Phase A and Phase B    B containment isolations have automatically actuated but neither Phase A or Phase B    B containment isolations have been reset.
D.      Both Phase A and Phase B    B containment isolations have automatically actuated and only Phase A has been reset.
107 107
 
NRC DRAFT                              07/24/07 07/24/07 Q #54 Q#54 ANSWER:
ANSWER:        D D
KA:
KA:            103K4.06 103K4.06 Knowledge of the Ctmt Knowledge            Ctmt design feature(s) and/or interlock(s) which provide for isolation system 3.1/3.7 containment isolation IOCFR55:
10CFR55:        41.b.7, 41.b.9 41.b.7,41.b.9
 
==Reference:==
5610-T-L11 Sheet 11 5610-T-L 3-EOP-E-0, Attachment 3, Step 12 Cog Level:      3 Analysis Level 3 because the operator must recognize that a manual SI does not actuate Phase A. He then must analyze the plant condition to determine that an automatic SI has occurred and that this will actuate a Phase A. He then must remember that E-0 attachment 3 resets both SI and Phase A & B if actuated (Phase B was not the E-O at the time of attachment 3). If containment pressure increases above 20 psig, a Phase B isolation signal will still be generated even with the Phase A reset.
New Question Response Analysis:
A.      Incorrect because the pressure increasing above 20 psig 9 will cause aa Phase psi B even after the SI and other actuation signals were reset in E-O.
B                                                              E-0. Plausible because the Phase A signal was reset in attachment 3.
B.      Incorrect because the plant conditions would result in an automatic SI signal even after the manual SI was actuated. This would result in aa Phase A signal as well. Plausible because the attch 33 does reset Phase BB if it had actuated at that time.
C.
C.      Incorrect Incorrect because both phase phase A and BB have have actuated. Plausible because because the operator could assume that another signal above 20 psig would actuate Phase A again therefore it would not be reset.
D.
D.      Correct per the reference Correct 108 108
 
NRC DRAFT NRC      DRAFT                              07/24/07 07/24/07 Q#55 0#55 AA S/G SIC tube tube rupture rupture occurred occurred on on Unit Unit 3.
3.
All safety All  safety systems systems functioned functioned as  as designed designed including including Phase Phase AA Containment Containment Isolation.
Isolation.
Which ONE Which    ONE ofof the the following following describes describes an an effect effect of of Phase Phase AA on on the the containment containment and and actions operators actions    operators will will take take to  respond to to respond    to the the Phase Phase AA signal?
signal?
A.
A.        Instrument Air Instrument    Air to to Containment Containment has  has been been isolated.
isolated.
Operators will Operators    will reset reset Phase Phase AA when when directed directed by by 3-EOP-E-O,    Attachment 3, 3-EOP-E-O, Attachment        3, Prompt Action "Prompt      Action Verifications".
Verifications.
B.
B.      CVCS letdown CVCS    letdown from containment containment has has been been isolated.
isolated.
Operators will reset Operators          reset Phase Phase A  A when directed directed by by 3-EOP-E-O, 3-EOP-E-O, Attachment Attachment 3, Prompt "Prompt      Action  Verifications .
Verifications".
C.      CCW valves to the RCPs in containment have been closed.
Operators will reset Phase A after initiating a controlled cooldown while performing 3-EOP-E-3.
D.      Normal Containment Coolers have been tripped.
Operators will reset Phase A after initiating a controlled cooldown while 3.-EOP-E-3.
performing 3-EOP-E-3.
109 109
 
NRC DRAFT                              07/24/07 Q #55 Q#55 ANSWER:        B KA:            103A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the Ctmt; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Phase A &      &B Isolation. 3.5/3.8 IOCFR55:
10CFR55:        41.b.7
 
==Reference:==
3-EOP-E-O, Attachment 3, Step 13 3-EOP-E-3, Steps 13 and 19 5613-M-3047, Sheet I 5613-M-3047,Sheet1 Cog Level:      1 Recall 1
New Question Response Analysis:
A.      Incorrect because Instrument Air has not been isolated. Plausible because operators will reset Phase A when directed by 3-EOP-E-O, Attachment 3.
B.      Correct per the references. Letdown isolates and operators will reset Phase A when directed by 3-EOP-E-O, Attachment 3 C.      Incorrect because CCW valves to the RCPs in containment have not been closed and operators will reset Phase A when directed by 3-EOP-E-O, Attachment 3. Plausible because CCW valves are closed upon Phase Band    B and E-3 does contain a step to reset Phase A.
D.      Incorrect because operators will reset Phase A when directed by 3-EOP-E-O, Attachment 3. Plausible because Normal Containment Coolers have been tripped 110 110
 
NRC DRAFT                          07/24/07 Q #56 0#56 Unit 4 is at 100% power at the beginning of core life with:
* D-230.
Control Rods are at 0-230.
* Rod control is in automatic Control Rod H-8 drops into the core:
core
* All automatic control systems responded as designed
* Tavg stabilizes rF7&deg;F below Tref.
Which ONE of the following describes the effect of this event on the CVCS system after RCS parameters have stabilized?
A.      Low Pressure Letdown Control valve, PCV-3-145, is throttled closed resulting in lower VCT level B.      Low Pressure Letdown Control valve, PCV-3-145, is throttled open resulting in higher VCT level.
C.      The CVCS demineralizers have absorbed boron resulting in a positive reactivity insertion.
D.
O.      The CVCS demineralizers have released boron resulting in a negative reactivity insertion.
III 111
 
NRC DRAFT NRC      DRAFT                            07/24/07 07/24/07 Q #56 Q#56 ANSWER:
ANSWER:          CC KA:
KA:              001 K3.01 001  K3.01 Knowledge of Knowledge          the effect of the effect that that aa loss loss or or malfunction malfunction of of the the CROS CRDS will will have have onon the the CVCS. 2.9/3.0 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              10 Cog Level:        2 Comprehension Level 2 because the operator will have to analyze that the change in Tavg will result in lowering 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 responds to letdown header pressure downstream of the letdown orifices. While RCS pressure and letdown header pressure may temporarily respond to this RCS temperature change
      . the control systems will soon restore these pressures to their normal values.
Plausible because if PCV-3-145 throttled closed, it would result in lower VCT level.
B.      Incorrect because PCV-145 responds to letdown header pressure downstream of the letdown orifices. While RCS pressure and letdown header pressure may temporarily respond to this RCS temperature change the control systems will soon restore these pressures to their normal values.
Plausible because if PCV-3-1 PCV-3-145  45 throttled open, it would result in higher VCT level.
C.      Correct per the reference D.
O.      Incorrect Incorrect because the CVCS demineralizers will absorb more boron resulting in aa positive reactivity insertion. Plausible because ifif the CVCS demineralizers released boron itit would result in resulting in aa negative reactivity insertion.
insertion.
112 112
 
NRC DRAFT NRC    DRAFT                              07/24/07 07/24/07 Q #57 0#57 Unit 44 reactor Unit    reactor is is at at 100%
100% power power when when 4A4A RCP RCP rotor rotor seizes.
seizes. The The 4A 4A RCP RCP stops stops rotating instantly.
rotating  instantly.
Which ONEONE ofof the the following following describes describes the  initial effect the initial  effect of of this this event event on on the the Reactor Reactor Coolant  System?
Coolant System?
A.
A.      Pressurizer level Pressurizer    level and pressure will decrease.
DNBR will decrease and Clad Temperature Limits will NOT DNBR                                                          NOT be exceeded.
Fuel rod failure will not occur.
B.      Pressurizer level and pressure will decrease.
The DNBR will decrease and Clad Temperature Limits will be exceeded.
Fuel rod failure may occur.
C.      Pressurizer level and pressure will increase.
DNBR will decrease and Clad Temperature Limits will be exceeded.
Fuel rod failure may occur.
D.      Pressurizer level and pressure will increase.
DNBR will decrease and Clad Temperature Limits will NOT be exceeded.
Fuel rod failure will NOT occur.
113 113
 
NRC DRAFT                            07124/07 07/24/07 Q #57 Q#57 ANSWER:
ANSWER:        C C
KA:
KA:            002K6.02 002K6.02 Knowledge of Knowledge        the effect of the 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 IOCFR55:
10CFR55:                          41.b.14 41.b.2, 41.b.3, 41.b.14
 
==Reference:==
14.1.9 FSAR Section 14.1.9 Cog Level:    2 Comprehension Level 2 because the operator must relate the type of RCP failure to the effects on the RCS parameters. He then must analyze how the changing parameters relate to DNBR and determine that even though RCS pressure is increasing, the reduction in core flow causes DNB to occur and then understand the affect of DNB on the fuel rods.
New Question Response Analysis:
A.      Incorrect because pressurizer level and pressure will increase. Plausible because Total core cooling flow will decrease and the DNB Ratio will decrease and core damage will occur.
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 D.      Incorrect because DNB limits will be exceeded and core damage will occur.
114 114
 
NRC    DRAFT NRC DRAFT                                      07/24/07 07/24/07 Q #58 Q#58 Operators are Operators    are performing performing aa startup startup on on Unit Unit 33 and and power power isis 5%5% with with all all pressurizer pressurizer controls  in automatic controls in  automatic whenwhen the the controlling controlling pressurizer pressurizer levellevel 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 ofof this this failure  assuming NO failure assuming      NO operator action?
operator    action?
Pressurizer level Pressurizer    level will will continuously:
continuously:
A.      decrease.
decrease.
Letdown isolation Letdown      isolation will occur occur pressurizer pressurizer level level reaches reaches setpoint.
B.      decrease.
The reactor will trip on low pressurizer pressure when setpoint is reached.
c.
C.      increase.
The reactor will trip on high pressurizer level when setpoint is reached.
D.      increase.
Pressurizer PORV(s) will open when setpoint is reached.
115 115
 
NRC DRAFT NRC    DRAFT                            07/24/07 07/24/07 Q#58 Q#58 ANSWER:
ANSWER:          0D KA:
KA:              OIIA1.O1 011A1.01 to predict Ability to          and/or monitor predict and/or  monitor changes changes inin parameters parameters (to (to prevent prevent exceeding exceeding design limits) design  limits) associated associated with with operating operating the the PRZ PRZ LCS LCS controls controls including including PRZ PRZ level level and  pressure.
and pressure. 3.5/3.6 100FR55:
10CFR55:        41.b.3, 41.b.5
 
==Reference:==
5610-T-D -15 15 Sheet 1I 5610-T-D-16B Sheet 5610-T-D-16B    Sheet 11 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. 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 L      T-459A failure LT-459A causes letdown isolation. This combination results in rising pressurizer 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 will open at 2335 psig.
New Question Response Analysis:
A.      Incorrect because pressurizer level will continuously increase. Plausible because pressurizer level would decrease if L    T-459A failed high instead of LT-459A low and letdown isolation does normally occur at 14%.
B.      Incorrect because pressurizer level will continuously increase. Plausible because pressurizer level would decrease if L    T-459A failed high instead of LT-459A low and .the the reactor would normally trip on low pressurizer pressure when the pressurizer empties.
C.      Incorrect because the reactor will not trip on high pressurizer level at this power level. Plausible because pressurizer level will continuously increase.
increase.
D.      Correct per the references 116 116
 
NRC DRAFT NRC      DRAFT                              07124/07 07/24/07 Q #59 0#59 Operators are Operators      performing aa plant are performing        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  following describes the following    describes thethe direct direct effect effect of of depressing depressing the the Source Range Less "Source Range      Less than than P-6    Push to P-6 Push    to Reinstate" Reinstate pushbutton?
pushbutton?
The NIS source The NIS  source ranges ranges will:
will:
A. reinstate causing reinstate    causing aa SR SR Hi    Flux reactor Hi Flux  reactor trip.
trip.
B. reinstate but a SR Hi Flux reactor trip will NOT occur.
c.
C. NOT reinstate and a SR Hi Flux reactor trip will NOT occur.
D. NOT reinstate until power is reduced below 10% when the SRs will automatically trip the reactor.
117 117
 
NRC DRAFT NRC    DRAFT                              07/24/07 07/24/07 Q#59 Q#59 ANSWER:
ANSWER:        CC KA:
KA:              015A4.03 015A4.03 Ability to Ability  to manually manually operate operate and/or and/or monitor monitor in in the the control control room:
room: trip trip bypasses.
bypasses.
3.8/3.9 3.8/3.9 10CFR55:
10CFR55:        41.b.7 41.b.7
 
==Reference:==
 
==Reference:==
5610-T-L1 5610-T        Sheet 16
                        -L 1 Sheet 16 Cog Level:
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 D.
D.      Incorrect because the source source ranges will notnot automatically reinstate and trip the reactor when when power drops drops below 10%.
10%. Plausible Plausible because the SRs will not not reinstate  immediately  but but will reinstate (without trip) when power subsequently drops drops below below P-6.
P-6.
118 118
 
NRC DRAFT NRC      DRAFT                                07/24/07 07/24/07 Q #60 Q#60 Unit 33 core Unit    core off-load off-load isis in in progress progress when when the the refueling refueling SROSRO inside inside containment containment reports aa spent reports      spent fuel    element has fuel element    has dropped dropped andand aa large large amount amount ofof gas gas bubbles bubbles areare originating  from    the  damaged originating from the damaged element. element.
Which ONE Which    ONE ofof the the following following describes describes anan expected expected plant    response and plant response    and the the required operator required    operator response?
response?
A.
A.        Only Containment Only  Containment Ventilation Ventilation Isolation Isolation should should automatically automatically occur.
occur.
Manually    initiate  Control Manually initiate Control Room  Room    Ventilation  Isolation Isolation and verify the isolation isolation alignments as alignments        directed by as directed    by 3-0NOP-033.3, 3-ONOP-033.3, "Accidents Accidents Involving Involving NewNew oror Spent FueL" Spent  Fuel.
B.            Control Room Only Control      Room Ventilation Isolation should automatically occur.
Manually initiate Containment Ventilation Isolation 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 automatically occur.
Manually initiate both and verify the isolation alignments as directed by 3-ONOP-033.3, "Accidents ONOP-033.3,        Accidents Involving New or Spent FueL"    Fuel.
D.      Both Containment and Control Room Ventilation Isolation should automatically occur.
Verify the isolation alignments as directed by 3-0NOP-033.3, 3-ONOP-033.3, "Accidents Accidents Involving New or Spent FueL"  Fuel.                                          .
119 119
 
NRC DRAFT                              07/24/07 07/24/07 Q #60 Q#60 ANSWER:
ANSWER:          0D KA:
KA:              034A2.01 034A2.01 Ability to Ability to (a)  predict the (a) predict  the impacts impacts of of the the following following malfunctions malfunctions or or operations operations on on the the fuel handling handling system; system; andand (b)
(b) based based on on those those predictions, predictions, use use procedures procedures to  to correct, control, correct,  control, or or mitigate mitigate the the consequences consequences of  of those malfunctions malfunctions or or operations:
operations:
dropped fuel element.
dropped          element. 3.6/4.4 3.6/4.4 IOCFR55:
10CFR55:        41.b.9, 41.b.10, 41.b.11, 41.b.12
 
==Reference:==
 
==Reference:==
561 0-T-L11 Sheet 11 5610-T-L            11 3-ONOP-033.3, Steps 2.2, 4.3, 5.1.1.1 3-0NOP-033.3,                        5.1 .1.1 Cog Level: 2 Comprehension The SRO should recognize that bubbles from a dropped assembly are an indication the cladding has been breached. Along with the nitrogen gas bubbles will be gaseous fission products so that when detected by the containment gas monitor, 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 containment ventilation system isolate on high PRMS signals.
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 manually initiated.
B.      Incorrect because both containment and control room ventilation Isolation has automatically occurred. Plausible because control room ventilation Isolation should automatically occur and containment ventilation isolation can be manually initiated.
C.      Incorrect because both containment and control room ventilation Isolation has automatically occurred. Plausible because control room ventilation Isolation and containment ventilation isolation can be manually initiated.
D.      Correct perper the references 120 120
 
NRC DRAFT NRC    DRAFT                              07124/07 07/24/07 QQ#61
    #61 Unit          in Mode Unit 44 isis in  Mode 33 with with the  MSIVs closed the MSIVs  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 S/G rapidly rapidly depressurizes depressurizes.      .
Which ONE Which      ONE of  of the  following describes the following  describes the the response response of  of the safeguards system the safeguards    system to to this failure?
this  failure?
Safety injection Safety      injection will:
A.        NOT actuate with the MSIVs NOT                          MSIV5 closed.
B.
B.        actuate when Tavg decreases to 543&deg;F. 543&deg;F.
c.
C.        actuate when the 4A S/G    SIG pressure decreases to 485 psig.
D.        actuate when the 4A S/G    SIG pressure decreases to 900 psig.
121 121
 
NRC DRAFT NRC    DRAFT                          07/24/07 07/24/07 Q  #61 Q #61 ANSWER:
ANSWER:        C C
KA:
KA:            035K1.14 035K1.14 Knowledge of Knowledge        the physical of the  physical connection connection and/or and/or cause-effect cause-effect relationships relationships between between the  SIG  and  the  ESF.
the S/G and the ESF. 3.9/4.1 3.9/4.1 10CFR55:
10CFR55:        41.b.7, 41.b.8 41.b.7,41.b.8
 
==Reference:==
5610-T-L11 Sheet 19 5610-T-L 5610-T-D-18B 561  0-T-O-18B Sheet 1I Cog Level:      3 Analysis Level 3 because the operator must recognize that when a S/G 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 because the main steam lines would be depressurized. That's  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'sSIGs 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/C S/G pressure decreases to 485 psig. Plausible because 543&deg;543&deg;FF is an SI setpoint that when reached will make up part of SI logic.
C.      Correct per the references D.
O.      Incorrect because SI will actuate when the 4A S/G pressure decreases to 485 psig. Plausible because 900 psig would result in 100  100 psid at hot zero power that is an actuation signal if the MSIVs MSIVs were open.
open.
122 122
 
NRC DRAFT NRC        DRAFT                            07/24/07 07/24/07 Q #62 0#62 3-EOP-E-3, "Steam 3-EOP-E-3,  Steam Generator Generator Tube Tube Rupture,"
Rupture, directs directs operators operators to to use use the the Steam Steam Dump to Dump      Condenser system to Condenser    system to    initiate aa cooldown to initiate    cooldown atat maximum maximum rate rate prior  to RCS prior to  RCS depressurizat ion.
depressurization.
Which ONE Which  ONE of of the the following following describes describes how how the the Reactor Reactor Operator Operator will will accomplish accomplish this cooldown this cooldown using using the the Steam Steam Dump Dump to  to Condenser Condenser system?
system?
Place the
. Place  the Mode    Selector Switch Mode Selector      Switch in:
in:
A.              Bypass the AUTO. Bypass      the low low Tavg interlock.
interlock. Place Place the Hagan Hagan controller in  in MANUAL and MANUAL      and use use the the UP UP arrow arrow to to open the steam open the  steam dump    valves.
dump valves.
B. AUTO. Place the Hagan controller in AUTO and adjust the pot setting        setting to the desired setpoint to open the steam dump 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 AUTO and adjust the pot setting to the desired setpoint to open the steam dump valves.
123 123
 
NRC DRAFT                            07/24/07 07/24/07 Q #62 Q#62 ANSWER:
ANSWER:        CC KA:
KA:            041G2.I .28 041G2.1    .28 As it relates to the SO SD Sys: Knowledge of the purpose and function of major major system components and components    and controls.
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 19  19 SD-I 05 Page 17 SO-105          17 Cog Level:        Comprehension 2 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 SOTCSDTC 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 (manual-manual mode). The operator must also of the hagan process output (manual-manual 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.
Plausible because the Hagan controller will be placed in MANUAL and the UP arrow will be used to open the steam dump valves.
B.      Incorrect because the Mode Selector Switch will be placed in MANUAL and the Hagan controller will be place in MANUAL. Plausible because placing the Hagan controller in AUTO and adjusting the pot setting would open the steam dump valves if the Mode Selector Switch were placed in MANUAL.
MANUAL.
C.      Correct per the references D.
O.      Incorrect Incorrect because the Hagan Hagan controller will be place in be place in MANUAL.
MANUAL. Plausible Plausible because the Mode Mode Selector Switch        be placed Switch will be        in MANUAL placed in MANUAL 124 124
 
NRC DRAFT NRC      DRAFT                            07/24/07 07/24/07 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 ofof the the following following describes describes the the effect  of closing effect of 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 willwill decrease.
decrease.
The turbine will trip The                  trip when condenser condenser vacuum reaches reaches 25" 25 Hg.
Hg.
B.
B.        Condenser vacuum Condenser      vacuum willwill decrease.
decrease.
The turbine will trip when condenser vacuum reaches 20"          20 Hg.
C.        Main generator megawatts Main                megawatts will decrease.
The reactor will trip when the OP~T  OPAT setpoint is reached.
D.      Main generator megawatts will decrease.
The reactor will trip when the turbine trips due to high vibration.
125 125
 
NRC DRAFTDRAFT                        07124/07 07/24/07 Q #63 Q#63 ANSWER:
ANSWER:      BB KA:
KA:          055K3.O1 055K3.01 Knowledge of Knowledge  of the effect effect that aa loss loss or or malfunction malfunction of of the the CARS CARS will will have have onon the the main condenser.
main condenser. 2.5/2.7 2.5/2.7 IOCFR55:
10CFR55:    41.b.5, 41.b.7 41.b.5,41.b.7
 
==Reference:==
 
==Reference:==
5613-M-3014, Sheet 3 3-ONOP-014, Step 3.1, 5.5.2 3-0NOP-014, Cog Level:  1I fundamental knowledge New Question Response Analysis:
A. Incorrect because the turbine will trip when condenser vacuum reaches 20"      20 Hg. Plausible because condenser vacuum will decrease B. Correct per the references C. Incorrect because turbine efficiency will decrease if the operator assumes reactor power would have to increase to maintain the same output.
D. Incorrect because there is no high vibration trip on the turbine.
126 126
 
NRC DRAFT NRC      DRAFT                            07/24/07 07/24/07 Q #64 0#64 Unit 33 isis at Unit          at 75%    power when 75% power      when the the following following occurs; occurs;
**  annunciator D annunciator        D 5/3, 5/3, SGFP SGFP AA SUCTION SUCTION LO  LO PRESS, PRESS, alarms alarms
**  annunciator        D 7/4,  LP  HEATER annunciator D 7/4, LP HEATER BYPASS OPEN  BYPASS  OPEN alarms alarms
**  CV-3-201 1 indicates CV-3-2011          indicates open open
**  aa turbine turbine runback runback isis NOT NOT in in progress progress Which ONE Which      ONE of    the following of the  following correctly correctly describes describes the the first first operator operator response?
response?
A.
A.        Close CV-3-2011 Close    CV-3-201 1 ifif SGFP SGFP suction suction pressure pressure is is greater greater than 220 220 psig.
psig.
B.
B.        Reduce turbine load to restore SGFP suction pressure  pressure to greater than psig.
220 psig.
C.        Start th'e the standby Condensate Pump to restore SGFP suction pressure to greater than 220 psig.
D.      Stop the 3A SGFP to start the runback as it should have tripped when the SGFP A SUCTION LO PRESS annunciator actuated.
127 127
 
NRC DRAFT NRC    DRAFT                            07/24/07 07/24/07 Q #64 Q#64 ANSWER:
ANSWER:          CC KA:
KA:                056G2.4.50 056G2.4.50 As itit relates As      relates to to the  condensate system:
the condensate    system: Ability Ability to  verify system to verify system alarm alarm setpoints setpoints and and operate    controls  identified in the alarm  response manual.
operate cont.rols identified in the alarm response          manual. 3.3/3.3 3.3/3.3 IOCFR55:
10CFR55:          41.b.4 41.b.4
 
==Reference:==
 
==Reference:==
3-ARP-097.CR, D 3-ARP-097.CR,      D 7/4 7/4 Step Step 11 &
                                                    & 3.b.
3.b.
3-ARP097.CR, D 3-ARP-097.CR,      D 5/3 Step Step 2 && 3.a.
3.a.
Cog Level:        1I Recall New Question New Response Analysis:
A.        Incorrect because the ARP directs operators to start the standby Condensate Pump to restore SGFP suction pressure to >            > 220 psig.
CV-201 1 would help to restore SGFP suction Plausible because closing CV-2011 pressure.
B.        Incorrect because the ARP directs operators to start the standby Condensate Pump to restore SGFP suction pressure to > 220 psig.
Plausible because reducing turbine load would help to restore SGFP suction pressure.
C.        Correct per the references D.        Incorrect because the ARP directs operators to start the standby Condensate Pump to restore SGFP suction pressure to            to>
                                                                          > 220 psig.
Plausible because stopping the 3A SGFP would help to restore 3B SGFP suction pressure.
128 128
 
NRC DRAFT NRC    DRAFT                              07/24/07 07/24/07 Q #65 0#65 Chemistry has Chemistry    has reported reported that that the  concentration of the concentration  of oxygen oxygen in in the the in-service in-service gas gas decay decay tank isis 4.2%
tank            and the 4.2% and  the hydrogen hydrogen concentration concentration is is 4.8%.
4.8%.
Which ONE Which    ONE of of the  following describes the following  describes the  correct operator the correct  operator response?
response?
Stop  addition of Stop addition      waste gas of waste  gas to  the gas to the      decay tank gas decay  tank and and reduce reduce the:
the:
A.
A.        oxygen concentration oxygen  concentration to to << 4%
4% as as soon soon as as possible.
possible.
B.      hydrogen concentration to <<4%                    possible.
4% as soon as possible.
C.        oxygen concentration to << 4% within 48 hours.
D.        hydrogen concentration to <<4%  4% within 48 hours.
129 129
 
NRC DRAFT NRC    DRAFT                              07/24/07 07/24/07 Q#65 Q#65 ANSWER:
ANSWER:      A A KA:
KA:            071 K5.04 071  K5.04 Knowledge of Knowledge    of the the operational operational implications implications of of the the following following concept concept as as itit applies applies to to the  WGD  system:    relationship the WGD system: relationship of    of H2/02 H2/02 concentrations concentrations to  to flammability.
flammability. 2.5/3.1 2.5/3.1 10CFR55:
10CFR55:        41.b.10, 13 41.b.10,13
 
==Reference:==
 
==Reference:==
0-ONOP-061, NOTE 0-ONOP-061,      NOTE prior prior to to Step Step 55 Cog Level:
Cog  Level:  1I Recall Recall New Question New Response Analysis:
A. Correct per the reference.
B. Incorrect because ONOP-061 directs operators to reduce the oxygen concentration to <  < 4% as soon as possible. Plausible because with concentrations of both gases>
concentrations            gases > 4%, ONOP-061 directs operators to stop addition of waste gas to the gas decay tank.
C. Incorrect because ONOP-061 directs operators to reduce the oxygen concentration to << 4% as soon as possible. Plausible because with oxygen concentration > 2%, ONOP-061 directs operators to reduce the oxygen concentration>
concentration within 48 hours.
D. Incorrect because ONOP-061 directs operators to reduce the oxygen concentration to << 4% as soon as possible. Plausible because with concentration concentrations  s of both gases gases> > 4%, ONOP-061 directs operators to stop addition of waste gas to the gas decay tank.
130 130
 
NRC    DRAFT NRC DRAFT                            07/24/07 07/24/07 Q #66 0#66
**  Unit 33 isis at Unit        at 90%    power.
90% power.
**  Tavg      630&deg;F Tavg = 630&deg;F
**  RCS pressure RCS    pressure is  is 2235 2235 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  Mode 33 within in Mode    within 11 hour.
hour.
B.      Reduce Tavg to less than 625&deg;F within 15 Reduce                                          15 minutes.
C.
C.      Reduce power Reduce        power to less less than 75%
75% within 1515 minutes minutes D. Reduce RCS pressure pressure to less than 2235 psig within 5 minutes.
REFERENCE PROVIDED  PROVIDED 131 131
 
NRC DRAFT NRC      DRAFT                                07/24/07 07/24/07 Q #66 Q#66 ANSWER:
ANSWER:      AA KA:
KA:            G.2.1.11 G.2.1.11 Knowledge of Knowledge    of less  than one less than  one hour hour technical technical specification specification action action statements statements for for systems. 3.0/3.8 systems. 3.0/3.8 10CFR55:
10CFR55:      41.b.5 41.b.5
 
==Reference:==
 
==Reference:==
TS 2.1.1 TS    2.1.1 TS Figure TS    Figure 2.1-1 2.1-1 Provide as reference:
Provide      reference:        Tech Spec Figure Figure 2.1-1 Cog Level: 11 Recall New Question Response Analysis:
A. Correct per the reference.
B. Incorrect because the TS required response is to shutdown within 1                1 hour.
Plausible because reducing Tavg to less than 625&deg;F    625&deg; F would restore conditions to within the acceptable operating region and because there are other short term Tech Specs that require aa 15    15 minute response.
C. Incorrect because the TS required response is        is to shutdown shutdown within 11 hour.hour.
Plausible because reducing power to less than 75% would restore conditions to within the acceptable operating region and because there are other short term term Tech Tech Specs Specs that that require require aa 15 15 minute minute response.
response.
D.
D. Incorrect Incorrect because because the the TS TS required required response response isis to to shutdown shutdown within within 11 hour.
hour.
Plausible Plausible because because reducing reducing pressure pressure within 55 minutes minutes is is aa required action action ifif the the other other PTN PTN Safety Safety Limit Limit (press (press >2735
                                              >2735 psig) psig) isis violated.
violated.
132 132
 
NRC DRAFT NRC    DRAFT                              07124/07 07/24/07 Q #67 Q#67 Operators have Operators    have evacuated evacuated the    Control Room.
the Control  Room.
The Unit The  Unit 33 RORO isis performing performing Attachment Attachment 33 ofof 0-ONOP-1 0-ONOP-1 05,  05, "Control Control Room Room Evacuation and Evacuation"    and has    determined that has determined    that RCS RCS boration boration isis required.
required.
Which ONE Which    ONE of of the  following describes the following  describes the the correct correct orders orders the the RO RO should should give give the the SNPO to SNPO    to successfully successfully borate borate the the RCS?
RCS?
Locally open "Locally  open the:
the:
A.
A.      Emergency Boration 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 youyou to increase the 3C Charging pump    pump speed controller setpoint to setpoint    to 66 psig."
psig.
B. Emergency Boration Valve, MOV-3-350. After I start the 3B Charging pump, I will direct you to increase the 3B Charging pump speed controller setpoint psig.
to 12 psig."
C. Manual Boration Valve, 3-356. After II start the 3B Charging pump, II will direct you to increase the 3B Charging pump speed controller setpoint to 6 psig.
psig."
D. Manual 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."
133 133
 
NRC DRAFT NRC      DRAFT                                07/24/07 07/24/07 Q #67 Q#67 ANSWER:
ANSWER:        BB KA:
KA:    G.2.1.8 G.2.1.8 Conduct of Conduct    of Operations:
Operations: Ability Ability to  coordinate personnel to coordinate    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:
Level: 1I Recall Recall New Question Response Analysis:
A. Incorrect because the 3C Charging pump is the wrong pump (it will have no power) and the SNPO should increase the Charging pump speed controller setpoint to 12 psig. Plausible because MOV-350 is the correct valve to open and 6 psig is the initial charging pump controller setting.
B. Correct per the references C. Incorrect because valve 3-356 is the wrong valve and the SNPO should increase the Charging pump speed controller setpoint to 12            12 psig.. Plausible because 3-356 is aa manual emergency boration valve used for boration under different circumstance circumstances    s and 66 psig is the initial charging pump controller setting and 3B Charging pump is the correct pump.        pump.
D.
D. Incorrect Incorrect because valve 3-356 is      is the wrong valve and  and the 3C3C Charging pump  pump is is the  wrong  pump pump (it (it will have have no no power) Plausible Plausible because because 3-356 3-356 isis aa manual manual emergency emergency boration boration valve valve used used for boration boration under under different different circumstance circumstances  s and and because because 12  12 psig psig isis the the correct correct charging charging pump pump controller controller setting.
setting.
134 134
 
NRCDRAFT NRC        DRAFT                              07/24/07 07/24/07 Q #68 0#68 WhichONE Which    ONEof  ofthe thefollowing followingisisan anaccurate accuratecomparison comparisonofofthe theUnitUnit33SFPSFP radiolo gical monitoring radiological    monitoring system system totothe the Unit Unit44SFP SEP radiological radiological monitoring monitoring system?
system?
AAgaseous gaseous radioactive radioactive release releasefrom:
from:
A.
A.      both SFPs both    SEPs areare monitored monitored by  bytheir theirown own separate separate Unit Unit 33 and and Unit Unit 44 SFP SEP SPING    detecto  rs located  in  each  SEP SPING detectors located in each SFP vent duct. vent duct.
B.
B.      both SFPs both    SEPs areare monitored monitored by by aa common common SFPSEP SPING SPING located located inin the the SFP SEP comm    on  vent common vent duct. duct.
C.
C.      Unit 33 SFP Unit    SEP isis monitored monitored by by the the plant plant vent vent monitor monitor while while Unit Unit 44 SFP SFP isis monitored by monitored    by aa separate separate U4U4 SFP SEP SPING.
SPING.
D.
D.      Unit 44 SFP Unit    SFP is  monitored by is monitored        the plant by the  plant vent vent monitor monitor while while thethe Unit Unit 33 SFP SEP isis monito  red by  a separa  te  U3  SEP monitored by a separate U3 SFP SPING.. SPING 135 135
 
NRC DRAFT NRC      DRAFT                              07124/07 07/24/07 Q #68 Q#68 ANSWER:
ANSWER:        D D
KA:
KA:            G.2.2.4 G.2.2.4 Ability to Ability to explain explain the the variations variations in in control control board board layouts, layouts, systems, systems, instrumentation instrumentation and  procedural  actions between    units and procedural actions between units at    at aa facility. 2.8/3.0 2.8/3.0 100FR55:
10CFR55:        41.b.11
 
==Reference:==
SD-041 Page 20, SD-068 Page 33, 5614-M-3034, Sheet 1,  1, 5610-M-3060 Sheet 1,      1, 5613-M-3034 Sheet 1, 1, Cog Level: 11 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      SFP5 is monitored differently. Plausible because only unit 4 is vented to the plant S PING detector in its vent duct..
vent while unit 3 has a SPING C.      Incorrect because aa gaseous radioactive release from both SFP5    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..
D.      Correct per the references 136 136
 
NRCDRAFT NRC      DRAFT                                07/24/07 07/24/07 Q #69 0#69 WhichONE Which    ONEofofthe  thefollowing followingtemporary temporaryalterations alterationswouldwould require requireaa"prior priorPNSC PNSC approv  ed  Tempo approved Temporary      rarySystem SystemAlteration Alteration (TSA),,?
(TSA)?
A.
A.      lifting of lifting    ofaa wire wiretoto perform perform aa troubleshooting troubleshooting procedure procedure on on aa circuit circuit associated with associated        with turbine turbine runback runback logic.
logic.
B.
B.      addition of addition      ofaa jumper jumper inin the the start start circuit circuit of ofthe the 3A 3A HHSI HHSI Pump Pump which which will will remain      QOS      on an remain OOS on an ECO while  ECO    while the the jumper jumper isis inin place.
place.
C.
C.      addition of addition      of aa temporary temporary power power supply supply forfor aa Phase Phase AA Containment Containment Isolation Isolation actuati actuation  on circuit circuit until until aa permanent permanent powerpower supply supply can can 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    refueli following refueling. ng.
137 137
 
NRCDRAFT NRC        DRAFT                              07124/07 07/24/07 Q #69 Q#69 ANSWER:
ANSWER:        CC KA:
KA:            G.2.2.11 G.2.2.11 Knowledge Knowledge of ofthe the process process for for controlling 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:    1I Recall Recall New Question New  Question Response Analysis:
Response    Analysis:
A.
A. Incorrect because Incorrect  because lifting of a wire to perform troubleshooting troubleshooting on a circuit isis specifically excluded from requiring a TSA by ADM-503      ADM5O3 (Ref. Step 4.1.2.5).
4.1.2.5).
because lifting a wire is a temporary alteration.
Plausible because B.
B.                because addition of a jumper in a circuit of a component which will Incorrect because                                                                      will remain OOS on an ECO while the jumper is in place is specifically excluded from requiring a TSA by  byADM-503 ADM-503 (Ref. Step 4.1.5.9). Plausible because adding aa jumper to aa circuit is aa temporary alteration.
C. Correct per the references.
D.
D. Incorrect Incorrect becaus becausee installation installation of of drain drain rigs connected to floor drains drains isis specifically  excluded specifically excluded from requiring aa TSA    TSA by by ADM-503 ADM-503 (Ref.
(Ref. Step Step 4.1.2.1).
4.1.2.1 ).
Plausible Plausible becaus becausee installing installing aa drain drain rig rig is is aa temporary temporary alteration.
alteration.
138 138
 
NRC DRAFT NRC      DRAFT                        07/24/07 07/24/07 Q #70 Q#70 Refueling core Refueling  core off-load off-load isis being being conducted conducted onon Unit Unit 3.
3.
The following The  following off-load off-load data data has      been recorded:
has been    recorded:
Time          Cumulative ## of Cumulative        of fuel fuel elements elements off-loaded off-loaded      SFP SEP temperature temperature 0800 0800                                    o0                          138&deg;F 138&deg;F 0900 0900                                    33                          138&deg;F 138&deg;F 1000 1000                                    99                          139&deg;F 139&deg;F 1100 1100                                      15 15                        139&deg;F 139&deg;F 1200 1200                                      22 22                          141&deg;F 141&deg;F 1300 1300                                      30                        142&deg;F 142&deg;F 1400 1400                                      37 37                          14rF 147&deg;F 1500                                    47                          151&deg;F 151&deg;F Which ONE of the following identifies the first time at which the core off-load should have been stopped as required by 3-0P-040.2, 3-OP-040.2, "Refueling Refueling Core Shuffle"?
Shuffle?
A.      1200 B. 1300 C. 1400 D. 1500 1500 139 139
 
NRC    DRAFT NRC DRAFT                              07124/07 07/24/07 Q #70 Q#70 ANSWER:
ANSWER:      AA KA:
KA:            G.2.2.28 G.2.2.28 Knowledge of Knowledge  of new new and and spent spent fuel 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.11, 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:  11 recall recall New Question New  Question Response Analysis:
A. Correct because Correct    because the SFP SEP temperature increased to 141&deg;F 141&deg;E at 1200. This exceeds the OP-040.2 limit of 140&deg;F. 140&deg;E.
B. Incorrect because the off-load should have been stopped at 1200. Plausible because the cumulative off-load limit and the instantaneous instantaneous off-load limits have been reached at 1300.
C. Incorrect because the off-load should have been stopped at 1200. Plausible because the cumulative off-load limit has been exceeded at 1400.
D. Incorrect because the off-load should have been stopped at 1200. 1200. Plausible because the instantaneou instantaneous  s off-load limit has been exceeded at 1500.
1500.
140 140
 
NRC DRAFT NRC        DRAFT                                    07/24/07 07/24/07
    #71 QQ #71 AA plant plant worker worker isis assigned assigned toto work work inin aa radiation radiation field field under under the the following following conditions:
conditions:
** TheThe job job isis located located 22 meters meters from from aa 1"    valve that 1 valve  that isis reading reading 60 60 mr/hr mr/hr atat 11 meter meter distance.
distance.
** Additionally, Additionally, the the job job location location general general area area dose dose rate rate from from other other radiation radiation sources sources is  equal is equal to to the the 10CFR20 IOCFR2O minimum minimum dose  dose rate rate that that defines defines aa Radiation Radiation Area.
Area.
**  The operator's The    operators cumulative cumulative documented documented dose  dose for for the the year year is is 940 940 mrem.
mrem.
**  An extension An    extension of  of the the exposure exposure guidelines guidelines has has NOT NOT been been granted.
granted.
Determine the Determine      the number number of    hours he of hours  he may may work work without without receiving receiving aa dose dose extension?
extension?
A.        1lhr hr B.      22hrs hrs C.      33hrs hrs D.      4hrs 4  hrs 141 141
 
NRC DRAFT NRC      DRAFT                                  07124/07 07/24/07 Q#71 Q#71 ANSWER:
ANSWER:        C C KA:
KA:              G.2.3.1 G.2.3.1 Knowledge of Knowledge    of 10CFR20 10CFR2O andand related related facility facility radiation radiation control    requirements. 2.6/3.0 control requirements.      2.6/3.0 10CFR55:
10CFR55:        41.b.12 41.b.12
 
==Reference:==
 
==Reference:==
0-ADM-600, Section 0-ADM-600,        Section 5.7.1.4 5.7.1.4 11 OCFR20 OCFR2O - Radiation Radiation Area Definition Definition Cog  Level:
Cog Level:    33 Analysis Level 33 because the operator operator must recall the administrative administrative limits limits and then calculate the remaining stay time by    by determining the total dose rate. The operator must recognize to use the inverse square law to calculate that the valve reading 60 mr/hr at 11 meter will cause a 15 mr/hr dose rate at the 2 meter work location.
However, the operator must recognize that the general area dose (10CFR20          (10CFR2O dose rate =
    = 5 mr/hr minimum for Rad Area) needs to be added as well as the worker is also exposed to this. This will allow 4 hours of stay time before exceeding the 1000 Administrative Limit is 1000 mr/yr without an extension. Operator has mr guideline. Administrative 60 mr remaining exposure.
New Question Response Analysis:
A.      Incorrect-pla  usible if you improperly calculate the 60 mr/hr at 1 Incorrect-plausible                                                          1 meter remains constant out to 2 meters (plane source calculation).
B.      Incorrect-pla  usible if you do not account for the inverse square law and only Incorrect-plausible reduce the dose by Y    % (30 mr/hr) instead of 1/4 2                              % (a common mistake)
C. Correct Correct - the 15
                  -    15 mr/hr mr/hr from the valve valve is added to the 55 mr/hr mr/hr general area dose dose  rate  to have  20  mr/hr mr/hr total resulting inin 33 hours of stay time.
D.
D.      Incorrect Incorrect because because the    dose from the dose          the valve from the    valve atat 22 meters meters isis 15 15 mr/hr mr/hr but but the the general general area area dose dose rate rate must must bebe added added to    it.
to it.
142 142
 
NRC DRAFT NRC      DRAFT                              07/24/07 07/24/07 Q #72 Q#72 Given the Given    the following following conditions conditions at        work site:
at aa work  site:
**  Radiation level Radiation      level isis 40 40 mrem/hr mrem/hr
**    Radiation    level  with  shielding Radiation level with shielding isis 10        10 mrem/hr mrem/hr
**  Time for Time      for one one worker worker to  to place place shielding shielding isis 15 15 minutes minutes
**  Time    to conduct      the  task Time to conduct the task with one    with  one worker worker isis 11 hour.
hour.
**  Time to Time      to conduct conduct the  the task task with with 22 workers workers isis 20 20 minutes.
minutes.
Assumptions:
Assumptions:
**  IfIf shielding shielding is is used, used, itit is is to to be  installed by be installed    by one one worker worker only.
only.
**  The worker The      worker placing placing shielding shielding willwill be be exposed exposed to  to aa dose rate of dose rate of 40 40 mr/hr.
mr/hr.
Which ONE of the following would        would result in in the lowest lowest total whole body dose?
A.        Conduct the task with two workers with shielding.
B.        Conduct the task with two workers without shielding C.        Conduct the task with one worker with shielding.
D.        Conduct the task with one worker without shielding.
143 143
 
NRC DRAFT NRC      DRAFT                              07/24/07 07/24/07 Q #72 Q#72 ANSWER:
ANSWER:        AA KA:
KA:            G.2.3.2 G.2.3.2 Knowledge of Knowledge    offacility facility ALARA ALARA program.
program. 2.5/2.9 2.5/2.9 IOCFR55:
10CFR55:        41 .b.9, 41.b.12, 41.b.9,    41 .b.12, 41.b.13 41 .b.13
 
==Reference:==
 
==Reference:==
0-ADM-600, Step 0-ADM-600,        Step 5.1.1.2 5.1.1.2 Cognitive Level:
Cognitive  Level: 33 Application Application // Analysis Analysis Level 33 because Level    because the the operator operator must must recall recall the the ALARA ALARA rulerule which which calls calls for for the the total total collective exposure collective  exposure to to be  minimized. Then be minimized.      Then the the operator operator must must calculate    the calculate the collective exposure collective  exposure for each each option option and and choose choose thethe alternative alternative with with the the lowest lowest total total collective exposure.
collective  exposure.
Bank Question Bank Response Analysis:
A.
A.      correct because the total dose would be 10 mr to the worker placing the shielding plus 3.3 mr to each worker resulting in 16.6 total mr.
B.      incorrect because each worker receives 13.3 mrfor      mr for aa total dose of approximatel approximately  y  26.6  mr.
C.      incorrect because the worker would receive 20 mrem. (10 mrem while placing the shielding and 10  10 mrwhile mr while performing the work).
D.
D.      Incorrect Incorrect because because thisthis would would result inin one one worker worker receiving 40  40 mr.
mr.
144 144
 
NRC DRAFT NRC      DRAFT                                  07/24/07 07/24/07 Q #73 0#73 An operator An    operator has has volunteered volunteered to  to be be aa member member of  of an an Emergency Emergency Response Response Team  Team that will that  will enter enter aa high high radiation radiation area area to  rescue aa person to rescue      person from from aa non-life non-life threatening threatening situation.
situation.
** TheThe operator operator has has already already received received 22 REM REM Total Total Effective Effective Dose Dose Equivalent Equivalent (TEDE)
(TEDE) this  this year.
year.
**    The dose The    dose projection projection forfor each each team team member member forfor this this rescue rescue isis 44 REM REM TEDE.
TEDE.
Which ONE Which      ONE of      the following of the  following isis correct correct regarding regarding this this situation?
situation?
The operator The    operator may:may:
A.
A.        NOT be NOT      be part part of of the rescue rescue team.
IfIf the  operator participated, the the operator                      the additional additional 44 REM REM would exceed the annual I10CFR20 OCFR2O limit but would NOT      NOT exceed the allowable allowable exposure exposure limitlimit of Enclosure 11 of O-EPIP-20111, O-EPIP-201 II, "Re-Entry" Re-Entry...
B.      NOT be part of the rescue team.
If the operator participated, the additional 4 REM would exceed the annual 100FR2O limit and would exceed the allowable exposure limit of Enclosure 1I 10CFR20 O-EPIP-201 11, "Re-Entry".
of O-EPIP-20111,          Re-Entry.
C.      be part of the rescue team.
The additional 4 REM will NOT exceed the annual 10CFR20            IOCFR2O limit and will NOT exceed the allowable exposure limit of Enclosure I1 of O-EPIP-201            O-EPIP-20111, 11, Re-Entry.
        "Re-Entry" .
D.      be part of the rescue team.
The The additional additional 44 REM will  will exceed exceed thethe annual 110CFR20        limit but OCFR2O limit      but will NOT NOT exceed exceed the allowable exposure  exposure limit limit of of Enclosure Enclosure 11 of of O-EPIP-201 O-EPIP-20111,    11, Re-Entry.
        "Re-Entry" .
145 145
 
NRC DRAFT NRC        DRAFT                              07/24/07 07/24/07 Q #73 Q#73 ANSWER:
ANSWER:        DD KA:
KA:            G.2.3.4 G.2.3.4 Knowledge of Knowledge        radiation exposure of radiation    exposure limits limits and and contamination contamination control, control, including including permis  sible levels inin excess permissible levels        excess ofof those those authorized.
authorized. 2.5/3.1 2.5/3.1 IOCFR55:
10CFR55:        41.b.12 41.b.12
 
==Reference:==
 
==Reference:==
0-EPIP-20111, Step O-EPIP-20111,        Step 5.1.1.1, 5.1.1.1, 5.1.1.4, 5.1.1.4, 5.1.1.8, 5.1.1.8, Enclosure Enclosure 11 I OCFR2O.1201 10CFR20.1201 Cog Level:
Cog  Level:    1I Recall Recall New Question New  Question Response Analysis:
 
===Response===
A.
A. Incorrect because Incorrect    because the operator operator may be a membermember of the team in spite of 10CFR2O limits. Plausible violating the 10CFR20                  Plausible because because the annual 10CFR20 10CFR2O limit will be exceeded exceeded and the EPIP-20111 EPIP-201 11 limit of 10 REM will not be exceeded. exceeded.
B.
B. Incorrect because because the operator operator may be a member member of the team and the additional 4 REM would not violate the EPIP limit of 10 additional                                                        10 REM. Plausible Plausible becaus because  e  the  annual  IOCFR2O 10CFR20 limit will be exceedexceeded.
ed.
C.
C. Incorrect becaus because e the 10CFR2O 10CFR20 limits limits will be violated. Plausib Plausible  because le becaus  e the operato operatorr maymay bebe aa membe member    r of of the the team and and the EPIP-201 EPIP-20111      limit of 11 limit  of 10 10 REM REM will not  not be be violated.
D.
D. Correc Correctt becaus because  e the the operato operator  r may may bebe aa membe member    of the r of  the team team inin spite spite of of violating    the  I OCFR2O violating the 10CFR20 limits. limits. The The EPIP-201 EPIP-20111    limit of 11 limit  of 10 10 REM REM will will not not be be violated.
violated.
146 146
 
NRCDRAFT NRC      DRAFT                              07/24/07 07/24/07 Q #74 Q#74 Unit44tripped Unit      trippedfromfrom 100%100%power.
power.
Thefollowing The    following conditions conditions are  areobserved observed by  bythe the control control room room operators operators upon upon compl  etion  of  4-EOP-E-0:
completion of 4-EOP-E-O:
**  Steam Generator Steam      Generatornarrow narrow range range levels:
levels:      off-scale off-scale low low
**  Steam      Genera    tor Steam Generator pressures:  pressu  res:                  800  psig 800 psig
**  3A S/G 3A    S/G AFWAFW max.max. flowflow rate:
rate:                  100 gpm 100  gpm
* 3B S/G S/G AFWAFW max.max. flowflow rate:
rate:                  125 125 gpm
* 3B                                                              gpm
**  3C S/G 3C    S/G AFWAFW max.max. flow flow rate:
rate:                    125 gpm 125  gpm a  Pressurizer level:
Pressurizer        level:                                  off-scale off-scale low low
* RCS    pressu    re:                                    600 600 psig
* RCS pressure:                                                    psig
* RCS ColdCold Leg Leg temperatures:
temperatures:                        330&deg;F 330&deg; F
* RCS Which ONE Which    ONE of  of the the following following identifies identifies the the correct correct procedure procedure the the operators operators should should transit ion  to when      4-EOP    -E-0 transition to when 4-EOP-E-0 is complete? is  compl  ete?
A.
A.      4-EOP-E-1, "Loss 4-EOP-E-1,          Loss of Reactor Reactor or Secondary Secondary Coolant" Coolant B.
B.      4-EOP-E-2, "Faulted 4-EOP-E-2,        Faulted Steam Generator Generator Isolation" Isolation C.
C.      4-EOP-FR-P.1, "Response 4-EOP-FR-P.1,          Response to Imminent Imminent Pressurized Pressurized Thermal Thermal Shock Condit  ion Condition" D.
D.      4-EOP    -FR-H.1, Respo 4-EOP-FR-H.1,          "Responsense to Loss of Second Secondaryary Heat Sink Sink" 147 147
 
NRC DRA  DRAF  FTT                            07/24/07 07/2410 7 Q #74 Q#74 ANSWER:          A KA:              G.2.4.4 G.2.4  .4 Ability to recog recogn  ize abnor nize  abnorm  al indica mal  indicattions ions for system opera operati    ng param ting  parame    ters which are eters entry level conditions for emerg  emergeency ncy and abnor abnorm  al opera mal  operati    ng proce ting  proced  ures.. 4.0/4.
dures      4.0/4.33 IOCFR 10CF      55:
R55:      41.b.10 41.b.1  0 Refere Refer    nce:
ence:      4-EOP-E-O, 4-EOP    -E-0, Step 15 4-EOP-F-O, 4-EOP    -F-0, Enclo Enclos  ures 3 and 4 sures Cog Level:          Comprrehen 2 Comp      ehensi  on sion Level 2 becau becaus see the opera operatotorr must recog recogn  ize that a LOCA exists and a secon nize                                      seconddary ary break does not. The Opera    Operattor or must then apply the criteri criteria a of EOP-F EOP-F-O -0 to determine that a red or orang orange e path does not exist for heat sink or integr  integriity.
ty.
New Quest Questiion on Response Analy Analyssis:
is:
A.        Correcctt per the refere Corre                referen  ces nces B.        Incorre Incorr  ect ct becau becaus  see a LOCA exists and the correc correctt transi transittion ion is to EOP-EOP-E  -1, E-1, not EOP-EOP-E  E-2.
                      -2. Plaus Plausibible le becau becaus  e S/G press se      pressu  res are lower than expec ures                        expectted ed for the post-t post-trrip ip condition and conta contain mentt press inmen    pressu  re is at a value that can be ure caused caused by a MSLB.
c.
C.      Incorre Incorr  ect ct becau becaus  see a LOCA exists and the correccorrectt transi transittion ion is to EOP-E-1, not EOP-EOP-F  FR-P.
R-P.1.1. Plaus Plausib  le becau ible becaus see RCS cold leg tempetemperrature atures s are above the thresh threshooldld value of 320&deg;F 320&deg; F that would force transi transiti  on tion to FR-P.
FR-P.1 1..
D.      Incorre Incorr    ct becau ect  becaus    e a LOCA exists and the correc se                              correctt transi transiti  on is to tion    to  EOP-E-1,,
not EOP-EOP-F    R-H.1.
FR-H. 1. Plaus Plausib  le becau ible becaus  e se S/G NR levels are off-sc  off-sca le low and ale AFW flow rates are barely above the thresh      threshoold ld value of 345 psig that would force transi transiti on to FR-H.1.
tion 148
 
NRC DRA FT                                  07/24/07 07/24/0 7 Q #75 Q#75 Opera Operattors ors are perfor perform ming ing 3-EOP-FR-C.2, "Resp Respo  nse to Degra onse    Degrad  ed Core Cooling ded                g" and are currently depre depresssuriz surizin  g all intact S/Gs.
ing            SIGs.
The STA updat updateess the Shift Mana Manag    er that prese ger      presenntly tly the CSF status trees for Contaiinmen Conta  nmentt (due to high contacontain  mentt press inmen    pressuure) re) is Orang Orange e and Integr Integriity ty is Red. All other CSF status trees are green or yellow.
Which ONE of the follow ing descr  describ  es the correc ibes      correctt opera operato torr respo respon  se?
nse?
A.      Imme Immed diatel iatelyy transi transittion ion to 3-EOP-FR-Z.1, "RespRespo  nse to High Conta onse            Contaiinmen nmentt Pressu Pressure."
re.
B. Imme Immed diatel iatelyy transi transittion ion to 3-EOP-FR-P
                                                -FR-P..1, 1, "Resp Respo  nse to Immin onse      Imminent ent Press Pressuurized rized Thermal Shock Condi  Condittion."
ion.
C. Continue in 3-EOP-FR-C.2 until comp      compllete.
ete. Then transi transittion ion to 3-EOP-FR-Z-FR-Z..11,,
Respo "Resp    nse to High Conta onse              Contaiinmen nmentt Press Pressuure."
re.
D. Continue in 3-EOP-FR-C.2 until comp      compllete.
ete. Then transi transittion ion to 3-EOP-FR-P
                                                                                          -FR-P..11,,
      "Resp Respo onse nse to Immin Imminent Press Pressuurized rized Thermal Shock Condi Condittion."
ion.
149
 
NRCDRAFT NRC        DRAFT                                    07/24/07 07/24/07 Q #75 Q#75 ANSWER:
ANSWER:          DD KA:
KA:                G.2.4.5 G.2.4.5 Knowl    edge Knowledge of theof  theorganization organization of  ofthe theoperating operating procedures proceduresnetwork networkfor fornormal, normal, abnorm    al and  emerge    ncy    evolut abnormal and emergency evolutions. 2.9/3.6  ions. 2.9/3.6 100FR55:
10CFR55:          41.b.1O 41.b.10
 
==Reference:==
 
==Reference:==
0-ADM-211, Step 0-ADM-211,        Step 5.10.6 5.10.6 3-EOP  -FR-C 3-EOP-FR-C.2      .2 Caution Caution prior prior to to Step Step 1313 Cognitive Level:
Cognitive    Level: 22 Comprehension Comprehension Level Level 22 because because the the operator operator mustmust recall recall the the Caution Caution inin FR-C.2 FR-C.2 that that directs directs that that FR-FR-0.2  be  compl  eted  prior  to transit C.2 be completed prior to transitioning    ioning to to the the Red Red Path Path onon Integrity.
Integrity. The The caution caution states that states  that you you must must complete complete FR-C.2 FR-C.2 priorprior toto transitioning transition ing to to FR-P.1.
FR-P.1. This This isis contrar y  to the  rules  of  usage    and contrary to the rules of usage and require the  require    the operator operator to to analyze analyze and and evaluate evaluate that that the completion the  completion of  of C2 C2 isis higher higher importance importance than  than the the P1P1 transition transition for the given      plant given plant conditions. Additionally conditions. Additionally this exception exception to the rule    rule is is identified identified in in 0-ADM-211.
0-ADM-21 1.
New Question New    Question Response Analys Response              is:
Analysis:
A.
A.      Incorrect becaus Incorrect    because  e the operato operators  rs should contin continue        3-EOP-FR-C.2 ue in 3-EOP                until
                                                                                          -FR-C.2 until compl  ete.
complete.      Then    transit ion transition    to 3-EOP      -FR-P.1. Plausib 3-EOP-FR-P.1.            Plausible    because le becaus  e an Red pathpath exists exists on on Integri  ty.
Integrity.
B.
B.      Incorre Incorrectct becaus because  e the the operato operators rs should should contin continueue inin 3-EOP 3-EOP-FR-C.2        until
                                                                                          -FR-C.2 until compl  ete. Then complete.      Then transit    ion to transition    to 3-EOP      -FR-P.1. Plausib 3-EOP-FR-P.1.            Plausible    because    an le because an Red  Red exists  associa  ted    with exists associated with vessel  vessel integri    ty.
integrity.
C.
C.      Incorre Incorrectct becaus because  e the the operato operators rs should should transit transition ion toto 3-EOP 3-EOP-FR-P.1        following
                                                                                            -FR-P.1 follow    ing comple    tion of completion    of 3-EOP    -FR-C.2. Plausib 3-EOP-FR-C.2.          Plausible  le becaus because  e anan orange orange path path exists exists due due to to contain  ment high containment      high pressu    re.
pressure.
D.
D.      Correc Correct t per perthe the referen referencece 150 150
 
NRC DRA FT                                    07124/0 07/24/07 7
Q #76 0#76 Operators Opera  tors are perfor perform  ing 3-EOP-ES-1 .2, ming                  .2, "Post Post LOCA CooldCooldo wn and own Depressu Depre      rizat ssuriz    ion," and are prepa ation,              preparing ring to start an RCP.
Primarryy system Prima    system param paramete    rs are:
eters
* PRZ Level:                              73%
* RVLMSS Plenu RVLM      Plenum  m Level:            Full Full
* RVLM    S Head RVLMS Head Level:                        NOT Full Which ONE of the follow  following ing descr describes ibes the effect on pressurizeurizerr level when an RCP started is starte    under these condit d under            condition ionss and the correc correctt opera operator tor respo response?
nse?
Pressuriz Press      er level will:
urizer A.      drop when an RCP is starte    started.
d.
Transiition Trans  tion to 3-EOP 3-EOP-FR-FR-1-l.3,  Respons
                                        .3, "Resp  onsee to Voids in React Reactor or Vesse Vessell."
B.      NOT be affect affecteded when an RCP is starte  started.d.
Transiition Trans  tion to 3-EOP 3-EOP-FR-FR-1-l.3,  Respons
                                        .3, "Resp  onse  e to Voids in React Reactor or Vesse Vessell."
C.      drop when an RCP is starte  started.d.
Continue Contin          implem ue to imple      ent 3-EOP-ES-1 ment            -ES-1.2.
                                                      .2.
D. NOT be affect affecteded when an RCP is starte  started.d.
Continue Contin  ue  to impl impleemen mentt 3-EOP 3-EOP-ES -ES-1 1 .2.
                                                      .2.
151 151
 
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ReselVed.
 
NRC DRAFT NRC        DRAFT                                07/24/07 07/24/07 Q #76 Q#76 ANSWER:
ANSWER:          CC KA:
KA:                000009EA2.04 000009EA2.04 Able to Able      determine and to determine      and interpret interpret the the following following as as they they apply apply to to Small Small Break Break LOCA:
LOCA:
PRZ Level.
PRZ    Level. 3.8/4.0 3.8/4.0 IOCFR55:
10CFR55:          43.b.5 43.b.5
 
==Reference:==
 
==Reference:==
3-EOP-ES-1 .2, Step 3-EOP-ES-1.2,      Step 2525 and and BD BD 3EOP-F-O,      Enclosure 66 3-EOP-F-0, Enclosure 3-EOP-FR-l.3, CAUTION 3-EOP-FR-1.3,    CAUTION prior  prior to to Step Step 11 Cog Level: 2 Analysis Level 2 because the operator must determine that the RVLMS            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 starting an RCP is desirable in these circumstances circumstances to provide forced cooling and 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-1.3 FR-I.3 should not be implemented when SI pumps are 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.      Incorrect because pressurizer level will drop when an RCP is started as coolant flow to the head region collapses the void, lowering the pressurizer level. Plausible because aa transition to FR-l-3    FR-I-3 would address the head  head void.
Additionally the operator operator must recognize FR-l.3  FR-1.3 should not not be implemented when SI  SI pumps are operating.
operating.
C.
C.      Correct Correct per    the reference per the D.
D.      Incorrect Incorrect because because pressurizer pressurizer level level will will drop drop when when anan RCP RCP isis started started asas coolant coolant flowflow to to the the head head region region collapses collapses the the void, void, lowering lowering the the pressurizer pressurizer level.
level. Plausible Plausible because because thethe operators operators should should continue continue to to implement implement 3-EOP-3-EOP-ES-i ES-1.2..2.
152 152
 
NRC DRAFT NRC      DRAFT                                07/24/07 07/24/07 Q #77 0#77 3EOPECA-2.1, "Uncontrolled 3-EOP-ECA-2.1,        Uncontrolled Depressurization Depressurization of  ofAll All Steam Steam Generators,"
Generators, directs directs operators to operators      control feed to control    feed flow flowto  minimize RCS to minimize  RCS cooldown.
cooldown.
RCS cold RCS  cold reg leg temperatures temperatures have  have decreased decreased from from 54rF 547&deg;F toto 340&deg;F 340&deg;F inin the the past past 60 60 minutes.
minutes.
Which ONE Which  ONE of      the following of the  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    to  3-EOP-FR-P Transition to 3-EOP-FR-P.1,      .1, "Response Response to  to Imminent Imminent Pressurized Pressurized Thermal Thermal Shock Condition."
Shock    Condition.
B.
B. Decrease feed Decrease      feed flow flow to  25 gpm to 25  gpm toto each each S/G.
S/G.
Transition    to  and  complete    3-EOP-FR-H Transition to and complete 3-EOP-FR-H.1,          .1, "Response Response to    Loss of to Loss    of Secondary Secondary Heat Sink."
Heat    Sink.
C. Continue to implement Continue        implement 3-EOP-ECA-2.1.
3-EOP-ECA-2.1. Decrease feed flow to 25 gpm to each S/G.
D.                                    3-EOP-ECA-2.1. Decrease total feed flow to 345 Continue to implement 3-EOP-ECA-2.1.
gpm.
153 153
 
NRC DRAFT NRC        DRAFT                                07/24/07 07/24/07 Q #77 Q#77 ANSWER:
ANSWER:          CC KA:
KA:                W/EI2EA2.2 W/E12EA2.2 Able  to  determine Able to determine and    and interpret interpret thethe following following asas they they apply apply toto Uncontrolled Uncontrolled Depressuriza    tion of  all S/Gs:    Adherence      to  appropriate Depressurization of all S/Gs: Adherence to appropriate procedures          procedures and and operation operation within the within  the limitations limitations inin the the facility's facilitys license license and and amendments.
amendments. 3.4/3.9 3.4/3.9 10CFR55:
10CFR55:          43.b.1 && b.5 43.b.1      b.5
 
==Reference:==
 
==Reference:==
3-EOP-ECA-2.1, Step 3-EOP-ECA-2.1,          Step 33 3-EOP-F-0, Enclosure 3-EOP-F-0,        Enclosure 44 3-EOP-FR-H.1, CAUTION 3-EOP-FR-H.1,          CAUTION prior  prior to to Step Step 11 Cog Level:
Cog  Level:        Comprehension 22 Comprehension Level 22 because Level      because the operator must    must recognize recognize that withwith aa cool down> 100&deg;F/hour, 100&deg;F/hour, ECA-2.1 ECA-2.1    will require feed flow to be reduced to 25 gpm per S/G. This reduction in feed flow feed  flow will result in a red  red path on heat sink, but because because the reduction of feed flow was procedurally driven, performance of FR-H.1 is not desirable.
New Question Response Analysis:
A.
A.      Incorrect because RCS temperatures have not dropped far enough to trigger an orange path on Integrity and feed flow should be reduced to 345 gpm..                  gpm ..
Plausible because RCS temperatures have dropped 227&deg;F                  22rF in the past 60 minutes.
B.
B.      Incorrect Incorrect because transition to        to FR-Hi FR-H.1 is is not required because feed flow has      has been reduced due  due to procedural requirements requirements.. Plausible Plausible because because operators operators will will decrease decrease feed feed flowflow to 2525 gpm gpm toto each each S/G.
S/G.
C.
C.      Correct Correct perper the the reference reference D.
D.      Incorrect Incorrect because because feedfeed flow flow needs needs to to be be reduced reduced toto 25 25 gpm gpm to to each each S/G S/G as as directed directed by by EOP-ECA-1 EOP-ECA-1.2.      .2. Plausible Plausible because because operators operators will will continue continue to to implement implement 3-EOP-ECA 3-EOP-ECA-2.    -2.
154 154
 
NRCDRAFT NRC        DRAFT                                07/24/07 07/24/07 Q #78 0#78 Unit44 isisatat 100%
Unit              100% power powerwith with all all systems systemsinin normal normal alignment.
alignment.
** The The 4A  4A CCWCOW pumppump isis being being removed removed from from service.
service.
** The The 4A  4A CCWCOW pumppump CS  CS has has been been placed placed inin Pull-to-Lock Pull-to-Lock but but its its breaker breaker isis still still racked in.
racked        in.
The switchyard The    switchyard subsequently subsequently de-energizes.
de-energizes.
Which ONE Which      ONE of  of the the following following correctly correctly describes describes UnitUnit 44 sequencer(s) sequencer(s) response response and  and the first  procedure      operators the first procedure operators will use    will  use to  verify correct to verify  correct CCW COW system system alignment?
alignment?
A.
A.        4A sequencer 4A    sequencer will  will close close thethe 4C 40 CCW COW pump pump breaker.
breaker.
4B sequencer 4B    sequencer will      close the will close    the 4B 4B CCW COW pump pump breaker.
breaker.
4-EOP-ES-0.1, "Reactor 4-EOP-ES-O.1,          Reactor TripTrip Response."
Response.
B.
B.              sequencer will close 4A sequencer              close the 4C  40 CCW COW pump pump breaker.
breaker.
4B sequencer sequencer will close the 4B CCW        COW pump breaker.
4-ONOP-004, "Loss 4-0NOP-004,          Loss of Offsite Power."
Power.
0.
C.              sequencer will attempt to close the 4A CCW 4A sequencer                                              COW pump breaker.
4B sequencer sequencer will close the 4B CCW        COW pump breaker.
4-EOP-ES-0.1, "Reactor 4-EOP-ES-0.1,          Reactor Trip Response."
Response.
D.        4A sequencer will attempt to close the 4A COW              CCW pump breaker.
4B sequen sequencer cer  will close  the  40  COW 4C CCW pump breaker.
4-ONOP-004 4-0NOP-004,, Loss    "Loss of Offsite Power.
Power."
155 155
 
NRCDRAFT NRC        DRAFT                                        07124/07 07/24/07 Q #78 Q#78 ANSWER:
ANSWER:            CC KA: 000056AA2.47 KA:        000056AA2.47 - Able    - Abletoto determine determine and and interpret interpret the  the following following as  as they they apply apply to Loss    of Off-site    Power:      Proper to Loss of Off-site Power: Proper operation        operation of ofthe the EOGEDG load load sequencer.
sequencer. 3.8/3.9 3.8/3.9 10CFR55:
10CFR55:            43.b.5 43.b.5
 
==Reference:==
 
==Reference:==
4-EOP-ES-0.1, Step 4-EOP-ES-0.1,          Step 17 17 4-ONOP-004 4-0NOP-004,, First    First NOTE NOTE prior prior toto Step Step 1I 5614-T-L1, 5614-T-L          Sheet 12A 1, Sheet      12A && 128, 12B, 5610-T-L1, 5610-T-L          Sheet 1240 1, Sheet      124D 5610-T-L1, 5610-T            Sheet 152A
                              -L 1, Sheet      152A Cog Level:
Cog    Level:      22 Comprehension Comprehension Level 22 because Level      because the  the operator operator mustmust recognize recognize that that ifif the the 4A 4A CCW CCW pumppump is  is in in PTL PTL itit cannot    start. If the cannot start. If the 4A CCW 4A  CCW      pump      breake breakerr hashas not not been been racked out, the 4A sequencer will still try to close its sequencer                                    its breaker breaker inin the event of    of a LOOP.
LOOP. 4C CCW pump          pump can be can  be started by either sequencersequencer depending depending on the alignment  alignment of 40  4D bus.
However if both 4A and 48 However                            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                  to EOP-E-0 EOP-ES  EOP-ES-0.1 in response 0.1    response to the reactor trip caused by the LOOP. ES-0.1, Step 17 is the first                                first procedural opportunity to verify proper CCW operation.
procedural                                                      operation. Note that it is checked    checked a    a second time in ONOP-004 second                ONOP-004 after operatorsoperators complete complete ES-0.1.
New New Questi Question on Respo Response nse 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 breaker.r. Plausib Plausible  le becaus because  e 4B 48 sequen sequencer      will close cer will    close the the 4B48 CCW CCW pump  pump breake breaker  r and and operato operators  rs will will verify verify the the CCW CCW alignm alignment        first using ent first  using 4-EOP 4-EOP-ES- -ES-0.1,  React 0.1, "Reactor        Trip or Trip Respon Response." se.
B.
: 8.      Incorrect Incorrect becaus because  e 4A4A sequen sequencer  cer will will attemp attempt  t toto close close thethe 4A 4A CCW CCW pump  pump breake breaker r and and operato operators  rs will will verify verify the the CCW 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  le becaus because        48 sequen e 4B    sequencer      will close cer will      close the the 4B48 CCW CCW pump  pump breake breaker  r C.
C.      Correc Correct t per perthe the referen referencece D.
O.      Incorrect Incorrect becaus because  e 4B 48 sequen sequencer  cer will will close close thethe 4B  48 CCW CCW pump pump breake breaker      and r and operato operators rs will will verify verify the the CCW CCW alignment alignmentfirst 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 4A CCW CCW pump  pump breake breaker.r.
156 156
 
NRCDRAFT NRC      DRAFT                                  07/24/07 07/24/07 Q #79 0#79 Unit33 isis atat 75%
Unit              75% power powerwhenwhen the thefollowing following occur; occur;
**  Automatic VCT Automatic        VCT makeup makeup STARTS STARTS withwith VCT VCT level level atat 50%
50% on on LT-112.
LT-1 12.
**  3B  main      feedwater  flow    control  valve 3B main feedwater flow control valve transfers      transfers toto MANUAL MANUAL mode. mode.
**  QSPDS channel OSPDS          channel "A" A isis DEENERGIZED DEENERGIZED
**  Train 1I AFW Train        AFW flow flow control control valves valves fail fail CLOSED CLOSED After completion After  completion of    of any any immediate immediate operator operator actions actions andand with with the the plant plant stable, stable, the the US should; US  should; A.
A.        Restore 3A Restore      3A EDG EDG to to service service within within 7272 hours hours or or initiate initiate aa plant plant shutdown shutdown to  to reach      Mode  3  within    the following reach Mode 3 within the following 66 hours        hours because because 3A  3A EDG EDG auto-start auto-start capability has capability    has been been lost.
lost.
B.
B.        Restore 3P07 Restore      3P07 toto service service within within 11 hour hour or or initiate initiate aa plant plant shutdown shutdown to  to reach reach Mode 33 within the following 66 hours Mode                                      hours because because AFW actuation actuation logic has been logic  has  been degraded.
degraded.
C.      Verify that all Train B emergency equipment is operable within 2 hours or                      or initiate a plant shutdown to reach Mode 3 within the following 12 hours because 3A EDG auto-start capability has been lost.
because D.      Place 3A 4kv bus and 3A/3C      3A13C 480V load center bus stripping logic in the tripped condition within 2 hours because AFW actuation logic has been degraded.
157 157
 
NRCDRAFT NRC            DRAFT                                    07/24/07 07/24/07 Q #79 Q#79 ANSWER: BB ANSWER:
KA:
KA:                    000057G2.1.33 000057G2.1.33 As  it relates As it relates to Lossto  Lossof  ofVital Vital AC AC Inst.
Inst. Bus:Bus: Ability Abilitytoto recognize recognize indications indicationsfor  forsystem system operati    ng  parame operating parameters        ters which which areare entry-level entry-level conditions conditions for  fortechnical technical specifications.
specifications.
((3.4 3.4 1/4.0) 4.0 )
10CFR55:
10CFR55:              43.b.2 43.b.2
 
==Reference:==
 
==Reference:==
3-ONOP-003.7 Enclosure 3-0NOP-003.7            Enclosure 1,      1, NOTE NOTE 11 Tech    Specs.      3.0.3 Tech Specs. 3.0.3 - Page      -  Page 3/40-1 3/4 0-1 Cog Level:
Cog      Level: 22 Comprehension Comprehension Level    2  becaus Level 2 becausee the      the operator operator mustmust analyzeanalyze 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 in in aa loss loss of of 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      in results in loss of aa loss    of anan auto auto start start signal signal toto the the AFW actuation actuation as  as well well as as the the EDG EDG output output breaker auto breaker      auto closure closure failure. He    He then must    must determine determine that the TS actions  actions of 3.0.33.0.3 are required are  required based based on AFW availability.
New Question New      Question Response Analysis:
Response          Analysis:
A.
A.          Incorrect, indications are for a loss of 3P07 therefo Incorrect,                                                        therefore re operators operators must take    take action action    within    1 1  hour  to  restore      the Vital AC panel or initiate aa plant shutdown to to reach reach Mode 33 within the following 66 hours becaus                because            actuation e AFW actuati        on logic has    been    degrad    ed. Plausib has been degraded. Plausible because          le  becaus      3A EDG e 3A    EDG auto-st auto-start    capability has art capability      has been been degrad degraded  ed andand 3A3A EDGEDG tech  tech specs specs areare also also applica applicable      (but less ble (but    less restrictive).
restrictive ).
B.
B.        Correc Correctt perper the the referen reference ce C.
C.        Incorrect, Incorrect, indications indications are  are for for aa loss      of 3P07 loss of  3P07 therefo therefore    operators re operato          must take rs must    take action    within    1  hour  to  restore action within 1 hour to restore the              the Vital Vital AC AC panel panel or or initiate initiate aa plant plant shutdo shutdown wn to to reach reach Mode Mode 33 within within the the following following 66 hours hours becaus because    AFW actuati e AFW      actuation      logic on logic has has been been degrad degraded. ed. Plausib Plausible    le becaus because    all Train e all  Train BB emerge emergency        equipment ncy equipm        ent needs needs to  to be be verified verified operab operable  le within within 22 hours.
hours.
D.
D.      Incorrect, Incorrect, indications indications are  are for for aa lossloss of of3P07 3P07 therefo therefore    operators re operato          musttake rs must      take action action within within 11 hour hourto to restore restore the    the Vital Vital AC AC panel panel or orinitiate initiate aa plant plantshutdo shutdownwn toto reach reach Mode Mode 33withinwithin the thefollowing following 66 hours hours becaus because    AFW actuati e AFW      actuation      logic on logic has has been been degrad degraded. ed. Plausib Plausible    le becaus because    operators e operato        will need rs will  needtoto place place3A  3A4kv4kv bus    and    3A/3C      480V    load    center bus and 3A/3C 480V load center busstripping        bus  stripping logic logicininthe thetripped tripped condition.
condition.
158 158
 
NRCDRAFT NRC        DRAFT                            07/24/07 07/24/07 Q #80 0#80 Unit44isisatat100%
Unit              100%powerpowerwithwith all all systems systems inin normal normalalignment alignmentwhen whenthethe4A4AICW ICW pump    breakertrips pump breaker            tripsopen open on on over-current.
over-current.
The 4A The  4A ICW ICW pump pump isis declared declared inoperable inoperable and and removed removed from from service.
service.
Which ONE Which      ONE of    ofthe the following following describes describes the  the Technical Technical Specification Specification limits limits associated associated with the with  the 4A 4A ICWICW pumppump being being out out ofof service?
service?
Unit 44 isis inin a:
Unit              a:
A.
A.        72 hour 72      hour action action statement.
statement. The  The action action statement statement time time can can be be extended extended toto seven      days  if 4D  4KV  Bus seven days if 40 4KV Bus is realigned    is realign ed to to 4A 4A 4KV 4KV Bus.
Bus.
B.
B.        72 hour 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 seven        day action statement.
statement. The action action statement statement time cancan be be extended extended toto thirty days thirty    days if 40 4D 4KV Bus is    is realigned to 4A 4KV Bus.
D.
O.      seven day seven        day action statement.
statement. The action statementstatement time can NOT be extend extended    ed  by  realigning  4D 40    4KV  Bus.
159 159
 
NRCDRAFT NRC          DRAFT                                    07/24/07 07/24/07 Q #80 Q#80 ANSWER:
ANSWER:            AA KA:
KA:                  000062G2.2.22 000062G2.2.22 As  it relates    to As it relates to Loss  Loss of  ofNuclear NuclearSvc  SvcWater:Water: Knowledge Knowledge of    of limiting limiting conditions conditions for for operations && safety operations          safety limits.
limits. 3.4/4.1 3.4/4.1 IOCFR55:
10CFR55:            43.b.2 43.b.2
 
==Reference:==
 
==Reference:==
Tech Spec Tech    Spec 3.7.33.7.3 Actions Actions aa and    and bb 5610-T-E-15        91, 561 0-T-E-1591, Sheet 1  Sheet      1 Cog Level:
Cog    Level:      22 Comprehension Comprehension Level 22 because Level        because the the operator operator must must recognize recognize that that the the 4A4A ICW ICW pump pump is  is powered powered from    4A    4KV    Bus. If plant from 4A 4KV Bus. If plant components    compo    nents are  are inin normal normal alignment, alignment, 4B  4B and and 4C 40 ICW ICW pumps share pumps      share thethe same same traintrain power power supplysupply resulting resulting in in aa 72 72 hour    action    statement.
hour action statement.
Swapping 40 Swapping        4D Bus Bus to 4 A Bus  Bus places places 4C ICW      ICW pump pump on  on the "A"A Train increasing increasing the  the Action Time Action    Time to to 77 days.
days.
New Question New    Question Response Analysis:
Response        Analysis:
A.
A.        Correc Correctt per the referen reference ce B.
B.        Incorrect Incorrect becaus because    e the action statem  statement ent time can be extend extendeded to seven days ifif 4D 40 4KV 4KV BusBus is  is realign realigneded toto 4A 4A 4KV 4KV Bus. PlausibPlausible      because le because Unit  Unit 44 is is in in aa 72    hour  action    statem 72 hour action statement.        ent.
C.
C.      Incorrect Incorrect becaus because    e Unit Unit 44 is is inin aa 72 72 hour 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 00W CCW pumppump andand thethe action action statem statement ent time time cancan be be extend extended    ed to to 3030 days days (for (for aa CCW CCW pump)          40 4KV pump) ifif 4D    4KV BusBus isis realign  ed to realigned    to 4A4A 4KV4KV Bus.
Bus.
o.
D.      Incorrect Incorrect becaus because    e Unit Unit 44 isis inin aa 72 72 hour hour action action statem statement    and the ent and    the action action statem statement ent time time cancan be be extend extended    ed ifif 4D 40 4KV 4KV Bus Bus isis realign realigned    to  4A ed to 4A 4KV  4KV Bus.
Bus.
Plausib    le  becaus Plausible because        e 77 days days isis the the correct correct action action statem statement    time for ent time    for aa 00W CCW pump.
pump.
160 160
 
NRC DRA D k
1  FTR FT                            07/24/077 07/24/0
  #81 Q#81 Q
Unit 3 is at 100% powepowerr when a loss of all  aN feedw feedwa  ter event occurs.
ater As the crew transi transittions ions from 3-EOP-E-0, the STA informs them a red path exists on Heat Sink.
The opera operato  rs succe tors  successsfully sfully initiate bleed and feed.
Which ONE of the following descr    describ  es the report ibes      reportaability bility of this event event?  ?
The event must be report reporteedd to the:
A.      NRCOC within 4 hours  hours..
B.      NRC Resid Reside  ent nt within 4 hours hours..
C.      State of Florid Florida a within 15 minut minuteess and to the NRC immeimmed    iatelyy following diatel State notific notification.
ation.
D.      State of Florid Floridaa within 1 1 hour and to the NRC imme  immed  iatelyy follow ing State diatel notific notification.
ation.
REFE REFER  RENC ENCE  E PROVIDED 161
 
NRCDRAFT NRC        DRAFT                                  07/24/07 07/24/07
    #81 QQ#81 ANSWER:
ANSWER:          CC KA:
KA:              WW/E05    G2.4.30
                    /E05G2.4.30 As  it relates As it relates toto Loss Lossof  ofsecondary secondaryHeat HeatSink:Sink: Knowledge Knowledgeof    ofwhich whichevents eventsrelated related toto system    operati  ons/sta  tus system operations/status should be  should    be reported reported toto outside outside agencies.
agencies. 2.2/3.6 2.2/3.6 10CFR55:
10CFR55:          43.b.5 43.b.5
 
==Reference:==
 
==Reference:==
0-EPIP-20101, 0-EPIP-201        01, Enclosure Enclosure 1,1, Category Category 5,5, Item Item C.3 C.3 0-EPIP    -20101 0-EPIP-201 01,, CAUTIONS CAUTIONS before    before Step Step 5.6.1.11 5.6.1.11 Cog Level:
Cog    Level:    1I Recall Recall New Question New    Question Provide EPIP-20101 Provide      EPJP-20101 Enclosure Enclosure 1I 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  s  and 15 minutes and to    to the NRC immediately immediately following following State notification notification inin accordance with accordance        with 0-EPIP-201 0-EPIP-201 01, "Duties Duties of the Emergency Emergency Coordinator."
Coordinator.
Plausible becaus Plausible  because    e notification notification to the NRCOCNRCOC lAW ADM-115                required ADM-1 15 is require      d in in the the event event of of the the occurr  ence of signifi occurrence                  cant events as defined in 10CFR significant                              10CFR50.      72.
5O.72.
B.
B.      Incorre  ct becaus Incorrect  because  e the event event must be reportereported d to the State State of of Florida Florida within within 15  minute  s 15 minutes and and  to the  NRC NRC immed        iately follow immediately      following    State notific ing State  notification ation inin accord  ance with accordance        with 0-EPIP    -20101, Dutie 0-EPIP-20101,        "Duties s of of the the Emerg Emergency    Coordinator."
ency Coord  inator.
Plausib  le becaus Plausible  because  e notific  ation to notification  to the the NRC NRC Reside Resident    lAW ADM-nt lAW    ADM-115 1 15 isis require d in required  in the the event event ofof the the occurr    ence of occurrence      of signifi significant  events..
cant events C.
C.      Correc Correctt per per the the referen referencece D.
D.      Incorre ct becaus Incorrect  because  e the the event event must must be  be reporte reportedd toto the the State State of of Florida Florida within within 15 15 minute minutes s and and to to the the NRC NRC immed        iately follow immediately      following    State notification ing State notification in  in accord  ance with accordance        with 0-EPIP    201 01, 0-EPIP-201    01, Dutie "Duties s of ofthe the Emerg Emergency    Coordinator."
ency Coordi    nator.
Plausib  le becaus Plausible  because  e the the 11 hour hourtime timeframe frame applies applies to to NRC NRC notific notification  and ation and certain  other    notific ations  describ  ed certain other notifications described inin 0-ADM    0-ADM-115.
1 15.
162 162
 
NRC DRA FT                                    07/24/077 07/24/0 Q #82 0#82 Unit 3 is at 50% power with control Bank "0"      D at 180 steps as I&C invest investiigates gates a powerr cabin powe      cabineett non-u non-urrgent gent failure alarm alarm..
A momentary powe  powerr interruption in the 2BO2BD power cabin cabine ett control power circuitry causess all 3 of the Bank "0" cause                          D group 2 rods to drop 140 steps into the core where they are gripped and held norma  normallylly by the statio station ary grippers being re-ene nary                    re-enerrgized gized..
The US should direct the opera  operato  rs to; tors A.      Verify rod control is in AUTOMATIC and reduc      reduce e turbin turbine e load using 3-0NO 3-ONOP-100, "Fast Fast Load Reduc Reduction, tion", to lower Tref to within 3&deg;F of Tavg.
B.      Verify rod control is in MANUAL and reduc    reduce  turbine e turbin  e load using 3-0NO 3-ONOP-100P-100,,
Fast Load Reduc "Fast          Reduction, tion", until all Bank "0" D rods are aligne aligned d within 12 steps C.      Manuaally Manu    lly trip the reacto reactorr,, verify the reacto reactorr is trippe trippedd,, perfor performm 3-EOP-E-0 and stabili stabiliz zee the plant using 3-EOP-ES-0-ES-0..1.
1.
D.
O. Manuaally Manu    lly trip the reacto reactorr,, verify the reacto reactorr is trippe trippedd and Emergency Borate per 3-0NO 3-ONOP-046 P-046..1.
1.
163
 
NRC DRA NRC        DRAFT                                    07/24/0 07/24/077 Q #82 Q#82 ANSWER ANSW      ER::      CC KA:
KA:                  000003G 00000    3G.2..2.4.
4.66 As itit relate As      relates    to the s to  the dropp dropped      controll rod ed contro      rod event:
event: Know Knowledledge ge of of sympt symptom om based based EOPEOP mitigation mitiga          strategies tion strate      gies.. 3.1/4.
3.1/4.0  0 IOCFR5 10CF    R55: 5:      43.b.5 43.b.5 Referenc Refer  ence: e:      3- ONOP ONOP-02  -028.38.3,, Step 1I 3-EQ P-E-3-EOP    -E-0,0, Step Step 1, 3-EOP-ES 3-EOP    -ES-0 -0.1,
                                          .1, Step 5 Level: 2 Comp Cog Level:                Compreh rehenensio sionn The SRO must  must recogrecogniz nizee that even thoug  though  h the dropp dropped ed rods did not fully insert reactorr trip is requir                                                                                    insert a reacto                required.ed. He then must  must analyz analyze e that the contro controll rods that were dropped dropp    ed initially wouldwould still be trippa trippable ble as they were re-grip re-grippepedd by the statio    nary stationar  y grippers grippe    rs and should should be free to fall on the trip. He then must              must under understan stand d that the EOP netwonetwork  rk only addre addresses sses rods that do not fully insert    insert on a trip by emerg borating                                                                                              emer    ency genc  y borati        using ONOP ng using      QNQP-46  -46.1,
                                      .1, dropp dropped ed rods are not addre  addressed ssed unless unless they fail to insert.
insert.
Question New Quest        ion
 
===Response===
Respo            Analysis:
nse Analy      sis:
A.          Incorrect Incorr        because ect becau      se the reacto reactorr would be manu    manually ally tripp trippeed.
: d. Plaus Plausible ible becau because  se Tavg is restor restoreded to Tref by borati borating ng and reduc reducinging turbin turbine e load in ONOP ONOP-28  -28.3.3 which is used for dropp which                      dropped  ed rod recove recovery ry.. ONOP ONQP-02  -028.3 8.3 requir requireses the Rod Control Contr        Selector ol Selec        Switch to be placed tor Switch              placed in MANUAL.
B.        Incorrect Incorr        because ect becau      se the react reacto orr would be manu  manually ally tripp trippeed.
: d. Plaus Plausible ible beca becau  usese Tavg is restorestorred ed to Tref by bora  borati ting ng and redureduc cing ing turbi turbinnee load in ONQONOP    -28.3 P-28.3 whic which  h is used for drop  dropp  ped ed rod recorecove very ry..
C.        Corr Corre ectct as the eveneventt desc descrribed ibed was multiple drop    dropp    ed rods that were ped relat relatch cheded by the norm norma  all oper opera ation tion of the stati statioonar naryy gripp grippe  rs, they shou ers,        shouldld still be tripp trippa  able ble and fully inserinsertt when the man  manu  ual al trip is orde ordere  d. The EOP red.          EOPs  s only addr addre  ess ss rods that are stuck out of the core          core..
D.        Inco Incorr rrect ect beca becau  use se the EOP EOPs  s only addr addre essss stuck rods and these rods shou      should ld still inser insertt on the reactreacto  orr trip. Plau Plaus sible ible beca becauusese the step in ES-0.1 ES-0.1 direc directtss the oper opera  ator tor to Eme Emerg  rgenency cy Bora Borate  te usin usingg 3-ON 3-0NO  OP-0 P-046  .1 to com 46.1      comp    ensat pens  atee for any stuck rods  rods..
164 164
 
NRC DRAFT                                    07/24/07 07/24/0 7 Q #83 Q#83 Operators Opera tors are increa increasing sing Unit 3 power to 100%  100%..
* powerr at 95% power With powe              power,, annun annunciat    or B 9/3, SHUTDOWN ciator                DOWN ROD OFF TOP /
DEVIATION, DEVIA  TION, alarm alarms.s:
* The RO report reportss that control rod rod H-8 H8 (0(D Bank) has stopp stopped ed moving and is now 14 steps lower than other other 0D Bank control rods.
* Subseque Subse      nt invest quent  investiigation gation revea revealsls H-8 is stuck and untrip untripp able..
pable Which ONE of the follow following descr describes ibes the Tech Spec requirrequire d opera ed  operator tor response and the basis for the action action??
A.      Place Unit 3 in Mode 3 within 6 hours Place                                  hours to ensur ensure  adequate e adequ  ate Shutd Shutdowown n Margi Margin n
requirem requir emenents ts are met.
B. Place Unit 3 in Mode 3 within 6 hours Place                                  hours to reduc reducee the effect of the stuck rod on subseque the subse  quent nt Xenon Oscill Oscilla  tion.
ation.
c.
C. Declare Decla          inoperab re H-8 inope        le and reduc rable        reduce    powerr to <
e powe      < 75% within 1  1 hour, confir confirm m all Bank "0" D rod positio positions are within 2:.+/-  12 steps  of each other other to ensur ensure e adequate adequ        Shutdow ate Shutd  own  Margin n Margi    requirem n requir  emenents ts are met.
D. Declare Decla          inoperab re H-8 inope      le and reduc rable      reduce    powerr to <
e powe      < 75% within 1  1 hour, confir confirm m all D rod positio Bank "0"          positions ns are within 2:.+/-  18 steps  of each  other to reduc other    reducee the affect of the stuck rod on the subse subsequequent nt Xenon Oscill Oscilla tion.
ation.
165 165
 
NRC DRA NRC      DRAFT                                  07/24/0 07/24/07 7
Q#83 Q#83 ANSWER ANSW      ER::      AA KA:
KA:                  000005G 00000          .2.2.
5G.2. 22 2.22 As itit relate As      relates    to the s to    the Inope Inoperab    le/St rable/    uck Contr Stuck  Controlol Rod:
Rod: knowl knowledg edgee ofof limitin limitingg condit  ionss condition for opera for operationtionss andand safety safety limits.
Nmits. 3.4/4.1 3.4/4.1 IOCFR5 10CF    R55:5:      43.b.2 43.b.2 Referenc Refer  ence:e:      3-ONOP-0 3-0NO        P-02828,, Step 5.1.4.
5.1.4.22 Tech Spec 3.1.3.1  3.1.3.1 Action Action a.
O-ADM-536, 0-ADM        -536, Sectio Section  n %.1.3
                                                    %.1.3 Level:
Cog Level:              Recalll 1I Recal New QuestQuestionion
 
===Response===
Respo          Analysis:
nse Analy      sis:
A.        Correct Corre  ct per the referereference nce..
B.        Incorrect Incorr        because ect becau            Xenon Oscill se Xenon      Oscillatio ations ns are not the basis for the requir  requirem emenentt to MODE 3 in 6 hours be in MODE                  hours.. Plaus Plausible ible becau because se the reacto reactorr must must be placed placed in MODE 3 with MODE          within in 6 hours hours.. Misali Misaligne gned d rods could could be an initiati initiating ng event event for Xe oscillatio oscilla  tionsns which which do challe challenge nge the powe powerr distrib distributi ution on limits.
C.        Incorrect Incorr        because ect becau        se the unit must must be placed placed in ModeMode 3 with within in 66 hour hourss..
Plau Plaus sible    because ible becau        se the rod musmustt be declar declareded inope inoperab rable le and reduc reducing ing power power to <75% wou  would  ld be a correc correctt response if the rod was tripp  trippaable.
ble. Reduc Reducinging powerr using powe      using bora boratition on wou wouldld increa increasese shut shutddow own n margi margin.n.
D.        Incorrect Incorr  ect beca becau  use se the unit musmustt be place placed d in Mod Mode e 3 with within in 66 hour hourss and Xeno Xenon  n oscil oscilla  latio tions ns are not the basis basis.. Plau Plaus  ible beca sible  becau  se redu use  reduc  ing pow cing  power er to
          <75% and conf    confir irmi ming ng all rods in the bank are within 18      18 steps wou would    reduc ld redu  cee peak peakiningg facto factorrss and wou wouldld be aa corre correc ctt response if the rod were not untri untripppab pable le..
166 166
 
NRC DRA NRC        DRAF      FT T                                07/24/0 07/24/07 7 Q#84 0#84 Unit 44 isis at Unit          at 80%
80% powepowerr during during endend of of life life (EOL)
(EOL) powepowerr coast coast downdown opera      tion..
operation The auto The  auto functi functionon ofof the the maste masterr charg charginging pump pump contro controllellerr fails fails causin causing  g Charg Charging ing pump speed pump      speed to  to go go toto minim minimumum..
**  Operators Opera              respond tors respo    nd and and take take manu manual      controll of al contro      of Charg Charging ing pump pump speedspeed..
**  Tavg is Tavg      is being being allowe allowed    to "droop d to  droop" to to maint maintain ain the reacto reactorr critica criticall and and isis prese prese ntly 3&deg;F BELO 3&deg;F      BELOW  W Tref as  as direct directed      by ed by React Reactor  or Engin Engineereering ing..
Which ONE of Which              of the follow following    identifies ing identif    ies the press pressurize urizerr level level that should should be be maintaine maint  ained  d and the basis basis for maint maintaini ainingng that level.
level.
Pressuriz Press  urizer er level should should be:
A.        44%.
44%.
Pressuriz Press          er level progra urizer          program          determine m is determ        ined d by reacto reactorr power power to ensur ensure  e that the steam volumvolume  e in the pressurize urizerr is smalle smallerr at highe higherr powe powerr to preve prevent nt a high level reacto reactorr trip follow followinging a 100% load rejecti    rejection.
on.
B.        44%.
44%.
Pressuriz Press          er level progra urizer          program  m is determ determine  inedd by Tavg to ensur  ensuree that the water water volu volum  mee in the press pressurize urizerr is highe higherr at highe higherr tempe temperatu ratureress to preve prev    nt the ent pressurize press    urizerr heaters from uncov  uncoverin ering  g durin during  g a 10% step increa  increase  se in turbi turbinnee load.
load.
C.      47%
47%..
Pressuriz Press          er level prog urizer          prograramm is deter determ  mine ined d by react reacto  orr pow powe  err to ensu ensurree that the steam volu  volum mee in the press pressurize urizerr is high enou  enoug ghh at anyany powpowe    r er level to prevpreve  nt ent wate waterr relie relieff throu throug  ghh the safet safetiieses on aa 50% load rejec    rejecti  on.
tion.
D.      47%
47%..
Pres Press  suriz  er level prog urizer          prograram m isis deter determ mine ined d by Tavg to ensu    ensurree that the wate  waterr volu volum  mee in in the press pressurize urizer  r at at any any powpowe  err level level is is high enouenoug  ghh to prev preve    nt ent requ requir iring ing aa safet safety y injec  tion injecti  on follo  wing follow  ing aa react reacto orr trip.
trip.
167 167
 
NRC DRA NRC        DRAFT                                      07/24/0 07/24/077 Q #84 Q#84 ANSWER:
ANSW    ER:        B B
KA:
KA:                000028AA2.
8AA2.08 08 Able to determ Able      determine      and interp ine and    interpret  the follow ret the    following ing asas they they apply apply to to Press Pressuriz urizer er Level Level Malfun Malfu    ction:: PRZ nction        PRZ level level as as aa functio functionn of power power level.
level. 3.1/3.
3.1/3.55 IOCFR 10CF    55:
R55:          43.b.5 43.b.5 Referenc Refer ence:  e:      4-ONOP-041 4-0NO      P-041.6,.6, Step Step 4.2 &    & Enclo Enclosur suree 1, SD-009 pages SO-00      pages 8&9 Cog Level: 3 Applic    Application ation / Analy Analys sisis Level 3 becau because  se the SRO must  must recog recogniz nizee that the autom automati aticc pressurize urizerr level control system system would have been      been maint maintaaining ining level lower based based on the lower than normal Tavg for the present powe        powerr level. He must    must calcul calculate ate the progra programmmmed  ed pressurize urizerr level for the given plant conditions and relate            relate that Tavg is being maintaine maint ained  d at 3&deg;F below Tref and that prz          Prz level refere reference nce signal is genergenerated ated from Tavg and not from power    power.. Tref at 80% power    power would norma  normally lly be 568.6 568.6&deg;F&deg;F which demand would dema      nd 47% press pressurize urizerr level but since Tavg is 3&deg;F low, the requir        require edd pressurize urizer  r  level  would be 44%. Calcu  Calcullation:
ation: 22% to 53% level. 80% X 31 %
program progra  m level span =      = 25%. 25% +      + 22% =    = 47% for 80% power    power but Tavg is not on program progra  m so the press pressurize urizerr level must must be maintmaintaine ained d at 44% to equat equate  e to the 565.6&deg;F 565.6 &deg;F Tavg.
New Quest Question  ion
 
===Response===
Respo          Analyssis:
nse Analy        is:
A.      Incorre Incorrect  ct beca becau  use se prz Prz level is aa function of Tavg and aa high level react          reacto  orr trip will be gene generrated ated from a com  comp  plete lete load rejecti rejectio on.
: n. Plaus Plausible ible beca becau  se the use level is base based d on Tavg and is corre    correc ctt for the curre curren ntt Tavg.
B.      Correc Correct. t.
C.      Incorre Incorrect  ct beca becau use se press pressurize urizerr level level is is aa function of of Tavg and aa high steam volume would be aa caus      cause  e of the heaters uncove uncovering.
ring. A high level react  reacto orr trip will will be genegenerrated ated befo beforere wate waterr relief throu throug ghh the safet safety y valves. Plau Plaus  ible sible beca becau  use se the level is correcorrecctt for the curre curren ntt react reacto orr pow powe  err and wate waterr will not not be relea releassed ed throu throug ghh the safet safety y valv valves es..
D.
O.      Incorre Incorrect  ct beca becau  use se press pressurize urizerr level should should be 44%. 44%. PlauPlaus  ible beca sible  becau  se the use level level is is corre correc ctt for the curre curren ntt react reacto orr pow powerer and thethe level is is main mainttaine ained    high d high enou enoug  ghh to notnot require require aa SI SI following aa reactreactoorr trip.
trip.
168 168
 
NRC DRA NRC      DRAF  FT T                          07/24/0 07/24/07 7
Q#85 0#85 With reacto With    reactorr powe powerr at at 80%,
80%, PRMS PRMS-R-    1 5 alarm
                                              -R-15  alarmss and and count count-rate
                                                                          -rate increa increases ses rapidl rapidly y
and stabili and    stabilizes  at 5,000 zes at  5,000 cpm.
cpm.
Operators Opera          enter 3-0NO tors enter  3-ONOP-0    71.2, P-071  .2, "Steam Steam Gene Generator Tube Tube Leaka Leakage, ge," and and attem attempt to quan  tify quantify thethe leakag leakage    using the e using  the R-15 R-1 5 Prima Primary  to Secon ry to  Secondardary y Leak Leak Rate Rate  Graph Grap    h in the in  the Plant Plant Curve Curve Book.
Book.
Unit 33 Cond Unit      Condens enserer air air in-lea in-leakag kagee is consta constant  at 7 scfm.
nt at    scfm.
All of the S/G All          S/G tube leaka leakage is comin coming  g from the 3B S/G.
Which ONE of the follow Which                    following  describes ing descr        Technical ibes Techn  ical Speci Specifica ficatio tionn implic implicati ations ons..
The RCS prima primary      secondar ry to secon  daryy leakage has:
A.        NOT excee exceeded          Tech. Spec.
ded the Tech.      Spec. limit.
B.              exceeded NOT excee                Tech. Spec.
ded the Tech.      Spec. limit. Howe However ver,, be in Mode Mode 3 in:s; in 24 hours hours..
C.        exceeded excee            Tech. Spec.
ded the Tech.      Spec. limit. Be in ModeMode 3 in :s; 11 hour.
hour.
D.        exceeded excee            Tech. Spec.
ded the Tech.      Spec. limit. Be in ModeMode 3 in :s; 6 hours hours..
REFERE REFE    RENCNCE  PROVID E PROV    IDEDED 169 169
 
NRC DRA NRC          DRAF      FTT                                      07/24/0 07/24/07 7 Q #85 Q#85 ANSWER ANSW      ER::      CC KA: 00003 KA:      000037G  7G2.12.1.33.33          As itit relate As        relates  s toto Steam Steam Gene  Generator rator Tube Tube Leak:  Leak: Ability Ability to to reco gniz  e recognize indica indication tionss forfor system system opera operatingting param parameteeters  rs which whic  h  are are  entry-entry    level
                                                                                                                        -leve  l condition condit  ionss forfor techn technicalical specif specifica icationtions s.. 3.4/4.
3.4/4.0  0 10CFR5 10CF    R55: 5:      43.b.2 43.b.2 Refe  renc
 
==Reference:==
e:      3-ON 3-0NOOP-0  P-071  71.2,
                                              .2, Step Step 7,  7, 9A 9A TS 3.4.6.
TS    3.4.6.2.c2.c PCB Sectio PCB      Section      5, Figure n 5,  Figure 15,  15, Unit Unit 33 R-15 R-1 5 Prima Primary  ry to to Secon Secondar    daryy LeakLeak Cog Level:
Cog    Level:        33 Applic Applicat    ion 1/ Analy ation      Analysis sis Level 33 becau Level        becaus    see the the opera operator      must locate tor must        locate the correccorrectt point point on on the R-15 R-1 5 curve, curve, read read the value value from the    the curve curve (which (which is  is less less than the TS      TS limit) limit) and and then then    relate relat  e  the  air  in-in-leakage leakag    e to the needneed to multipmultiply ly the valuevalue by  by 7. Then the opera the multip                                                                                      oper    tor must ator    mus    t  comp com      are pare multiplieliedd value value to the TS limit    limit of 500 gpd and determ        determine  ine the TS limit  limit has been exceeded excee  ded.. The opera  operator        mus tor mustt then recall  recall the guidaguidance  nce of ONOP ONOP-07  -071.2 1 .2 to be in Mode 3 within Mode        within 11 hour which  which is more restric    restrictiv tivee than the TS limit of 6 hours        hours..
Question New Quest        ion Examiner note:  note: ONOPONOP 71.2 and TS have been frozen                    frozen earlie earlierr revisio revision. n.
5000 cpm =      = 122 gpd from graph      graph.. Multip Multiply  ly 122 X 7 scfm =          = 854 gpd which TS limit of 500 gpd from one S/G.                                                                              whic    h excee exceeds    ds Prov Proviide de PCB Sectio    Section            Figuree 15 as a refere n 5, Figur                        referen  nce ce Respon Respo    nsese Anal Analyysis:sis:
A.        Inco Incorr rrect ect bec becau ausse e S/G tube leaka    leakag  gee has exceexcee      ded the Tech eded          Tech.. Spec Spec.. limit and the unit mus  mustt be in Mod    Mode  e 33 in s; 11 hourhour.. PlauPlaus    ible bec sible    becauausse e ifif the curv curve  e is read direcdirecttly ly with withou outt mult multipiplyi  ng by 7, lying          7, the S/G tube leaka    leakag gee will not  not have have exce excee  eded ded the Tech Tech.. SpecSpec.. limit limit..
B.
B.        Inco Incorr rrect ect bec becauausse  e S/G tube leaka    leakag  gee has has exce excee      ded the eded      the Tech Tech.. Spec Spec.. limit limit andand the the unit unit musmustt be be inin Mod Mode e 33 in in s; 11 hour hour.. PlauPlaus    ible bec sible      becau aussee ifif the the curv curve  e isis read read direc direct tly ly with withou outt mult multipiplyi lyingng byby 7, 7, the the S/G S/G tube tube leaka leakag gee will will not not havehave exce excee  ededded the the Tech Tech.. SpecSpec.. limit limit and and 66 hour hours s isis the the time time iden identif tifiedied byby Tech Tech..
Spe Specs cs to  to go go from from Mod        e Mode I1 to  to ModMode  e 3.3.
C.
C.      Corr Corre  ect ct per per the the refer refere  ence nce D.
D.      Inco Incorr rrect ect bec becau ausse e the the unit unit mus must  t be be in in Mod Mode  e 33 inin s; 11 hour hour.. Plau Plaus    ible bec sible    becau ausse  e S/G    tube S/G tube leakageleaka    ge has has exce excee  eded ded the the Tech Tech.. Spec Spec.  . limit limit whic which      allows h allow      s  66 hrs hrs    to to HSB HSB..
170 170
 
NRC DRA NRC        DRAF    FTT                                  07124/0 7 07/24/07 Q #86 Q#86 Unit 33 isis at Unit            at 100%
100% powepower      with the r with    the 3A 3A Norm Normal  al Conta Contain inmen mentt Coole Cooler  r (NCC (NCC)  ) out out of of service servic  e on  on aa cleara clearan    ce  (ECO nce (ECO).). The    The 3B 3B NCC NCC subse subseq  quent uentlyly trips.
trips.
Which ONE Which        ONE of  ofthe the follow following    describ ing descr    ibeses the the effect effect on on RCP RCP opera operati  tion on and and thethe correc correctt operato opera        r  resp tor response?  ons  e?
A.
A.        RCPRCP stator stator tempe temper    atures rature      will start s will  start to to rise.
rise.
If  stator tempe If stator      temper    atures rature      exceed s excee      248&deg;F,, trip d 248&deg;F      trip the the reacto reactor,r, transi    tion to transition    to 3-EOP-E-O, 3-EOP        -E-0, "Reac Reacto  torr Trip Trip or or Safety Safety Injecti Injection, on," and and stop stop allall RCPs RCPs..
B.
B.          RCP stator RCP        stator tempe temper      atures rature      will start s will  start to to rise.
rise.
If stat If stator  or tempe temper    atures rature      exceed s excee      248&deg;F,, conta d 248&deg;F      contact ct the the Electr Electrica icall Maint Mainte enanc nancee Superv Super        isor as visor    as direct directed ed byby 3-0NO 3-ONOP-0  P-0-4-411.1,
                                                                        .1, "Reac Reacto torr Coola Coolant  nt Pump Pump Off-Off-Normal,"
Norm      al, for for autho authoriz    ationn to rizatio    to contin continuuee RCP RCP opera operati tions ons above above 248&deg;F248&deg; F..
C.
C.        RCP pump RCP        pump bearin bearing      temperrature g tempe      atures s will start start to rise.
rise.
IfIf bearin bearing      temperrature g tempe      atures    exc s excee eed  225&deg;F,, trip the reacto d 225&deg;F                  reactor, r, transi  tion to transition 3-EOP-E-0, 3-EOP        -E-0, "Reac Reacto  torr Trip or Safety Safety Injecti Injection, on," and stop all RCPs    RCP5..
D.      RCP pump  pump bearin bearing    temperrature g tempe      aturess will start start to rise.
bearing If bearin        temperrature g tempe      atures      exceed s excee    d 225&deg;F 225&deg;F,, conta contact ct the Electr Electricaicall Maint Mainte  enanc nancee Supervvisor Super        isor as direct directed        3-ONOP-0 ed by 3-0NO        P-0-4-411.1,
                                                                        .1, "Reac Reacto torr Coola Coolant  nt Pump Pum  p  Off-Off Normal,              authoriz al," for autho        ation to contin rizatio        continu uee RCP operaoperati tions ons above above 225&deg;F225&deg;F..
171 71
 
NRC DRA NRC        DRAF      FTT                                      07/24/0 07/24/07  7 Q #86 Q#86 ANSWER ANSW      ER::        AA KA: 003A2 KA:        003A2.    .0303 Ability Ability toto (a)
(a) predic predictt the the impac impacts ts ofofthe the follow followinging malfu malfun      nction ctions  s oror ope operarati  ons on tions      on the the RCP; RCP; and and (b)(b) based based on on those those predic predicttions, ion  s, use use  proce pro    ced dures ure    s to to correctt,, contro correc        control,    or mitiga l, or  mitigat  tee the the conse conseq    uences quenc    es of of those those malfu malfun  nction ctions s or  or opera operati  tions:
ons:
Pro blem Proble    mss assoc associat    ed with iated    with RCPRCP motor motorss,, includ includinging faulty faulty motor mo      s tors  and and  curren cur    ren t, t, and and winding windin        and bearin g and      bearing    temper g tempe        ature proble rature      problem ms. s. 2.7/3.1 2.7/3.1 100FR5 10CF  R55:  5:      43.b.5 43.b.5 Referen Refer  ence: ce:      3-ONOP-041 3-0NO      P-041..1,  1, Step Step 44, 44, FO ED pagepage StepStep 11 && 55 SD-29,, Page SD-29        Page 10  10 and and Fig.
Fig. 11 Cog Level:
Cog    Level: 22 comp    compre    hension rehen    sion - LevelLevel 22 becau becaus    see the the SRO SRO must  must recog recogni    nizeze that that NC NCCs Cs provid providee coolin cooling    to  the g to the RCP  RCP motormotor comp compar  artme tmentsnts  thereb ther  eby  y  coolin cool  ing g    the    stator stator and not and    not thethe pump pump bearin bearing  gs.s. HeHe then then must must underunderst stand and that that  two two    NCCs NC  Cs    canno cannott maintai maint  ainn the contacontain    ment ambie inmen      ambient      temperrature nt tempe      ature const constan  antt at full power power,, and that an            an increas increa    see inin conta contain      ment tempe inmen      temperratureature will cause cause an  an increa increas  see in the stator stat    or temperrature tempe      atures  s of the RCPs RCPs,, he then must    must recall recall the thresh thresho  old ld  tempe tem    per rature atur      e to take take action and the correc action                  correctt action action to take,take, New Quest New    Questio    ionn Respon Respo    nsese Analy Analysi    s:
sis:
A.        Correct Corre    ct per the refere referen    ce.
nce.
B.
B.        Incorreect Incorr    ct becau becausse  e If stat statoror tem tempeperrature aturess exc  exceeeedd 248&deg; 248&deg;F  F,, ope opera ratotorsrs shoshould uld trip the reac    tor, reactor, tran      sitio transi  tionn to 3-E 3-EOP OP-E-
                                                            -E-0,0, Re "Reac actotorr Trip or Saf Safetyety  Injecti Injec        on,"
tion,      and..
and stop all RC  RCPs  Ps.. Pla Plaususib  le bec ible  becau ausse e RCRCP  P stat statoror tem tempe perrature atur  ess  will    startt to rise star and 248 248&deg;F&deg;F is the tem  tempe perrature ature requ requiriring ing ope opera    tors rato  rs to take acti  action on.  . Also the    the Ele Electrctriical cal Sup Super ervvisor isor maymay authautho oriz rizee ope operaratition on inin exc exces esss of of limit limits  s    for  stator stat    or tem tempe perrature ature ifif the auth autho  oriz  ationn is rizatio    is giv givenen bef before      startin ore star    tingg the the RC RCP. P.
C.
C.        Inc  orreect Incorr    ct bec becau aussee RCRCP  P pum pump  p bea  ringg tem bearin      tempe perrature aturess areare depdepen enddent ent upo upon  n COW CCW con  conditditiions, ons, not not thethe run    ningg of runnin      of NCC NCCs  s.. Pla Plaus  ible usib      becau le bec    aus see    if if  the the    pump pum      p bea  ringg tem bearin      tempe  perrature aturess incrincreaeassee to to >> 225 225&deg;F&deg;F,, the the ope operaratotors rs  should sho  uld      trip trip  the the reac reactotor,r, got got toto EO  P-E-0 EOP-E    -O andand stop stop RO RCPs  Ps..
D.
D.        Inc Incorrorreect ct bec becauaussee RORCP  P pum pump  p bea bearin ringg temtempe perrature aturess are are depdepenenddent ent upo  upon  n COW CCW con        ditiions, condit    ons, notnot the the run    ningg of runnin    of NOO NCCs    s.. Pla Plaus usibible  becau le bec    aus  se e    if if  the the    pump pum    p bea bearinringg tem tempe perrature aturess incrincreaeasse, e, 225 225&deg;F&deg;F isis the the tem tempeperrature ature requ requir    ing ope iring      opera  ratotors rs to to take take acti    on..
action 172 172
 
NRCDRA NRC          DRAF    FTT                                    07/24/0 07/24/077 Q #87 Q#87 Operato Opera  torsrsareareperfor perform  ming ing3-EOP 3-EOP-ECA--ECA-1  1.1, .1,"Loss LossofofEmer Emerg gency encyCoola Coolant nt Rec Recircircu lation, ulation        in  resp    ons  e
                    ," in response totoaaLOCA        LOCAand    andfailure failureofofbothboth RHR RHRpump  pumps. s.
Asdirect As  directed ed by  by3-EOP 3-EOP-ECA-  -ECA-1      .1, both both Conta 1.1,            Contain    ment tSpray inmen      Spraypump  pumps  s (CSPs      ) have stop ped stopped.  .                                                                                              (CSP5)      have been been The STA The    STAsubsesubseq      uently quent          reports ly report        an Orang s an    Orange  e path path onon Conta Con inmen tainmentt pressu pressure. re.
Which ONE Which      ONE of  ofthe the follow followi    ng descr describ    es the ing            ibes    the correc correctt opera operato  torr respo respons nsee and for the  acti for the action?  on?                                                                                            and thethe basis basis A.
A.        Continu Contin    uee perfor perform      ing ECA-1 ming      ECA-1.1.  .1.
Mainta Maint      in  CSP      s ain CSPs stopped instop    ped    in accor accord    ance with dance      with thethe guida guidan  ncece ofof ECA-1 ECA-1.1.
Maximizes Maxim      izes availa availabbility ility of of the the RWST                                                          .1.
RWST invent invento oryry for for injecti injectio onn flow.
flow.
B.
B.        Continu Contin    uee perfor perform      ing ECA-1 ming      ECA-1 .1. .1.
Sta Start rt CSPs CSPs in    in accor accord    anc  e dance with with the the guida guidan  nce ce ofof FR-Z.
FR-Z.1  1..
Contain Conta        ment barrie inmen        barrierr protec protecttionion isis aa highe higherr priorit priority y than injecti injectioonn flow flow as as long as RWST as  RWST level  level is >> 60,0060,000      gallons                                                              long 0 gallon    s..
C.
C.      Transitition Trans      ion to to FR-Z.
FR-Z.1    1,, "Resp Respo      nse to High onse          High Conta Contain  inmen ment Press Pressuure." re.
Sta  rt  CSP    s  in Start CSPs accordance  acc    ord  ance withwith the guidaguidan  nce ce of FR-Z.
FR-    1.
Z.1 .
Contain Conta        ment barrie inmen        barrierr protec protecttion ion is aa highe higherr priorit priorityy than injecti injectioon  flow as n flow        long as lon g as  RW    ST    leve as RWST level > 60,0    l  is    60,00  000 gall gallononss..
D.
D.      Tra nsitition Trans    ion to FR-  FR-Z. Z.11,, Re    spo  nse to Hig "Resp    onse          High h Con Conta    inmen tain  ment Pre Press ssuure."
re.
Ma  inta in Maintain CSPs CSP      s stop stoppepedd in acc accorord  anc dance  e wit with  the gui h the    guidadannce ce  of  ECA-1 of ECA-1 .1.  .1.
Ma  ximizes Maxim    izes ava      ilabbility availa    ility ofof the the RWRWST  ST inv inven ento tory  for inje ry for    injecti ctioon  flow..
n flow 173 173
 
NRC DRA NRC          DRAF    FT T                                  07/24/0 07/24/077 Q#87 Q#87 ANSWER ANSW      ER::      0D KA:
KA:                    006G2.4.6 006G    2.4.6 As itit relate As        relates    to Emer s to  Emergen  gency  cy Core Core CoolinCooling:      Knowled g: Know      ledge ge of of sympt symptom om based based EOP  EOP mitig  ation mitigation strate strategies gies.. 3.1/4.
3.1/4.0 0 IOCFR5 10CF    R55: 5:      43.b.5 43.b.5 Referenc Refer    ence: e:      3-EOP-EC 3-EOP      -ECA- A-1    .1, Step 1.1,    Step 88 3-EOP-FR 3-EOP      -FR-Z  -Z.1
                                            .1,, CAUT CAUTION  ION PriorPrior to Step 8 Cog Level:
Cog    Level: 33 Analy  Analysis sis Level 3 becau Level        because  se  the    situation situati              require on will requir        e the SRO to analyz  analyze  e comp competin etingg priorit    ies priorities for the remai remaining      RWST injecti ning RWST            injection    water and determ on water              determine  ine that even thoug  thou  ghh  a  highe higherr priority priorit      procedur y proce    duree (FR-Z (FR-Z-1)      would start the CSPs
                                        -1) would                      CSPs the EOP mitiga    mitigating ting strate strat    gy egy    to follow is to conse follow            conserve rve the RWST  RWST inven  inventorytory to protec protectt the core.
core. The SRO must        mus    t understan under    stand  d that a transi transition          FR-Z.1 is requir tion to FR-Z.1                requireded but that a cautio caution  n in FR-Z.1 FR-Z    .1  states states that the CSPs CSPs shouldshould be opera  operated ted iaw the requir  requirem emen ents ts of ECA-1 ECA-1 .1.  .1. The SRO must relate must      relate the plantplant condit conditionionss and determdetermine  ine that maint maintaini aining ng the reducreduced ed injec  tion injection      flow    estab  lishe lished d in ECA-1 ECA-1 .1  .1 is more of a priorit  priorityy than runnin runn  ingg  the  CSPs CSPs under these condit under                conditionionss even thoug  though  h an Orang Orange  e path on the conta  containm inmen entt exists exists..
New QuestQuestion ion
 
===Response===
Respo            Analysis:
nse Analy      sis:
A.          Incorrect Incorr        because ect becau      se the Oran Orang  gee path on cont  conta  ainm inmenentt integr integrityity mus mustt be addressed addre    ssed but the EOP mitiga      mitigating ting strat strateegy gy will not run aa CSP    CSPs        recircculat s if recir      ulation ion is not avail availa able ble in orde orderr to main mainttain ain injec injectition on flow for as long as poss      possib    le.
ible.
B.          Inco Incorrrrect ect beca becau  usese the OranOrang    gee path on cont  conta  ainm inmen entt integ integr  ity mus rity  mustt be addr addre  essed ssed but the CSP      CSPs  s will not be run if recir    recirc culat ulation ion is not availavaila  ble in able    in orde orderr to mainmainttain ain injec injectition on flow for as long as poss        possibible.
le.
C.          Inco Incorrrrect ect beca becau  usese the OranOrang  gee path on  on cont conta  ainm inmenentt integ integr  ity mus rity  mustt be be addr addre essed ssed butbut the CSP  CSPs    s will not not be be run run ifif recir recirc culat ulation ion isis not not avail availa  ble in able    in orde order  r to to main mainttainain injec injectitionon flow flow forfor as as long long as as poss possib ible.
le. Plau Plaus    ible beca sible    becau  usese trans transiition tion will will be be mad made  e toto FR-Z FR-Z.1  .1 whic which h will will direc directt that that the the CSPCSPs    to be s to  be start starte edd unle unless ss the the RWS RWST    T isis need neede    edd for for injec injecti tion on flow flow..
D.
D.        Corr Corre  ect ct per per the the refer refere ence nce 174 174
 
NRC NR    C DR  DRA    AFFT T                                    07/2  4/07 07/24/  07 Q #88 Q# 88 Opera Op  erators tors are are resrespon pondin dingg to  to aa red reduceuced    Intake d Inta    ke Co Coolin oling Intake Inta ke Co Coolin oling    W                                                              g Wa Wate terr (IC (ICW)
W) flow flow due due to g Waate  terr Sys Syste  tem m lea leakag kage e..                                                                to WhWhich ich ON ONEE of  of the the foll folowlowing ing des descrcribibeess the the effe effect ct (if(if any any)) on Co ole rs Coolers (NC  (N  CC Cs5)) abiability lity to                                                        on the the No Norma rmall Co Conta ntainm inment ent to remremoveove hea he at t  fro from  m  the the    Co Co    nta tha thatt effe effect ct,, and and the the cor                                                    nta  inm inm    ent ent  ,
                                                                                                      , the the  con co  seq ns  eq uen ue  ces nc      of correcrectt opeoperaratotorr res respon pons                                                            es of se?
e?
The NC The    NCCs Cs abiability lity toto rem remove  ove hea heatt is:
is:
A.
A.        degra deg  radde  d. Co ed.      Contantainminment ent tem temperperatatuureress will will INCINCR RE EA 125&deg;F and 125        and equ equip                                                            ASSE E tow towardard the the TSTS limlimit of me ipment    nt env environ ironm meentnta all qua qua  lifi lific of Initiat  e                                                                cat atio ion ns s WI  LL LL    be be  cha cha  llen llen ged ged  .
Init        Co iate Conta  ntainm inment ent Pur Purgege in in acc acco Purge                                                    ordrdaanc nce with with O-OO-OP  P-0
                                                                                                  -0553, 3, "Co Cont ntaain inm Pu  rge SysSyste temm.."                                                                                      meent nt B.
B.        degra deg  radde  d. Co ed.      Conta ntainminment  ent tem temper perat atuureress will will INC INCR  RE EA AS  SE 125&deg;F and equ 125                equip                                                                E tow towardard the TS limit of ipmme    nt environ ent        ironm    ent menta  all qualifi lificcat Isolate the affe                                                            atio ionnss  WI LL    be  challenged.
affect cteed d portion tion of the ICW  lOW opera                                                            sy sys ste tem m  and    est  abl ab    ish lis h at least one ope  rabble le ICW hea  head  derer..                                                                            one C.      unaffeffeccte tedd.. Containment temper              peratatuureress will will NOT CHANGE and equ enviro    nm ironmeent  ntaall qualifi lificcat ion atio    s                                                            equip ipmmeentnt will NOT be cha ns will                  chall  llen en ged ge  d.. Init Ini  iate Purge in acc  acco    rda  nc ordance with                                                              tiat e  Co  nta  inm  ent with O-OO-OP    -05 P-0    3, "Co 53,    Cont ntaain inmmeent nt Purge Sys    Syste tem m.."
D.      im impprorovveded.. Containment temper              peratatuureress wil willl DECREASE and equipm enviroiron nmme ent ntaall qua qualifilificcat ion                                                              ipment atio  nss wil willl NOT be challenged. Isolate portio tion n of the ICW sy        sys  ste m and est                                                    the  affeect aff  cte edd tem          estababllisish h at least on  one e opope  rab era    le ICW he ble          hea adder er..
175 175
 
NRCDRA NRC          DRAF    FTT                                        07/24/0 07/24/07 7 Q #88 Q#88 ANSWER:
ANSW      ER:          BB KA:
KA:                      022A2.
022A2      .0404 Abi lity Ability toto (a) (a) predic predict      the t the impacimpacts      ofthe thefollow ts of          foHowi  ingng malfu malfun  nction ctions  s ororopera operati  tions onson CC  S;  and CCS; and (b) based  (b)    bas  ed on on those those predic predict                                                                        on the the ion  s, tions, use  use proce pro  ced dures ure    s to to correc cor    t, rect  , contro con        l,  or mit igat mitigatee the  the conse conseq      uences      ofthose                                                                        trol  ,  or quenc      es of      those malfu malfun    ctions nction    s ororopera operati  tions:
ons: Loss Loss of wat er. 2.9 water. 2.9/3.2    /3.2                                                                                                    ofservic service    e 100FR5 10CF  R55:    5:        43.b.5 43.b.5 Referen Refer  ence:  ce:        3-ONOP-019 3-0NO        P-019,, StepStep 55 RNO,RNO, SD-02  SD-029,    9, Page Page 8,    8,    SD-04 SD-040,    0, Page Page 77 Tech Specs Tech      Specs 3.6.1.
3.6.1.5      &  Basis 5 & Basis Cog Level:
Cog    Level: 22 comp      compre      hension rehen    sion Lev el 22 becau Level        becaus      see the the opera operato  torr must must recog recogni  nizeze that that thethe ICWICW systemsystem provid provides    es heat heat rem  ova  l  for removal for the CCW  the    CC  W system system whichwhich provid provides  es heat heat remov rem    ova al l  for for  conta con    inmen tain  men    t  via via    the Nor mal Normal Conta  Contain        ment cooler inmen        coolers      and the                                                                                  the s and      the Contr Control  ol Rod Rod DriveDri  ve  Mech Me      chaanism nism    cooler coo        s.      The actions action  s ofof sever several        ONOPss will reduc                                                                            lers    . The al ONOP                  reduce      heat loads e heat      loads on the system    sys    tem    but but ultima      tely    the CC W CCW tempetem    perrature atures                                                                                        ulti  mat    ely    the s will rise causin causing    g the conta contain  inmen ment tempetemperrature  ature to rise.
rise.
New Quest New    Questio    ion  n Respon Respo      se Analy nse    Analysi      s:
sis:
A.
A.        Incorreect Incorr        ct bec becau ausse  e ther there  e is no proce procedduralural diredirectctio ionn to init initiate iate aa Con Conta  taininmen mentt Pur Purge  ge.. PlausPlausib    le  bec ible becau  ausse e the NC NCCs  Cs abil ability ity to remremov  ove  e hea heatt is deg degra  rad  ded ed      and and Con Conta  tain    mentt tem inmen      tempe  perrature aturess will incr increa eassee tow towar ardd the TS limit    limit of 125125&deg;F &deg;F and and equ equip  ipm mentent env enviroironnmen mental tal qua    lific qualif      ationss wiN ication        will be be chachallellen  nged ged    and bec and    becau  ausse  e init  iating initiati    ng aa conconta tain  mentt pur inmen      purgege wou would  ld red reduc ucee con conta  taininmen mentt tem tempeperrature atures. s.
B.
B.      Cor Corre  rectct perper the the referefererennce ce C.
C.        Inc Incorr orreect ct bec  ausse becau      e the the NCNCCs  Cs abil    ity to ability    to rem remov  ovee heaheat  t isis deg degraradded.
ed.
Con Conta  tain    mentt tem inmen        tempe  perrature aturess will will incr increa eassee and and equ eqUip ipm  ment ent    enviro environnmenmental    tal qua qualif lific  ationss will ication        will bebe cha    llennged challe    ged and  and becbecauausse  e there isis no there          no pro proce ced dural ura  l  direct dire    ctioionn to to init    iate aa Con initiate        Conta  tain  mentt Pur inmen            ge.. Pla Purge        Plaususibible le becbecauausse  e    initiati init  iati ng aa con ng      conta tain inmen men      tt pur purge  ge wouwould  ld red reduc ucee concontatain  mentt tem inmen        tempeperrature aturess D.
D.      Inc  orreect Incorr      ct becbecauausse  e the the NCNCCs  Cs abil  ity to ability    to rem remov ovee hea heat t isis deg degraradded.
ed. Con Conta      inmen tem tempe  perrature aturess will will incr    eassee and tain    mentt increa        and equequip ipm  ent env ment      enviro ironnmen men      tal qua tal  qualif  ication lific            s  will be be cha      llennged.
ged. Pla                                                                                      atio  ns will challe                    usibible Plaus      le bec    ausse becau      e ope operaratotors rs will will Isol Isolateate    the affe the    affect    ed    portio of ofthe the ICW ICW sys      tem and                                                                              cted      por  tionn system      and esta estab blis  h atat leas lish        leastt one one ope operarabble le ICWICW hea heade der.r.
176 176
 
NRC NR    C DR DRAF  AFTT                                  0712  4/07 07/24/  07 Q#89 Q#    89 Both Bo  th uni units ts are are at at 100 100%  % powpower  er wit withh all all sys syste tem ms s inin nor norma mall alig alignm nment ent..
  ** 0-O0-OSP  SP-07
                  -075.11,1, "AuAuxixilialiarryy Fee Feed    wa dw  ateterr Ins Inserv ervice ice Tes Test,t," isis bei being ng per the  A the "A" AF  AFW  W pum pump. p.                                                                    perform forme edd to to tes testt
  **  The Sh The      Shift ift MaManag nager er isis not notifie ifiedd tha thatt the the "A" A AFAFW W pum pumpp dev develo eloped ped 300 maxim ma    ximum um obt  obtain ainabl ablee spespee                                                                300 gpmgpm atat aa edd ofof 580 58000 RP  RPM.M.
Which Wh  ich ON  ONEE of of the the foll follow owing ing desdescr    ibe crib ess the the corcorrec rectt ope opera rattor Sp ec  . im Spec. implica  pli cattion ionss of                                                          or resrespon pons see and and thethe Tec Tech.h.
of this this eveevent?
Decla De  clarere the the "A" A AFAFW W pum pump:
A.
A.          operable and ope            and retu return rn it toto ser servic vice.
e.
Align Alig    A AF W pum n "A"            pump to Tra    Train 11 to restore  tore full fuN com compliaplianc ncee with the TS LCO.
B.
B.          inoper ino  perable but available and ret retuurn rn it to servic vicee..
Align Alig    A AFW pump to Train 2 to n "A"                                              restor toree full complia pliancncee with the TS LCO.      D.
C.        inoper ino  perabl e and remove it from          from service.
Align Alig  n "c" C AF W pump to Train 1I to extend the AFW TS action time hours to 30 days.                                                                                        from from 72 D.        inoperable and remove it fro ino                                      fromm servic vice e..
Align Alig  n B "B" AFW pump to Train 2 to ext hours to 30 days.                                            end the AFW TS action          ion time frofrom m 72 177 177
 
NRCDRA NRC          DRAF    FTT                                    07/24/0 07/24/077 Q#89 Q#89 ANSWER:
ANSW        ER:        CC KA:
KA:                    061G2.
061G          2.22 2.2.22 As As ititrelate relates      to  the s to the AFW  AF  W system system:: knowl knowle    dge of edge      oflimitin limitingg condit conditiions onsfor  foropera    tions safe ty    lim  its.
safety limits. 3.4/4.1 3.4  /4.1                                                                                  operati    ons andand IOCFR5 10CF    R55:  5:        43.b.2 43.b.2 Referen Refer  ence: ce:      3-OP-0 3-0P-    075,75, Sectio Section      7.1 n 7.1 0-OSP-0-OSP        075  .11  ,  Ste
                                    -075.11, Stepp 7.1.6.1  7.1.6.1 TS 3.7.1.
TS    3.7.1.2      Actionss 1I and 2 Action            and 33 Cog: Level:
Cog:    Level: 22 comp    compre      hension rehen    sion Lev  el  2  bec Level 2 becausee the aus      the opera operato  torr must must recogrecogni nizeze that that 58005800 RPMRPM and and 300  300 gpmgpm do  do not meet the meet    the criteri criteria    for  a a for a SAT  SA  T test.
test. and and the                                                                      not the pump pump must mu    st  be be  declar dec lareedd  inope ino  perrable.
able      Then the opera the  operato  torr must must recog recogni    ze that that even                                                                  . Then nize            even thoug though  h either either "8" B or or "c" C  AFW AF    W  pump pum      can    be alig ned aligned to  to Train Train 1,  1, OP-07 OP-0755 direct                                                                          p  can    be directs    that "c" s that      C AFW AFW pump  pum    p be be aligne alig nedd    to to  Train Tra      1  and finally itit is finally      is this this action action that will restor                                                                      in  1 and restore  e 2 indep indepe    ndentt AFW enden        AFW trains trai ns  and    increa    see the Act  ion Action TimeTime to  to 30 days.days.                                                                            incr  eas      the New Quest New    Questio    ionn Respon Respo    nsese Analy Analysi    s:
sis:
A.
A.        Incorre Incorr      ct becau ect  becausse    e the "A"A AF    W pump AFW      pump fail failed ed to dev devel  op eno elop  enoug ughh flow or RPM      RPMss and and mu  mustst  be    dec  lare declared    d ino inopeperrable able and take  taken  n OO OOS.S. PlaPlaus usibiblele  becau bec  aus se    the e the A
          "A" AF AFW W pumpump    p was DO  OOS    S dur  ing the Inse during            Inservrvicice  Testt and wou e Tes          would  ld  norma nor  mal  lly ly bebe retu return rneedd to servservicicee and alig alignenedd to TraTrainin I1 ifif the test hadhad bee been  n SASAT.T.
B.
: 8.        Inc  orreect Incorr      ct bec becau  aussee the the A "A" AF    W pum AFW      pump  p fail failed ed to  to dev devel  op eno elop    enougughh flowflow or or RPM RPMs and      mu  st and must be dec  be        lareed declar    d ino inopeperrable able and                                                                      s and take taken n DO OOS. S. PlaPlaus usib ible le    becau bec  aus see  the A
          "A" AF AFW  W pumpump  p nea    rly deli                                                                              the nearly          verred delive    ed the the req requir uireed    flow and d flow    and mig might      be con consid (err  one  ous (erroneously) av ly)        ailable ht be            sideered red "availa    ble" for for serv servicice.
e.
C.
C.        Cor Corre  rectct per per thethe refe refererennce ce D.
D.      Inc Incorrorreect ct bec becau ausse e ope    rato exte    nd opera      rs nee tors    needd to to alig align    "c" AF n C      AFW    pump W pum    p toto TraTrain in I1to to extend the AFthe    AFW W TS  TS acti actionon tim time e from from 72  72 hou hours rs toto 30 30 day days.
alre                                                                                        s.    "8" B    AFW      pump AFW pump isis alreadadyy alig    nedd to aligne      to Tra  in 22 but Train        but unt  il C until  "C" pum pump  p isis alig aligne  d to ned to Tra Train in 1,1, the the TS TS Act    ion Tim Action      Time e isis still still 72 72 hou hoursrs. . Pla  usibible Plaus      le becbecau ausse      "8" AF e B    AFWW    pump pum      p  is  norma is normally    lly alig alignenedd toto Tra Trainin 2..
2 ..
178 178
 
NRNRC  C DR DRA  AFFT T                                0712 4/07 07/24/ 07 0#Q #9 900 UnUnitit 44 isis inin Mo Mode de 1I witwithh all all sys systetemms    opera s ope    rabble le,, wh whenen CoConta ntainm gas mo gas      monitonitors  ,
rs, PR PRMS  MS-    11/12
                                            /12,, Sa                                            inmentent par parti ticu culate late and and
                                      -11          Samp mple le Inle Inlett Tem Temp  perera atutur ree swi switch tch,, TS TS-36
                                                                                                            -3640, 40, fail faisls HIG HIGH H..
Which Wh    ich ON  ONEE of  ofthe the foll folow lowing ing des descr    ibe crib  ess the the Tec Techh SpSpec ec imp impli lica cat tion ionss of of this this fail faiure lure??
Th Thee TS TS-36 -3640  40 fail faiure lure::
A.
A.          did NO did      NOTT affe affec ctt ope operarabbil ity of ility  of R-1 R-111 or or R-1 R-12. 2.
Th    e The apppliap      cable lica  ble TecTech h SpSpecec LCLCD  D isis sat satisfi isfied ed..
B.
B.          disabl dis    abled ed R-1 R-111 onl only.
y.
Verify Ve    rify R-1 R-122 isis ope operarabble    and the le and      the ass associ ociat ateedd Tec Tech h SpSpec ec LCLCDD will will be be sat satisfi  ed..
isfied C.
C.          disabl dis    ableded R-1R-122 onl only.
y.
Verify R-1 Ve          R-111 is  is ope operarab ble  and the le and      the ass assoc ociiat ateedd Tec Tech h Sp Spec LC LCD will will be be sat    isfiied satisf    ed..
D.
D.        disabl dis  abled      bot ed bot R-1  h  R11 and  and R-1 R-12.2.
Until ope Un        operarab bilility ity of of R-1 R-111 andand R-1 R1 22 isis res restore tored d,, comply wit with the app Tech Tec    h Sp Spec Act  Actioionn Sta State temme  nt..                                                appli lica cable ent 179 179
 
NRCDRA NRC        DRAF  FTT                                  07/24/0 07/24/077 Q #90 Q#90 ANSWER:
ANSW        ER:    0D KA:
KA:                  073G2.
073G          1.33 2.1.33 As As ititrelate relates  to  Pro    ces s to Processs Radia  Radiati    on Monit Monito tion            ring: Ability oring:    Abilitytoto recog recogninizeze indica indicat tions ions for sys tem    ope rati system operating paramng    parame      terswhich which are                                                              for eters              are entry-entry-le level vel  condit con    ions diti ons for for techn tech  ical spe cifi  cations                                                                                        nica  l specification    s.. 3.4/4.
3.4/4.0  0 10CFR5 10CF    R55: 5:    43.b.2 43.b.2 Referen Refer      ce:
ence:      SD-068, SD-06      8, Page Page 27  27 and and Figure Figuress 1919 and and 20 20 TS    3.4 TS 3.4.6.1  .6.1 Cog Level:
Cog    Level: 22 comp  compre      hension rehen    sion Lev  el  2 Level 2 becaubec  aussee the the opera operato  torr must must recog recogni  ze that nize  that TS-36 TS-364  400 failing failing high high trigge trigger  rss the high tempe high  temperrature ature alarm alarm at  at 125&deg;F 125&deg;F andand closes                                                                the closes the the inlet inle t and and  outlet out let valves valv  es and and    stops the samp the  sample      pumps.
le pump          Becaus                                                                                stops
: s. Becau      see the the samp sample    flows throug le flows    through    h both bot h  R-11 R-1  1  and    R12    in  series bot h  R-1 I and both R-11      and R-12 R-12 havehave lostlost samp sample and    RI  2  in  series,,
flow. The le flow. The TS TS  Action Act  ion  Statem Sta tem  ent  applie app  liess  ifif both R-I1 and R-11    and R-12 R-12 areare inope inoperrable.
able. IfIf either either R-11                                                              both R-11 oror  R-12 R-1  2  are  satisfi sati    ed, sfie  d,  the  LCO LC  D    is is sati sfie satisfied. d.
New Quest New    Questio  ionn Respon Respo      se Analy nse  Analysisis:s:
A.
A.        Incorre Incorr    ct becau ect  becausse    e the tempe temperrature ature swi switch tch fail failure    disabl ure disa      ed bot bled    both  R-111 and h R-l      and R    R-
: 12. Plausib
: 12. Plaus        le  bec  aus  e ible because if the swi      switch tch fail failure ure had not disa  disabl  ed R-1 bled    R-111  and    R-12, R-12, the app    licaable applic    ble Tec Tech  h Spe Spec  c LC LCO D wou wouldld be sati satisfi sfieed.
d.
B.
B.        Inc  orreect Incorr  ct bec becau  ausse e the the tem tempe perrature ature swi switch tch fail failure    disabl ure disa      ed bot bled    both    R-111 and h R-1      and R      R-12.
: 12. Pla  usib Plaus      le bec ible    becauausse e ifif R-1 R-122 rem remaiaine nedd ope opera rabble,  the app le, the    applic licaable    Tech ble Tec        Spec h Spe      c LC LCO  O wou wouldld be be sati  sfieed.
satisfi    d.
C.
C.        Inc  orreect Incorr    ct bec becau ausse e the the temtempe perrature ature swi switch tch fail failure    disabl ure disa      ed bot bled    both    R-111 and h R-1        and R    R-12.
: 12. Pla    usib Plaus    le bec ible  becau ausse e ifif R-1 R-111 rem remaiaine ned d ope operarabble,    the app le, the    applic  able licable Tec Tech  h SpeSpec    c LC LCO D wou wouldld be be sati  sfieed.
satisfi  d.
D.
D.      Cor Correrect ct per per thethe refe refererennce ce 180 180
 
NRC NR    C DRDRAF  AFT T                                  07/2 07/24/
4/07 07 Q#91 Q#  91 Unitit 33 isis at Un              at 100 100% pow    power er wit withh all all sys syste  ms tem    in nor s in  norma mall alig alignm nmentent and withdr wit  hdraw  awn. n.                                                                                  and con control trol rod rodss full y fully
  ** An Annun nuncia ciatortor FF 4/64/6,, RP RPIS  IS PO POWE WER  R TR TROU OUBLBLE,E, ala alarmsrms..
  ** TheThe fiel  field    op  era d ope rattor        reports or rep    orts tha thatt the the 300 3D01  1  sup sup ply ply    bre bre  ake akerr to to thethe RP tripped trip    ped ope  open. n.                                                                              RPI inv inverte erterr has has Predict the Pre          the imp  impacactt of of this this fail failur uree on on the the rod rod pos positio ition indindica ication tion (RP action act ionss req  require uired. d.                                                                        (RPI) sys system and  and thethe RPls RP  Is will will be  be powpowere eredd from from the the GV CVT:
A.
A.          automatically.
aut RPls RP    Is ind indication tion mamay hav e cha  chan  ged.
nge Initial Init  iallly  imple y imp    lem me  nt 3-0 ent    3-ONONOP-0 P-028.
28.11,, "RG RCC G Mis Misal alig ignnm me ent nt.."
Then The        transi n tran    sititio onn to 3-03-ONO NOP-0 P-028.28.2, "RG RCC G Pos Positiitioonn Ind Indication tion Malfun lfunct ctio ionn."
B.        automatically.
RPIs  ls indicatio    tionn will will NOT change.
Initial Init  iallly  Imple y Imp        me lem ent  nt 3-0 3-ONO NOP-0P-028.
28.2, "RGRCC G Pos Positiitio onn Indicatio  tion n Malfun lfunct ctio ionn."
C.
G.          afterr manual tran afte                      transf sfe er.
r.
RPIs  ls indicatio    tion n may hav e cha    chan ngegedd..
Initial Init  ialllyy imp imple lem me  nt 3-0 ent  3-ONO NOP-0P-028.1, "RG  RCC G Mis Misal aligignnm meentnt.."
Thenn tran The        transi    tio siti  onn to 3-0 3-ONO  NOP-0 P-028.
28.2, "RGRCC G Position Indicatio        tionn Malfu lfun  ctio nct ionn."
o.
D.        afterr manua afte            nuall tratrannsf sfeer.
r.
RPls indicatio        tion n wil l will NOT change.
Initial Init  ialllyy Im Impplelem  meent nt 3-O 3-0 NONOP-0 P-028.2, R  "RG CCG Po Pos siti itio onn Indicatio  tionn Malfu lfun ctio nct ionn."
181 181
 
NRC DRAFT                                                07/24/07 Q# 91 ANSW AN  SWER :            A KA::
KA                      014A2.
A2 .02  02 Abiility Ab  lity to (a) predict  dict the imp  impactactss of the foll follow owiing ng mamallfun functio ctions or operat      ratiion RPIIS; RP    S; and (b) based on tho            those se predict                                                        onss on the ions, use pro diction          pro  ced ced  ure s  to  cor  rectt,, control, or rec mitiga mit igattee the con  conseqsequences of tho        thosese ma mallfun functio ctions or operations: los the RPRPIls. s. 3.1/3.6                                                                              losss of pow er to IOCFR 10C  FR5    5:
55:        43.b.5 Refere ferenc  nce e::      SD-006 Pa SO              Paggee 11 and Fig  Figure 5, 3-ONO 3-0  NOP-0  P-028.
28.1, Step 1.1, 5.6 3-ONO 3-0  NOP-0  P-028.
28.2, Step 1.1, 5.3 3-ARP 3-A  RP--09  097  .CR 7.C  R,, F 4/6 416 Cog Co g Level:            11 Re Reccal alll New Ne  w Qu Que    stio est  ion n Respo Re  sponse An      Ana alylysi siss::
A.          Corrre Co    rect ct per the refe    refere ren nce ce B.          Incorr Inc  orre  ct because ON ect                  ONOP  OP-028.2 is not a direct ent OE has demonstrat                                                        entrry y pro procedure and sta          stattion ion trated ed tha thatt the out put vol voltag tage e of the CV inverte inv  erter res                                                                  C\I  T  is  diff diff  eren ere    t nt than tha  n the resuulti ltin ngg in all RP RPIlss indica icatting ing diff differe erenntly mu st first perform act tly  afte r tran  sfer sfe    .
: r. Op  erator torss actiiononss of ONONOPOP-028.1 and the    then n wh whe enn directe  cted                                                          tran  sitio siti onn  to  ON ON  OP OP  -028.2 d.. Plausibusible le because The RP      RPII pow er supply has aut transf tran  sfe err rreedd from the inv    inverte                                                        auto o--
erter to the CV T.
C.        Incorrorre  ct because the RP ect                        RPII pow er supply has auto-t inv inverte erter to the CVT. Plausi                                              o-trran anssfe  rre ferr  edd from the usib  le because the RP ble                    RPIlss will indicaicattee low er tha before the pow er interrup            rruptio tion                                                          than n n and operato rators rs will Initially impimp 028.1, "RC  RCC Mis  Misalig                                                              lem    ent  3-ONO 3-0  NOP-alignment ent,," the thenn transitio sition n to 3-0 3-O  NO NO Indicaicattion ion Malfunction.                                                    P-0 P-0    28.2
: 28. 2,,  RC "RC    C  Pos Pos  itio ition n."
O.
D.        Incorr orre ectct because the RP        RPII pow er supply has auto-tr inv inverte erter to the CV T and because ON                                      o-tran anssfe  rre ferr  edd from the ONOP OP-028.2 is not a direct ent        entrry y pro procedure. Op      Operator  torss will Initially impimplem lement 3-03-O  NO NO  P-0 P-0  28.1
: 28. 1,,  RC "RC    C Mis Misaligalignment  ent,," the then n transitio sition n to 3-0 3-ONONOP-0P-028.
28.22,,  RC "RC  C  Pos Pos  itio itio  n  Indica Malfunction.      n." Plausi  usib  le because the primary procedure ble                                                                    icattion ion respond to this event is ON                                                            ope  rat rato orsrs  will  use    to ONOP OP-028.2 182
 
NRC NR    C DRDRA  AFFT T                                  0712 07/24/
4/07 07 0#Q #92 92 AA req require uired    continu d con    tinuououss fire fire wa watch tch has has bee the 3C                                                  been    establ n est ablish isheded in in the the Au Auxilia xiliarryy Bui the    3C MCMCC. C.                                                                                          Build ldin g at ing  at
  ** AR  ARMSMS Ch  Chann annel el 15, 15, AuAuxx Bld Bldgg No North rth N/S N/S CoCorrid rridor, or, ala alarms rms and and its increa inc  reases ses toto 80 80 mr/mr/hr hr..                                                            its dig digital dis display
  **    The RO The    RO depdepreresssesess the the ChCh.15
                                                  .15 HIG HIGH H alaalarm PB PB on on the the AR ARMS  MS con control no  tes notes tha thatt the the dis display rea  reads ds 55 mr/                                                trol pan panel andand mr/hr hr,, the the sam sam    e  val val  ue ue  as as  the the shown In sho        In Att Attach achme ment nt 11 (AR                                                    hig highh ala ala  rm  val val ue ue (ARM  MSS SeSettpo poiint nt Lis List and and LocLocat High "Hi      Area gh Are  a RaRadiation                                                      atioion ns) s) of of 0-O 0-ONO NOP-0P-066, tion MoMonito nitori ng Sys ring  Syste temm Ala Alarm.
rm."
Which Wh    ich ONONE  E of of the foll follow owinging des descr  ibe crib ess the the validit idityy of of this this reading and the correct op    era ope rattor      respon or res  pons se?e?
The alarm is:
The A.          valid.
Evacu Eva  cuaate    perso te per  son  nss in the affe affect cteed d area.
Do NOT includ    lude the fire watch person in the evacuatio  tion n..
B.          valid.
Evacu Eva  cuaate  perso te per    son nss in the affeaffect cteedd area.
Inc lude the fire watch person in the evacuacuatiotion n..
C.          NOT valid.
Silenc Sile  nce e the alarm  rm..
Notify Radiatio    tionn Protec  tectio n to survey the area.
tion D.        NOT valid.
Sil Sileenc ncee the alarm  rm..
No Notify tify Radiatio tionn Protec  tectio tionn to ins install tall aa portable rad radiati iation monit    nito or.r.
183 183
 
NRC DRAFT                                                07/24/07 Q #92 Q#  92 ANSW AN  SWER :          B KA::
KA                    072G2 G2..1.1 1.14 As it rela relatetess to AreArea Ra  Rad  iati dia    on Mo tion    Monito nitoring: Kn Kno ow wle leddgege of system status crit whiich wh  ch require the notific            ation of pla ificatio                                                                    criteria plan ntt personnel.
nel. 2.5/3.3 IOCFR 10C  FR5  5:
55:        43.b.4 bA , 43.b.5 Refere ferencnce e::    O-ONO  NOP-066, Step 2 and CA UTION prior to Step 3 Cog Co  g Level: 2 com        compre prehension Level 2 bec because the operator mu st rec              recoogngniize ze tha thatt the ala alarrm m is valvaliidd and tha continu tinuous fire wa    wattch ch loc loca  tion atio  n at the 3C MCC is adjacent to thatt the loca loc  tion atio  n and that respon                                                                  the    AR    MS  Cha Ch    nneell 15 ann ponse se to an AR MS ala      alarrm m tak takeses priority over a continu wattch wa  ch..                                                                                                    tinuous fire New Ne  w Qu Que  stio est  ionn Respo Re  sponse An  Ana    lysi aly siss::
A.        Incorr Inc orre    ct bec ect  because fire wa      wattch ch personnel should be inc          incllud ude  d in the evacuation.
ed usib Plausi      le bec ble  becaus e the ala    alarrmm is val valiidd and a loc locaall area evacuation      tion is required.
B.        Corrre Co    rectct per the refe refererenncecess..
C.        Incorr Inc  orre    ct because the ala ect                        alarrmm is val valiid.
: d. Plausiusib le because the ala ble silenced if the ala      alarrm                                                                  alarrm m ma mayy be m is det deteermrmiine nedd to not be val  vali  d id  and Protectecttion ion will subseq                                                        bec  aus    e  Rad Ra  iati dia    on tion sequen uentlytly be cal callled ed to sur surv  ey the area.
vey D.      Incorr Inc  orre  ect ct because the ala        alarrm m is val valiid.
: d. Plausib usiblele because the ala silenced if the ala      alarrm                                                              alarrm m mamayy be m is detdeteermrmiine nedd to not be val vali idd  and Protec tecttion ion will subseq                                                          bec  aus      Raddia e Ra  iati  on tion sequenuentlytly be cal callled ed to ins insttall all a portab  tabllee radiation monitor.
184
 
NRC NR      C DRDRAF  AFTT                                    07/2 07/24/
4/07 07 Q #93 Q#  93 Opera Op    erators tors are are res respon pondin dingg to to aa larg large    break e bre  ak LOLOCA CA whwhenen thethe ST folow foll lowing ing QSQSPD  PDSS Co Corere Exi Exitt The                                                STA A rep reports orts the the Therm rmoococouupl plee rea readin dings:
gs:
QuQuad ad 1I                    Quad Qu  ad 22                      Quad Qu    ad 33                      Qu Quad ad 44 CETT Tem CE        Temp    p            CETT Tem CE        Temp  p            CETT Tem CE          Tempp                CE CETT TemTemp  p R7 R7        660 660                  K5 K5          1250 125                  H8 H8          415 415 P8 P8        590 590                  K3                                                              K11 Ku      666 666 K3        ???
                                            ???                  F9 F9        835 835 N6 N6        604 604                  J2                                                              N1 N155    680 680 J2        2300 230                  E8 E8          7??
                                                                            ???
N4 N4        625 625                  G6                                                              H1 H133    602 602 G6        675 675                  BlO B1  0      905 905 Mu1 M1        ???
            ???                  G1                                                              H9 H9    615 615 G1        1560 156                  B5 B5          660 660 M9 M9        ??
            ????                F5                                                              E1 E14    622 622 F5        230 2300 L8 L8        670 670                  F3 F3 E12 E12    688 1780 178 Which ON  ONE of the foll  follow  ing des owing      descrcribibeess the cor coree condit ditiion Manag Ma  nager should giv      givee to the Unit Supervis                              on and the dire        ctio direct  n the Shift ion or?
CETs J2 and F5:        F5:
A.        should be included in the core con dit ditiion on evaluatio  tion n..
A Red Path exists      sts.
Transitio    n to 3-EOP-FR-C.1, "Re tion                              Respspoons nsee to Inadequate Core Cooli            olin g."
ng.
B.        should be included in the core con dit ditiion on eva evalua luatio tion n..
An Ora Orang  ngee Path exists.
Transitio tionn to 3-EOP-FR-C.2, R          "Reesp spoons nse e to Degraded Core Co            Cooli olin g."
ng.
C.        sho shoulduld NOT    T be included in the core con A Re                                                  conditditiion on eva evalualuatiotion n..
Red d Path exists.
Transi nsitio tionn to 3-EOP-FR-C.1, R          "Reespspoons nse e toto Inade deq quuat atee Core    re Co Cooli olin g."
ng.
D.
D.        sho  uld should NO  NOTT bebe included ed in  in the the coree concondit ditiion on eva evalualuatiotion An An OrOraang ngee Pat Pathh exists                                                      n..
sts..
Tra Transi nsitio tion n to to 3-EOPOP-FR-FR-C. -C.2, 2, R"Reesp spoons nsee toto Degraded  ded Core      re Co Cooli olin g."
ng.
185 185
 
NRCDRA NRC          DRAF  FTT                                    07/24/0 07/24/07 7 Q #93 Q#93 ANSWER:
ANSW        ER:      AA KA:
KA:                    017A2.02 017  A2.02 Abi lity  to Ability to (a)  (a)predic predict      theimpac t the      impacts  ts ofofthe thefollow followiingng malfu malfun  nction ctionss ororopera      tions ITM    sys  tem  ;  and ITM system; and (b) based    (b)    bas  ed on  onthose operati      onson  on the the those predic predict  ion tions,  s, use use  proce pro    dures ced  ure  s to  correc    t,  contro or  mit  igat or mitigate the  e  theconse conseq      uences quenc      es of  ofthose those malfu to  cor    rect  ,  con  troll,,
malfunnction ctio  s ns or or  opera ope    tions:
rations: Core Core Dama          ge 3.6/4.1 3.6/4.1                                                                                                                    Damage 10CFR5 10CF    R55:  5:      43.b.5 43.b.5 Referen Refer  ence: ce:      3-EOP-F-0, 3-EOP      -F-0, EncloEnclosu      re 22 and sure      and Basis Basis Page Page 20  20 Cog Level:
Cog    Level: 33 Analy  Analysi  siss Lev  el  3  bec  aus Level 3 because the opera e  the    operato  torr must must analyz analyze  e all all of of the the core core tempe temperratureature data then recall then    recall that that thethe evalua evaluattion  ion is                                                                    data and and is based based on  on the the five five  highe hig  hesst t  CETs CE  Ts  includ    ing    the    failed CETS and  and that that thresh thresho                                                                            incl udi  ng  the    failed CETS                                    ld for old    for Red Red Path Path is is 1200&deg; 1200&deg;F  F  (Oran (Or  ang ge  Path    =
the  QS    PD  S                                                                            e  Pat  h  =  700&deg;F 700  &deg;F)  ).
                                                                                                                          . Revie Rev    ieww of of the QSPDS readin    reading  gss revea reveals        that includ ls that      includiing ng the the failed Conditi                                                                        fail ed  CETs CE  Ts  revea rev      ls eals  a  Red Red      Path Pat  h Condi        on and tion    and FR-C.
FR-C.1        needs to be 1 needs                be implem implementedented.. This tho  ugh                                                                            This must must be determdete  rmi  ined ned    even eve  n that though that if the  if  the failed failed CETsCETs are not includ      include and                                                                      ed, d, five CETsCE  T5  are are  greate gre  ater r than than      700&deg;F 700 and thethe opera operato  torr will conclu conclud                                                                                          &deg;F dee errone erroneo    usly that only ously          only an OrangOrange    e Path Path exists exists..
New Quest New    Questio  ionn Respon Respo        se Ana nse    Analy  lysi s:
sis:
A.
A.        Cor Corre rect ct per per the refe refere  ren  ces nces B.
B.        Inc  orreect Incorr      ct bec becau ausse  e aa Red Red Pat        h exis Path        ts and exists  and tran transi  tion sitio    should n sho    uld bebe mad made        to e to 3-E  OP  -FR 3-EOP-FR-C.1, Re-C.1  ,  "Resp  spo  nse to onse      to Ina Inadedeqquate uate Cor Core e  Coolin Coo  lingg."
                                                                                                        . Plaus Pla  usib ible    becau le becausse the the con conditditiions ons for for anan OraOrang  ngee Pat                                                                            e Pathh also also exis existt and and EO EOP- P-F  FR-C.
R-C    2
                                                                                                                .2  is is  the the    correc      t pro proceceddure ure to to tran    sitio  n for                                                                        cor  rect transi    tion    for an an Ora Orangngee Pat Path.h.
C.
C.        Inc  orreect Incorr    ct bec becauausse  e the the failfaileded CE    Ts sho CETs    should uld be be incl includ udeed d inin the the eva evalua luationtion.
Pla  usib  le Plausible becau bec  ausse  e aa Red                                                                                  .
Red Pat  Pathh exis exists ts and and opeopera ratotors rs  should sho  uld    transi tran  sitiotion    to  3-EO    P-FFR-C.
R-C.1,                                                                                                  n  to  3-EOP-                1, Re "Resp  spoonsense to  to Ina  deqquate Inade    uate Cor Core    Coolin e Coo        g."
ling.
D.
D.        Inc  orreect Incorr    ct bec becauausse  e the the fail    ed CE failed    CETsTs sho should uld be  be incl includ udeedd inin the the evaevalua luation tion.
Pla  usib  le  bec Plausible because    aus    e the                                                                                    .
the con      ditiions condit    ons forforan an Ora Orangngee Pat Pathh  also exis also    existt  and and      EOP-FR-    C.22 isisthe                                                                                                  EOP FR-C.            the cor    rectt pro correc        proce ceddure ure toto tran transi sitio tion n forforanan Ora Orangngee Pat Path.
h.
186 186
 
NRC NR    C DRDRA  AFFT  T                                07/24/
07/2 4/07 07 Q #94 0#  94 With Wit  h Un Unitit 33 at at 80%
80% pow  power,er, ope opera  tor rato  rss are are res respondindingg to to aa Xe Xenon non osc RO rep RO    reportsorts the the foll follow owinging val values ues of                                              oscilla illation tion.. TheThe of Axi Axial al Flu Fluxx Dif Differe ferenc ncee (AF (AFD D):):
              **    N-41:
N-4 1:          +13
                                    +1
              **    N-42:
N-4 2:          +122
                                    +1
              **    N-43:
N-4 3:          +1
                                    +1 6
              **    N44:
N-4              +16
                                    +1 Which Wh  ich ON  ONE  E of of the the foll follow owinging des descr  ibe crib ess the the con conditi dition on ofof the the rea eff ect effect (if (if any any) ofof allo allowin wingg con                                              reactors r's AFD andand the continu tinued ed opeoperati ration on wit withh the thesese con conditi dition onss??
The rea The    reactor AF    AFD is: is:
A.          within wit  hin the operati  ration ona all spa spac  e.
ce.
Operatio Op            n tion at thisthis pow power level may continu      tinue e indefin efinit itel elyy..
B.          within wit  hin the operat    ratiion onaall spa spac e.
ce.
Wi    th With the positiv    itive AFD, Hot channel factors transsie                                                    tors may be exc  exce  eed eded if a short term tran    ien ntt occurs.                                                                                    term c.
C.        outside the operat        ratiion ona all spa spacce.
e.
Hot channel factors        tors may be exc  exce eed eded as a result of contin        tinu ed operat ued this pow er level.
this                                                                                                ratiion on at D,
D.        outside the operat        ratiion onaall spa spacce.
e.
Hot channe        l nnel factors tors wil willl not be excexce  eded as a res eed            result ult of contin tinu ed operat ued at thithiss pow er level but mayy be ex                                                                  ratiion on excceeed eded if a short  rt ter termm tratran sie nsi  nt occurs.
ent REFERENCE PR            PROVOVID  IDE ED D 187 187
 
NRC NR    C DRDRAF  AFT  T                                      0712 07/24/
4/07 07 Q #94 Q#  94 ANSW AN    SWER  ER::      CC KA::
KA                    G2.1.7 G2    .1.7 Ability Ab  ility to to eva evaluluaate    plant te pla    nt per perform forma    nce anc    and ma e and      make ke ope operati ration onaall jud operati ope  rating ng chacharacteri teristi                                                                  judgemgeme  ent ntss bas  ed on based  on sticcs,    reactorr beh s, rea            behavi avior, andand ins instrum trume  entnt inte interp rprret etaatio tionn.. 4.4 4.4 IOCF 10C  FR R5  5: 43.
55:        43.b.5 Refere Re  ferenc ncee::      PCB Se PC        Secctio tion 5, 5, Fig Figure ure 1A1A O-AD O-A      M-DM-53  5366,, Att Attach achme ment nt 1, 1, Se Secctio tion 3/4 3/4.2 PCB Se PC        Secctio tion 7, 7, Fig Figureure 11 Cog Lev Co      Levelel:: 2 com  compre prehensio n Le vel Level 2 bec  beca  use the ope aus            opera  rattor  will have to plot the giv or will                              givenen AFD val refere refe  rennce    provid ce pro    vided.
ed. The Then                                                                valuesues on the n the ope  opera rattor or  wil willl hav  e  to  rec  ognize that 2 val outside the operat out                      ratiion ona all spa spac                                                                        values ues are
: e. 2 of the 4 val ce.                    values ues  out    sid  e  imp the operat  ratiion ona all spa spac    e. The                                                      im  pli lies es  tha  t  AF  D is out of ce. The ope opera rattor  will then have to rela or will the operat  ratiion ona all spa spac                                                              rel ate te  tha  t  bei ng    out  side of e me ce    meansans Hot channel factors        tor  s continu tinued                                                                        ma  y  be  exc ex  ceeed ed    ed  as a result of ed operat  ratiion on at thisthis pow er lev el.
New Question Prov Pro  vidide e PCB Secti      ctio onn 5, Fig  Figuurere 1AIA and and Secti  ctio onn 7, FigFigu  urere 1 1 as reference    nces  s Respo spon  nsese An Anaalylyssis is::
A.          Incorrect bec  beca    use the AFD is outside the.op aus be  ca                                                              ope  erarati tioona nall sp spa  acce.
: e. Plausible bec    use 2 of the four AFD values are aus AFD was within the operat                                      wit hin    the  ope    ratiion rat  ona all sp spa accee and if ratiion ona all sp spaacce, e, operat rati ion on  at  this thi contintinuuee indefiefinnititel elyy..                                                        s  pow    er  level ma mayy B.        Incorrectect bebec  caaus use the AFD        D is outside the ope      operat ratiion ona all sp spa be bec caaus use 22 of the four AFD values are                                                    acce.
: e. Plausi  usible ble AFD was within the ope                                          wit  hin  the    ope ope  rati rat  ona ion  al l spa sp ac ce  and ifif e and operatratiion onaall sp spa acce, e, hot hot chachanne nnell factor ex exc ceeed ededed as                                                                          tors s  wo  uld uld    not not  be be as aa resresultult ofof contin tinu ued ed ope operatratiion on at at thi thiss power    er level. el.
C.
C.        Correct  ct per thethe refrefe ere ren ncces es..
D.
D.        Incorrect  ect be bec caaususee hothot cha channennell fac factor tors s ma mayy be be ex exc ceeed eded con contintinuued ed opeoperat                                                                  ed as as aa resresult ult of of ratiion on at at thi thiss power  er level.
el. Pla Pla  usi usi out outsidee the                                                                  ble ble  bec be  ca aus us  e e  the the    AF AFD  D isis the ope operat ratiion ona all sp spaacce.
e.
188 188
 
NRC NR    C DR  DRA  AFFT T                            07/2 07/24/
4/07 07 Q#95 0#  95
  **  Unitit 33 RC Un          RCSS temtemper perat atuure re isis 400 400&deg;F.&deg;F.
  **  Unitit 44 RC Un          RCSS temtemper perat atuure re isis 310 31 0&deg;F
                                                      &deg;F..
Which Wh  ich ONONEE of  of the the foll foNow owing ing ide identif ntifie iess the the min minim imuumm req require Co  nd en  sat Co nde nsa tee Sto  Stora                                                      uiredd wa water ter inv invent entory ory in in the ragge    Ta nk e Tan k sys systetemm and and    de des scr ibe crib ess the inv entory invent  ory??                                                              the the  ba bassis is for for tha thatt req require uiredd A.
A.      210,0 210    ,0000    gallon 0 gal    lons.
s.
En    su Ensurres        suffici es suf    ficien entt wa water ter to to ma mainta intain  Unit 33 at in Un      at Ho Hot Sta Stan ndb dby con minim min    imuum m of of 2323 hou hours.
rs.                                                    conditi dition on for for aa B.
B.      210,0 210    ,00 00  gallon 0 gal    lons.
s.
Ensur En    sures    suf es sufficificien entt wa water to mainta  intain    Unit 4 at Hot Sta in Un                Stanndb dby condit minim min    imuum m of 23 hours.                                                                ditiion on for a C.      420,0 420    ,00 000 gallonlons.
Thiss is suffic Thi                ficiien entt wa ter to maint  intaain in both Units at these condit    ditiion mi  nim minimuum      m of 15 hou rs and then cool dow                                            onss for a Mode  de 4.                                                  n bot  h rea cto r coo  lan t sys syste tem Mo                                                                                                  mss to D.      420,0 420    ,00 000 gallons.
Th  is  is This suffic      ficiien entt wa ter to maint    ain inta  in both units at these condit    ditiion onss for a minim min    imu  um m of 23 hours.
189 189
 
NRC NR      C DR DRAF  AFT  T                                  07/2 4/07 07/24/  07 Q#95 Q#    95 ANSW AN  SWER  ER::      AA KA KA,;                  G2.1.3 G2  .1.322 Ability Ab  ility to to exp explain lain and and app apply ly all all sys system tem lim  limits its and and preprecau caution tions.s. 3.8 3.8 1OCF 10C  FR R5  5:
55:        43.b.2
: 43. b.2 Refere Re ferenc ncee::      3-OP-0 3-0    P-018.
18.1, 1, Ste Step 4.24.2 Tech Tec  h SpSpecs ecs 3.7 3.7.1.3 O-AD 0-A  DM  M-  536
                                  -53 6,, SeSecctio tion 3/43/4.7.1
                                                                .7.1.3 Cogg Lev Co    Levelel::    22 Co Comp mpreh rehens ension Level Lev    el 2 bec beca aususe the ope opera  rato torr must evaluate the RCS provid vided ed and determine that Unit 3                                            S tem temper peratatuureress is in MoMo  de de  3 and    Un  it 4  is  in Mo
: 4. Only afte  afterr this this determinatio      tionn is made can the operat                                Mode de correct Tec  Tech.
: h. Specs                                                            rato orr  app  ly    the ecs..
New Question Respo spon    se An nse    Analy alysis sis:
A.        Correct per the refe    refere    nce ren  ce B.        Incorrect bec  beca    use there is suffic aus                        ficiien entt water to maint    intaainin only Unitit 3 at these condit  ion ditionss for a min  minim imu umm of 15 hours. Un        Unitit 4 would be on RHR at this temperperatatu ure re and its AFW system valved out                                                        this gallons is the requir                                                  . Plausible be      bec caaus us e  210  ,000 uireedd amount of water inventory in the CSTs.
C.        Incorrect bec  beca  use only 210,000 gallons is the aus inv entory in the CSTs and Un                                            requir uire edd amoun ountt of wa ter Unitit 33 is the onl y unitt tha  tha tt  wo be becca  use Un aus      Unitit 44 would be on RHR at thi                                          uld  needd CS nee      CST T water valved out. Plausible be                                  thiss  tem  per pe  atu rat urere  and and itsits AFW sys  sys bec caaus use the numberss sho                                                    tem tem by the Te                                                              sho    wn wn    are are    the  num  ber  s s provided    ed Tec  chh Spec Basis    sis document    ent..
D.      Incorrect ect bebeccaaususee onl onlyy 210,000 gallonss is invent                                                          is the the req requiruireedd amamoun ountt of of water ter entoryory inin the CS CSTsTs andand UnUnitit 33 isis the the onlonl y y  uni uni tt tha tha tt  wo wo    uld uld    nee nee  d  CS be beccaaus usee Un Unitit 44 wo would uld be be on on RH                                                      d        T CST water      ter RHR    R atat thi thiss  tem tem  per pe  ratatu re ure    and and    its valved ved outout.. Pla Plausi usible ble be                                                          its  AF AF WW    sys sys  tem tem bec caaus usee thethe numberss sho      shownwn areare the by by the the Te Tecchh Spec                                                                  the numberss pro    provid vided ed ec Basissis doc docum ument ent..
190 190
 
NRC NR    C DR DRA AFFT  T                              07/2 07/24/
4/07 07 Q #9 Q#    966 BoBothth Un Units its are are atat 100 100%    powe
                                      % pow    er.r.
The 3A The    3A ED  EDGG isis outout of of ser servic vicee and and aa 1414 day day Tec Techh SpSpec ec Act for Un for    Unitit 3.3.                                                                Actio ionn Sta tem State me ent nt isis inin effe effecctt ECO EC    O req reques  uests    have ts hav      been e bee      subm n sub  mititt ed by ted  by Ma Main inteten nanancece to eq  uip equipment me    nt from from serservic vice:                                          to rem remove ove the the foll owing follow  ing e:
  ** 3A  3A Co Contantainm inmentent Sp Spray ray Pu Pumpmp
  ** 3A  3A EmEmerg  ergenc ency    Conta y Co  ntainm inment ent Filt Filter er
** 3A    3A ReResid sidual ual HeHeatat Re Remomoval val PuPumpmp
** Pre  Press ssu uri  zerr He rize    Heate ater Co Contro ntroll Gro Grou upp IfIf tak taken en outout of of ser servic vice, e, wh which ich ON ONE  E of of the wo    uld red                                              the foll follow owing ing com comp  pon onent ents s from would        reduce  uce the the UnUnit 33 effe effec tivee Tec                                      from the the list list abo abov    vee ctiv    Te  ch h  Sp Sp ec  Ac Acttio ionn  Ti Tim mee  from to    2  ho to 2 hours??  urs                                                                        fro m the  cur cu  ren  t rrent 14 14 daydays s A.
A.          3A Co  Conta ntainm inment ent Spray Pump B.
B.          3A Em  Emergergencencyy Co ntainment  ent Filt Filter er C.          3A Residua      uall Heat Remova    vall Pump D.          Press Pre    ssu uri zer Heaterr Contr rize                      oll Gro ntro    Grouup p 191 191
 
NRC NR      C DR  DRA  AFFT    T                                        0712 07/24/
4/0707 Q#96 Q#    96 ANSW AN    SWER  ER::        BB KA::
KA                      G2G2.2.2
                                  .2.24 4 Ability Ab  ility toto ana analy lyzze    the effe e the      effect ct ofof ma mainteintennan ancece actactivit ivities ies on on LC LCO  D stastatus tus.. 3.83.8 1OCF 10C  FRR5  55:5: 43. 43.b.b.22 Refere Re  feren  ncece::      TS 3.8 TS    3.8.1.1
                                      .1.1,, Act Actio ionn d.1d.1 O-OS O-O    SP  P-0  23. 3,
                                      -023.3, Ste  Step  p 6.16.1.2.2 andand Att Attac achhm meen ntt 22 Ste Step  p 88 Cogg Lev Co      Level el:: 22 com  comp    reh pre    ensio hen    sionn Le vel Level 22 bec  beca    usee the aus      the opeopera ratotorr mu must  st rec recogn ogniz izee that the 3A EC comp com  pononentent and and the  then detdeter                                                              ECF is    is a Train B      B safety erm miinene thethe imp im  pac act t  of of  tha tha  t  pie pie  ce ce ser vic servicee dur during the  the ma mainte                                                            of  equ eq    ipm uip      ent ment being out of inten nanance ce act activi  ty.. The ivity      The SR  SRO mu the Act the  Actio    n  tim  e ion time to 2 hou                                                              mu  st st  ana an    lyz aly  ze e that thisthis reduce  uced d hours rs ifif the the opeopera      torrss pla rato        placedced a Train B while the 3A ED      EDG is    is OOS.                                                                B  saf  ety    com co  mp  pon onent ent OOS    S S.
New Question spon Respo    nsese Analy  alysissis:
A.        Incorrect bec      beca  use 3A Containment aus                                ent Spray Pump is Train A equ                    equip  ipm being out of service will          will not sho  short                                                              meentnt and rten en the TS Act    Ac    ion tio  n  tim  e  from fro  m ass  oc associiat  ate ed    with the EDG to 2 hou d with                                                                                      the    14  day dayss hours  rs.. Pla Pl auusi sibble le  bec be  caaus us  e        ing DOS wi" OO        will intr introd oduucece an add  additio                                                        tak          the 3A CSP itional TS Ac      Acttio ionn time to comply wit 72 hours, not 2 hou        hours                                                                          with h  but      willl be it wil rs..
B.        Correct per  per the ref    refeere ren ncce e C.        Incorrect  ect be bec caaus use 3A Residua          uall Heat Re    Remo  movalval Pu Pump mp is  is Tra Train in A eq an  d and being out of ser          servicvicee wil                                                                      equ  ipm uip  meentnt wi"l not not sh sho ortrten en    the    TS TS    Act Ac  ion tio  n ass assoc  ociiat ateedd witwith h the EDG                                                                tim  e e  from fro  m  the    14 14  day da  yss G to 22 hours.      rs. Pl  Pla auusi sib ble le  bec be ca  aus RHRP  RP DO OOS    S wil                                                                      us  e e  tak tak  ing ing    the the    3A 3A wi"l int intrrod odu  uce ce an an addadditioitional nal TS TS Ac ACtio wil wi"l be                                                                            tionn timee to  to  com com      ply ply    with wit    but itit h but be 77 da    ys ,
days, not  not 22 hou hours. rs.
D.
D.        Incorrect ect be bec  caaus usee thethe pressu  ssuriz  rizeerr con controtroll gro groupup he hea eq equ uip  me ipment  nt an    d bei                                                              ate ters rs areare TraTrain in AA and    being ng out out of of serservicvicee wil wi" l  not not the the 14                                                                          sho sh    rten ort  en    the the    TS TS      Act Ac    ion tio    timee fro n tim      from 14 daday yss assassoc ociiat edd wit ate      withh thethe ED EDG  G                                                                  m the                                                                  to to  22  hou hou  rs.
rs. Pla Pl  auusi sib ble le    bec be  caaus    e  wh the con contro    l trol grogroupup he heaate  rs do ters    do not not ha us  e  wh  ile ile hav vee aa Te Tecchh SpSpec ec LC LCO, O, the the BU  BU he hea  ate  rs wh ters  which ich are are alsalsoo Tra                                                                            Gro Gr  oupup  "A" A
Train in A "A" eqequ  uipipm meent nt dodo and and tak takinging he hea ate  rs OD ters    OOSS wil  wi"l int                                                                          the the    BU BU    Gro Gr oupup    "A" A
intrrod odu  uccee anan add additioitional nal TS TS Ac Act  ion tio wil  l  be will be 72  72 ho    urs                                                                n  tim tim  ee  to to    com com    ply ply    with wit    but h but itit hou  rs,, not not 22 ho hou ursrs..
192 192
 
NRC NR    C DR  DRA AFFT  T                                07/2 4/07 07/24/ 07 Q #9 Q# 977 WhWhic ichh ON ONEEof ofthe thefoll folow lowing ing actactiv ivititi ieses req require uiress dire direc ctt sup Senio Se  niorrRe React actor  Opera erator?                                            supeerv rviisio sionn by by aa lice nse licen  d sed or Op        tor?
A.
A.      Under Un  derw waateterrTV TV camcameerara sur surve veiill  ance llan  ce inin the the refu refueelin lingg cav cavit ityy B.
B.      React Re  actor  vesse or ves  sell irra irrad diaiattion ion spe spec    imen cim  en rem removaovall C.
C.      Lowe Low err inte intern rnaals  remova ls rem  ovall D.
D.      Contro Co ntroll rod rod unl unlat atcch  ing hin g 193 193
 
NRC NR      C DRDRAF  AFT    T                              07/2 4/07 07/24/ 07 Q#97 Q#  97 ANSW AN    SWER ER::        0D KA::
KA                    G2G2.2.2
                              .2.277 Know Kn  owled ledge ge of of the the refu refuel  ing elin    proces g pro  cess. s. 3.5 3.5 IOCF 10C  FRR5  5:
55:        43.b.61b.
: 43.        /b.77 Refere Re ferenc ncee::      4-OP-0 4-0    P-038. 38.1, Ste Step 4.14.1 & & SeSecctio tion 4.64.6 Cog Lev Co    Levelel::    11 rec recall Bank Qu Ba      Quest estion Respo Re  spon nsese Ana Analy  lyssis is::
A.        Incorr Inc  orrect ect bec beca  aususe und erw erwater TV camera surveillan is not considered a Core Alte                                                  ce in the refu refuel elin ingg cavity Altera    tio rati onn and as such doe    doess not requir supervision by an SRO.                                                                        uire  dire e directct Plausible bec  beca aususe this this act activi ivittyy typica direct dire  ctlyly over the core while the                                                      ically lly occurs upp er inte internrnaals ls are removed and irradiated fuel in place.
B.        Incorrect bec  beca    use reactor vessel irradiatio aus                                      tionn specimcimen removal is not consid ered a Core Alt          Alteera tio rati onn and as such doe by an SRO. Plausible bec                                            do es s not requiruire e dir dire  ct superv ect        ervision beca  use thi aus      thiss act act ivi ivit tyy occ  urs dire dir while the reactor head is rem                                                      ectctly ly ove  rr the reactoctor oved.
C.        Incorrect be    beccaaususe lower inteintern rnaals ls remova ovall is not consideredd aa Co Alt Alteera  tio n ration and as suchh do        doe ess not requir                                              re Plausible be                                            uire e dir direect ct sup superv ervisio isio  n  by  an    SR bec caaus use thi  s act this  activi ivittyy occurs dir                                            O.
reacto                                                      direect ctly ly overr the reareacto ctorr while the ctorr headd and upper int        inteern rna als ls are removed.
D.      Correct per the ref            ere refe  nce ren ce 194 194
 
NRC NR    C DR  DRA  AFFT T                                07/2 07/24/
4/07 07 Q#98 Q#  98 Core Co  re off-off-lo loaadd isis inin pro progre gress ss on on UnUnitit 3.
3.
  ** OnOnee fue fuell ass assembly    bly isis latc latch heded on on the
* the mamanip nipula ulator tor cra crane.
ne.
An  oth
* An oth er fueer fuell ass assembly  bly isis ver vertica ticall in in the the upe upennde derr on on the the SpSpent ent Fue Fuell Pit Pit sid side.e.
AA refu refuel  ing  cav eling cavity  ity sea seall fail failur uree occ occu  rs and urs    and cav cavity ity lev level el beg begininss dec decre reaasi sinng g raprapidly idly..
Which Wh  ich ONONEE of of the the foll follow  ing des owing      descr  ibe crib  ess the the cor corre recctt ope operarato torrs' s res respon pons seses??
A.
A.          Insert Ins  ert the the assassembly  bly onon the the ma manip nipula ulator into into the the cor Lay the Lay    the ass assembly                                                    core e and and lea leave ve itit latc latched hed.
in bly in thethe upe upennde derr dow downn and and lea leave itit in in the the tran transsfe ferr car cart.
B.
B.        Insert Ins  ert the the assassembly on      on the the ma manip nipulator into into thethe cor Relatc Re  latch    the    ass h the assembly in core e and and unl unlatc atch it.it.
in the the upe upen  ndeder and and momove it to a fue    fuel rac rack.
k.
C.
C.        Do NO Do    NOT Ins  Insert the assembly      bly on the manipulator into        into the cor the edg edge e of of the corcore                                                          coree but move it to e and leave it sus    su sppen en ded de  d..
Lay the assem Lay                embly bly in the upe  upenndeder down and leave it in the tra nsf er cart.
nsfer D.        Do NOT Ins ert the ass        assememblybly on the manipulator into      into the cor nsfer transf      canaal.
er can      l.                                                                coree but move it to Relatc latch h the ass  assem embly bly in the upeupen    der and move it to a fuel rac nde k.
195 195
 
NRC NR    C DR DRA  AFFT  T                                  07/2 07/24/
4/07 07 Q #9 Q#  988 ANSW AN    SWER  ER::      AA KA::
KA                  G2G2.3.1
                              .3.1O 0 Ability Ab ility toto per perform form pro  proced cedu  res ure s toto red reduce uce excexce ess ssiive ve lev levels again aga  insstt per perso sonnn    el exp expo                                                  els of of rad radiati iation on andand gua guard rd nel          su osure.re. 3.3 3.3 I OCFR 10C    FR55:55:      43.b.41b.
: 43.      /b.77 Refere Re  feren    ce::
nce        3ONOP-0 3-0        P-O3    3.2
: 33. 2,, Ste Step    5.1.2, p 5.1  .2, 5.1 5.1.3.3  &
                                                                            & NONOTE TE Pri Prior or to to Ste Step p 5.2 5.2.4
                                                                                                                    .4 Cogg Lev Co      Level el::    1I Re Recalll New Qu Ne      Quest estion Respo Re  spon    se An nse    Analy alysis sis:
A.        Corre ct per per the referefererennc e.
ce.
B.          Incorrect Inc      ect bec beca aususe the ope opera    torr sho rato    shouuldld lay the ass  assememblybly in the upe an andd leave it in the tran    transsfe ferr cart. Pla                                                upen  nde der down Plau usi sibble le  bec be  caaus us e  ope op erarato torrs  sho assem the ass        bly embly on the manipulator into                                                      s  sh ouuld ld  insert into the cor coree but shoshouuldld leave it latc latch hed ed.
C.        Incorrectect bec beca    use ope aus    opera    torrss sho rato      shouuldld insert the ass  assemembly bly on the manipulator into the cor into        core    and leave it latc e and                latch  ed. Pla hed      Plauusisibble le  bec be  aus ca us e  the ope the assassememblybly in the upe  upen                                                      opera rato torr sh shoouuld ld lay der down and nde              and leave it in the trans        nsffer er cart.
D.        Incorrect ect bebecca  use op aus          era ope    torrss sh rato      shoouuld ld insert the ass  assemembly int intoo the co corree an  d leave it lat                                            bly on the ma    manip nipula ulator tor and                latcchhed ed an and d  bec be  ca aus us ass assem  embly e  the  ope op    rato era  tor r sho sh    uld ould lay the bly in the up  upe ennde derr do dow wnn an and d leave itit in be bec  ca use un                                                        in the tra trannssfe fer r car car  t.
: t. Pla Pl auusi sibble aus      unllat atcchh the assassemembly bly heldd by the ma                                                le ass assem                                                                ma  nip nip  ula ula tor tor  and an  d  rela rel  tch atc    ing hin emblybly in the up  upe ennde derr an andd move  ve itit to aa fue g  the op  enn to the op                                                  fuell rac rackk are are bot bothh workable    ble opopttio ion ope                ope era  torrs rato  s but but neneiith theerr is                                                                nss is dir direeccte tedd by by ONOP-03    -033.2 3.2..
196 196
 
NRC NR    C DR DRA    AFFT  T                              0712  4/07 07/24/  07 0#Q #9 999 UnUnitit 33 has has exp expe    rience erie  nced d aa loslosss of of offs offsite ite powpower  er(LO (LOOP OP).).
  ** The The 38  3B ED  EDGG has has eneenerg rgizize edd the the 38 3B 4K4KVV bus  bus asas des desig ignne ed.
** 3A  3A ED  EDGG loc  locked ked out out andand can can NONO  T  be d.
* SI  wa                                              T  be    res res  tar tart ted ed. .
* SI was NO      s    NOTT req require uiredd and and did did NONOTT occoccur. ur.
Which Wh    ich ON  ONEE of  ofthethe foll folow lowinging desdescr  ibe crib ess the the mit mitig igaatio tionn stra strate 3-E 3-EOP  OP-ES  -ES--O. 0.2  ,  N 2, "Naturaatu rall Cir                                                teggie iess pro provid videded by by Circulculatio ationn Co Coold oldow own,"
n, for for the the pre presen sentt pla plant nt con cond diti itions ons??
Limitit the Lim        the RCRCSS coo  cooldo ldown wn rate rate to:
to:
A.
A.            25&deg;F 25&deg;  F/h  /hrr and and ma mainta intainin RCRCSS sub subcoolin  lingg ~ 80&deg; 80&deg;FF toto avo the rm thermaall sho  shoc  kin                                                      avoid the the pos possibilit ilityy of of cki ngg the the reareactorr ves vessesell..
B.
: 8.          25&deg;F 25&deg;  F/h /hrr and and ma mainta intain    RCSS sub in RC      subcoolin  lingg ~ 226226&deg;F to to avo reactorr ves rea          vesse                                                              avoid the the pos  sibilit possib    ilityy of of sell hea head  d voivoidd form forma  tion.
atio  n.
C.
C.          60&deg;F 60&deg;  F/h/hrr and and ma mainta intain in RCRCS S subcoolin  lingg  ~  80&deg;F to avoid the pos the  rmall sho therma          shocckikin ngg  the                                                              sibilit possib  ilityy of reactor vesvessesell....
D.          60&deg;F 60&deg;  F/h/hrr and and mainta intain in RCS subcoo    coolin ling  g ~  226&deg;F to avoid the pos reactor ves  vessesell hea head  d voi d formforma                                              possib sibilit ility y of tion.
atio 197 197
 
NRC NR    C DR  DRA  AFFT  T                                          07/2 07/24/4/0707 Q #9 Q#  999 ANSW AN    SWER  ER::        BB KA KA                    G2G2.4.7.4.7 Know Kn  owledledgege of of the the eveeven ntt basbaseded EO  EOP P mitmitig igaatio tionn stra strate teggie iess.. 3.8 3.8 IOCF 10C  FR R5  5:
55:          43.b.
: 43. b.55 Refere Re  feren  ce::
nce          3-EOP 3-E    OP-ES-ES--0. O.2,2, Ste Step p 1010,,1717,,18  18 Cogg Lev Co      Levelel:: 22 Co    Comp mpreh rehensensiv Le                                                ivee vel  2  be Lev el 2 becca    aus usee the the SRSRO  O mumust  st rela relate    the los te the      losss ofof the the 3A plant pla  nt con cond  itions diti  ons and and det deter                                                    3A 4K 4KV V busbus to  to the the pre presensentt erm miinene tha tha  t t  onl onl  y y  on one  e  CR CR    DM DM the n  mu  st  rel the n mu st relaate            this kno                                                        co coo  oli ling ng  fan fan    is is  ava av    ilab ailab    le. He te this      know  wleled dge ge toto the the effe effec ctsts the                                                          He natur nat  uraall circ circu  lattion ion coo                                                  the CR CRDM coo    co    ling oli ng    fan fan  s s  hav ha    e  on ula            cooldldoow wnn andand det deter erm miinene thathatt the ve    on aa higher hig  her sub subccoo oolin                                                              the    low low  er er  coo co    ldo old  ow  wn n  rate rat    s  and es and mu lingg num numb  berers    must s mu    st be be appappli  ed for lied    for the giv                                                      much ch remova rem  ovall fro fromm thethe rea  reactor hea                                                givenen plapla  nt con co    ndditi iti ons on  s  as as    hea  t head  d isis dim diminis inishheded wit withh onl y one                                              he  at one CRDM fan ..
New Ne  w QuQuestestion Respo Re  spon    se Ana nse    Analy  lyssisis::
A.
A.          Incorr Inc  orrect ect becbeca    use ope  opera aus              rattor orss sho shouuld ld maint  intaainin RCS sub av oid avoid      the    possi pos    bilility ity of reactor ves                                          subccoo  oolinling g ;::: 226&deg;&deg;F    F toto sib                          vesse sel l  he hea add  voi be becca  use ope aus        opera                                                              d  form for  ma atio tio  n. Pla    usi Plausibble    le rattor orss shoshouuld ld limit the RC S coo        coold ldoow wnn rate rate to 25  25&deg;&deg;F  F/h/hrr..
B.
B.        Correct per Co            per the refe  refere  renncce e C.        Incorrec ectt be bec  caaus use op  ope  era ratotorrss sh sho ouuld ld limit the RCS co an  d maint                                                                                coo  ldo old  ow wn n ratrate e to 25  25&deg;  &deg;FF/h and              ain inta in RCS su        sub bccoo oolin  g 2 22 ling      2266&deg;  F                                                                  /hrr ve  sse                                                          &deg;F    to to  av avo oid id  the the  pos po  ssisib bilility ity    of  rea ves sell he  hea add void for    form maatio tion. Pl  Plaauusi                                                    of reacto    ctorr 80                                                          sibble le be bec caaus usee ma maintintaaininin ing g  sub    coo 80&deg; &deg;FF is    an is an app  ap  pro roppri  atee str riat          ate                                                            su  bc    oo  ling lin  g>>
stra      gyy ifif bo teg        botthh CRCRDM  DM    co coo olelers rs  are 60  &deg;F 60&deg; F/h /hoourur is is an an attattaain  abble                                                    are    in in    ope op      rati eration anon    and d ina    le cocoooldldoowwnn rat rate e tha thatt mi mig  ght ht be be viewe co con nssid ideerin ringg the the off                                                                          we    d d  as as    app ap  proroppririat atee off--no norrm ma all ev eve ennt.
t.
D.
D.        Incorrec  ectt be bec caaususee op ope  era  torrs rato    s sh sho ouuld ld lim limitit the the RC RCSS co Pl  au sibble                                                                              coooldldoow wnn rat ratee to to 2525&deg; &deg;FF/h Pla usi    le be bec  caaususee op ope era rat tor s sh ors  shoouuld ld                                                                      /hrr avo                                                              ma ma    int inta ainin  RC RC    S S  sub su  bc coo oo    ling lin    g      226 avoid id the the po      ssi pos sib  bilility ity of of rea reacto ctorr ve 2  22  6&deg;  &deg;F F    to to an ves sse sell he hea  add voi voidd for formmaatio tionn an and      60&deg; an att  ain atta  inaabblele co coooldldoow  n wn ratrate e tha                                                        d  60  &deg;F F/h
                                                                                                                                      /ho  our ur  isis thatt mimigghtht bebe vieviewewedd as as apapp    rop the the off off--no nor rm    al ma l eveev ennt.t.                                                              pro  pri riat ate e    con co  ns  sid ide  erin rin  gg 198 198
 
NRNRC  C DR  DRA  AFFT  T                                07/2 07/24/
4/07 07 QQ #10
      #100  0 UnUnitit 44 has has exp expe    rience erie    ncedd aa larg large  break e bre    ak LOLOCA CA andand con contatain at 28 at  28 psipsig.
: g.                                                                        inmmeen ntt pre pressu ssurere has has pea peak ked ed The Em The      Emergergencencyy Co Coord ordina inator tor (EC (EC)) has has NO  NOTT yetyet rec receiv eiveded any rad ioa radioactivvecti      relea e rele  ase ses  fro m                                                    any ind indica ication tion ofof pot enttia poten    iall s from Co  Contantainm inment ent..
Which Wh    ich ON ONEE of  of the the foll folow lowing ing des descr  ibe crib  ess the the ProProte teccti tive ve Act Actio (P
(PA ARR)) thethe ECEC sho shou    ld ma                                                      ionn Re Recom comm meen nda dation tion uld  makeke dur durin ingg init initial    conta ial con  tacctt wit withh the the Sta St te?
ate?
A.
A.            No PA No    PAR  R sho shou  ld be uld    be ma madede unt untilil con confi    rmatio firm  ation n of of aa rad radioa ioactiv ctive e rele rel ase ease isis ma made.
de.
B.
B.          Shelte Sh  elterr all all per perso sonns  within s wit  hin aa 22 mil mile    radius e rad  ius ofof the the site ou t  to out to 55 milmiles      in the                                              site and and she shelt lter er all all per  sonns perso    s es in  the dow down  nwwiind nd secsectors tors..
C.
C.          Evac Eva  cuauate allall per perso sonns  within s wit  hin aa 22 milmile e rad radius of of the site ou outt to to 55 mil miles    in the dow                                              site and and she sheltlter er all all per persosonns s es in        down  nwwiind nd secsectors tors..
D.
D.          Evac Eva    uate all cua      all per persosonns  within s wit  hin a 2 mil  milee radius of the site perso per sonns    ou  t to s out 5 mil    miles                                              site and and eva evac cuauate all es in the dowdown    nwwiind nd sectortorss..
REFERENCE PROVIDED IDED 199 199
 
NRC DR NR        DRAFT                                              07/24/
0712 4/07 07 Q#10 Q#  1000 ANSW AN  SWER ER::      BB KA::
KA                    G2.4.4 G2  .4.44 Know Kn  owledledge ge ofof em emergergency pla  plan pro protec tective tive actaction recrecomomme mendandationtions.s. 4.0
 
==4.0 100FR55==
10C                  43.b.5 43.
Refere Re  ferencncee::    3-EPIP 3-E    PIP-20
                                  -201101 01,, En Enclo closur sure 1,  1, Category 11 (Ge    (Gene 3EPlP                                                                nerralal Em Emergergency) 3-E  PIP-20-20101, Step 5.1    5.1.4 3-EPIP 3-E    PIR-202O101IOI,, Att Attach achment 3,    3, Pa Paggee 11 of 6 Cog LevLevelel::        compre 2 com      prehension Level Lev        becaus el 2 bec      ause the operator mu st det erm with 28 psig inside con tainme                          ine that the combination of a larg            large LO CA wit                                                                                                              e break Th                                                    nt  as  cla  ssifia fiabble le as    a  Ge    ner  al en The n the ope rator mu      must recall that the min                                                      Em Em    erg ency.
withou                                                    minim  imuumm classific  ficaatio tionn  for  a  GE wit hout a rele releas    e ase is "Sh Shelter all persons within                                                    ,  eve  n persons out to 5 mil all per                                                                      mile a 2 mil    e radius of the site and shelter miles es in the downwind sector          torss.
Provide EPIP-20101, En            Encloclosur sure e1 I as a Refer    ferenc ence New Qu estion Respo nse An    Analyalysis sis:
A.        Inc orrect because the EC should issue the PAR to she        shelterlter all persons within milee radius of the site and she a 2 mil lter lter all persons out to 5 mil        mileses in the downwind sector        torss.. Plausible because there is radioactive rele                                                          no indicatio    tionn  of  potent ential ial releasase ess fro fromm Containment.
B.        Correct per the refe    refererennce ce C.        Incorrect because the EC sho should uld issue the PAR to she          shelte lterr all persons within a 2 mil milee radius of the site and she        sheltelterr all persons out to 55 mi          milles es in the downwind sec    sectortorss.. Plausible because evacua conser                                                            cua  tio tion n  cou cou  ld ld  be  con  sideredd more servat vative ive than she  shelter ltering ing in the event                                                              re nt of aa Gener neral al Emergenc    ency.y.
D.      Incorrect because the EC sho            should uld issue the PAR          R to she shelterlter all aa 22 mi millee radius of the site and                                                          all personss wit  with in hin and she sheltelterr all personss out to      to  5 downwind    ind sec sector torss.. Plausible becausee eva                                    5  mi milles es  in in  the the conser                                                        evacua cuatio  n cou tion  could ld bebe consideredd more servatvative ive thann she shelter ltering ing in in the the eve                                                              re event  nt of aa Gener neralal Emergenc    ency. y.
200 200}}

Latest revision as of 04:38, 14 January 2025

301 Reactor Operator Written Exam (Section 2)
ML101590396
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 03/28/2010
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NRC/RGN-II
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