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| number = ML101620366
| number = ML101620366
| issue date = 03/28/2010
| issue date = 03/28/2010
| title = 2005-301 Final SRO Written Exam (Section 9)
| title = 301 Final SRO Written Exam (Section 9)
| author name =  
| author name =  
| author affiliation = NRC/RGN-II
| author affiliation = NRC/RGN-II
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:76. 002A2.04 OO1l212/RCS/C/A (4.3/4.6)lN/SM05301lSIRFAlSDR A large LOCA has occurred.
{{#Wiki_filter:76. 002A2.04
Which ONE of the following actions are corrrect given the following conditions:
: 76. 002A2.04 OO1l212/RCS/C/A 00 l/2/2/RCS/C/A (4.3/4.6)lN/SM05301lSIRFAlSDR (4.3/4. 6)/N/SM0530 l/S/RFAJSDR AA large large LOCA LOCA has has occurred.
RWST level is 17% and continues to decrease.
occurred. Which Which ONE ONE of  of the the following following actions actions are are corrrect corrrect given given the the following    conditions:
RHR sump level is 410 feet and increasing.
following conditions:
All RCPs were tripped (by procedure) when RCS pressure dropped below 1400 psig The crew is currently performing the actions of EOP-2.0, LOSS OF REACTOR OR SECONDARY COOLANT The following EOPs are being considered:
* RWST level RWST       level isis 17%
EOP-2.2, TRANSFER TO COLD LEG RECIRCULATION
17% andand continues continues to  to decrease.
* EOP-2.4, LOSS OF EMERGENCY COOLANT RECIRCULATION Transition to: A. EOP-2.4 from EOP-2.0. When RHR sump level reaches the required level, transition to EOP-2.2. B. EOP-2.4 from EOP-2.0. When RHR sump level reaches the required level, return to EOP-2.0 and transition to EOP-2.2. C. EOP-2.2 from EOP-2.0 then transition to EOP-2.4. When RHR sump level reaches the required level, return to EOP-2.0 and transition to EOP-2.2. Dyo EOP-2.2 from EOP-2.0 then transition to EOP-2.4. When RHR sump level reaches the required level, transition back to EOP-2.2. Feedback Distractor analysis:
decrease.
A and B. Incorrect:
* RHR     sump level RHR sump        level isis 410 410 feet feet and and increasing.
The transition is not made directly to EOP-2.4 from EOP-2.0 unless coolant recirculation was established and subsequently lost, this is not the case. C. Incorrect:
increasing.
The transition from EOP-2.4 is made back to the procedure step in affect which would have been in EOP-2.2 not EOP-2.0. D. Correct.  
* All RCPs All RCPs werewere tripped tripped (by (by procedure) procedure) when  when RCS RCS pressure pressure dropped dropped below below 1400 1400 psig psig
* The crew The    crew isis currently currently performing performing the the actions actions ofof EOP-2.0, EOP-2.0, LOSS LOSS OF REACTOR OR OF  REACTOR        OR SECONDARY COOLANT SECONDARY             COOLANT The following The    following EOPs EOPs areare being being considered:
considered:
* EOP-2.2, TRANSFER EOP-2.2,     TRANSFER TO        TO COLD COLD LEG  LEG RECIRCULATION RECIRCULATION
            **    EOP-2.4,    LOSS      OF  EMERGENC EOP-2.4, LOSS OF EMERGENCY COOLANT RECIRCULATIONY  COOLANT        RECIRCULATION Transition to:
EOP-2.4 from A. EOP-2.4         from EOP-2.0.
EOP-2.0. When    When RHRRHR sumpsump level level reaches reaches the the required required level, level, transition transition to to EOP-2.2.
B. EOP-2.4 from EOP-2.0. When RHR sump level reaches the required                        required level, return to EOP-2.0 and transition to EOP-2.2.
C. EOP-2.2 from EOP-2.0 then transition to EOP-2.4. When RHR sump level reaches the required level, return to EOP-2.0 and transition to EOP-2.2.
D EOP-2.2 from EOP-2.0 then transition to EOP-2.4. When RHR sump level reaches the Dyo required level, transition back to EOP-2.2.
Feedback Feedback Distractor analysis:
A and B. Incorrect: The transition is not made directly to EOP-2.4 from EOP-2.0 unless coolant recirculation was established and subsequently lost, this is not the case.
C. Incorrect:
Incorrect: The transition from EOP-2.4 is made back to the procedure step in                        in affect which would have been in EOP-2.2 not EOP-2.0.
D.
D. Correct.
 
==Reference:==


==Reference:==
==Reference:==
EOP      EOP 2, 2, page page 44 of  of 32 32 EOP EOP 2.2, 2.2, page page 33 of  of 13 13 EOP    2.4,  page EOP 2.4, page 4 of    4    29 of 29 KIA CATALOGU K/A    CATALOGUE        E QUESTION QUESTION DESCRIPTI DESCRIPTION:    ON:
    - Reactor Reactor Coolant Coolant System System (RCS);(RCS); Ability    to (a)
Ability to  (a) predict predict the the impacts impacts of  the following of the  following malfunctions malfunctions or or operations operations on  on the the RCS; RCS; and        (b) based and (b)    based on    those predictions, on those    predictions, use use procedures procedures to  to correct, correct, control, control, or or mitigate mitigate thethe consequence consequences      s of of those those malfunctions malfunctions or  or operations:
operations: Loss Loss ofof heat heat sinks.
sinks.
Categories Categories Tier:
Tier:                  22                                            Group:
Group:            22 Key  Word:
KeyWord:              RCS RCS                                          Cog Level:
Cog  Level:        C/A CIA (4.3/4.6)
(4.3/4.6)
Source:
Source:              NN                                            Exam:
Exam:              SM05301 SM05301 Test:
Test:                  SS                                            Author/Reviewer:
Author/Reviewer:  RFAJSDR RFAlSDR
: 77. 003A2.03
: 77. 003A2.03 002/211IRCPS/CIA 002/2/1/RCPS/C/A(2.7!3.        1 )/N/SM0530 1/S/RFAJSDR 2.7/3.1INISM0530IlSIRFAlSDR This    Question This Question DELETED  DELETED The following The    following conditions conditions exist:
exist:
Reactor Power
        - Reactor
          -            Power isis 9%.9%.
        - AA Total
          -            Loss of Total Loss      of All All Service Service WaterWater has has occurred.
occurred.
AOP-1    17.1,  Total  Loss  of  Service
        - AOP-117.1, "Total Loss of Service Water," has
          -                                                  Water,    has been been entered.
entered.
RCP    temperatures        are
        - RCP temperatures are beginning to
          -                                beginning      to rise.
rise.
Service Water
        - Service
        -            Water can  can not not be be restored.
restored.
Which ONE Which      ONE of  of the the following following describes describes the the action(s) action(s) the the operators operators must must take  and .the take and  the sequence sequence of those    actions    (in  accordance of those actions (in accordance with AOP-117.1)?with AOP-1    17.1)?
A.v    Initiate aa reactor A Initiate        reactor plant plant shutdown shutdown per  per GOP-4B, GOP-4B, POWERPOWER OPERATION OPERATION (MODE(MODE 11 - -
DESCENDING). Stop DESCENDING).              Stop upup to    TWO RCPs.
to TWO      RCPs. Isolate Isolate unnecessary unnecessary CCW COW loads, loads, and and ensure ensure FS FS
* is is aligned to the DIGs. D/Gs. When an      an RCP RCP motor motor bearing bearing temperatures or    lower seal water or lower bearing temperature exceeds the specified limit, bearing                                                    limit, stop the affected RCP.
RCP.
B. Initiate a reactor B. Initiate        reactor plant plant shutdown per    per GOP-4B, GOP-4B, POWERPOWER OPERATION OPERATION (MODE(MODE 11 - -
DESCEN        DING).
DESCENDING). Isolate unnecessary CCW loads, and ensure FS is aligned to the DIGs.
Secure an RCP only if motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit.
C. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 11 -                              -
DESCENDING). Stop at least TWO RCPs. Isolate unnecessary CCW loads, and ensure DESCENDING).
ES is aligned to the DIGs.
FS                          D/Gs. When the running RCP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, increase monitoring and continue pump operation until the unit is shutdown then stop the affected pump.
D. Stop ONE RCP. Initiate aa reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 11 - DESCENDING).
                        -  DESCENDING). When an RCP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, trip the reactor and stop the affected RCP.


EOP 2, page 4 of 32 EOP 2.2, page 3 of 13 EOP 2.4, page 4 of 29 KIA CATALOGUE QUESTION DESCRIPTION:  
Feedback Feedback Distractor Analysis:
-Reactor Coolant System (RCS); Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Distractor    Analysis:
Loss of heat sinks. Categories Tier: 2 Group: 2 KeyWord: RCS Cog Level: CIA (4.3/4.6)
A. Correct:
Source: N Exam: SM05301 Test: S Author/Reviewer:
A. Correct: lAW      AOP-1 17.1, the lAW AOP-117.1,         the reactor reactor should should be be shutdown shutdown (not  (not tripped).
RFAlSDR 
tripped). Secure Secure upup to to TWO TWO RCPs (Step RCPs      (Step 12).
: 77. 003A2.03 002/211IRCPS/CIA 2.7/3.1INISM0530IlSIRFAlSDR This Question DELETED The following conditions exist: -Reactor Power is 9%. -A Total Loss of All Service Water has occurred.
12). TheThe affected affected RCPRCP should should bebe shutdown shutdown ifif RCP RCP motor motor bearing    temperatures bearing temperatures exceeds 195 exceeds      195 of°F oror lower lower seal seal water water bearing bearing temperature temperature exceeds exceeds 2250F 225°F (Step (Step 13).
-AOP-117.1, "Total Loss of Service Water," has been entered. -RCP temperatures are beginning to rise. -Service Water can not be restored.
13).
Which ONE of the following describes the action(s) the operators must take and .the sequence of those actions (in accordance with AOP-117.1)?
B. Incorrect:
A.v Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1 -DESCENDING).
B. Incorrect: Do Do not not wait wait until until temperature temperature are are exceeded exceeded to     secure RCPs to secure    RCPs C. Incorrect:
Stop up to TWO RCPs. Isolate unnecessary CCW loads, and ensure FS is aligned to the DIGs. When an RCP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, stop the affected RCP. B. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1 -DESCENDING).
C. Incorrect: Step Step 12 12 allows allows two two RCPs RCPs to to be be stopped stopped ifif plant plant conditions conditions permit.
Isolate unnecessary CCW loads, and ensure FS is aligned to the DIGs. Secure an RCP only if motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit. C. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1 -DESCENDING).
permit. Prudent Prudent action action is to is      shutdown with to shutdown   with 22 RCPs RCPs running running and     secure one and secure    one ifif necessary necessary for for temperature.
Stop at least TWO RCPs. Isolate unnecessary CCW loads, and ensure FS is aligned to the DIGs. When the running RCP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, increase monitoring and continue pump operation until the unit is shutdown then stop the affected pump. D. Stop ONE RCP. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1 -DESCENDING).
temperature.
When an RCP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, trip the reactor and stop the affected RCP.
Feedback Distractor Analysis:
A. Correct: lAW AOP-117.1, the reactor should be shutdown (not tripped).
Secure up to TWO RCPs (Step 12). The affected RCP should be shutdown if RCP motor bearing temperatures exceeds 195 of or lower seal water bearing temperature exceeds 2250F (Step 13). B. Incorrect:
Do not wait until temperature are exceeded to secure RCPs C. Incorrect:
Step 12 allows two RCPs to be stopped if plant conditions permit. Prudent action is to shutdown with 2 RCPs running and secure one if necessary for temperature.
D. Incorrect:
D. Incorrect:
Shutdown is initiated in step 3 and Step 12 secures the RCP. Reactor is not tripped unless above P-7.  
D. Incorrect: Shutdown Shutdown isis initiated initiated inin step step 33 and and Step Step 12 12 secures secures the the RCP.
RCP. Reactor Reactor isis not not tripped unless unless above above P-7.P-7.


==References:==
==References:==
GOP-4B


GOP-4B AOP-117.1, page 8 AOP-118.1, page 5 KIA CATALOGUE QUESTION DESCRIPTION:  
==References:==
-Reactor Coolant Pump System (RCPS); Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
GOP-4B AOP-117.1, page 8 AOP-118.1, page page 55 K/A CATALOGUE KIA     CATALOGUE QUESTION DESCRIPTION:    DESCRIPTION:
Problems associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems.
- Reactor Coolant Pump System (RCPS); Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures consequences of those malfunctions or operations: Problems to correct, control, or mitigate the consequences associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems.
Facility POST EXAM comment resulted in this question being DELETED from the exam. The correct sequence is not contained in any of the distractors, so there is no correct answer. The question was originally constructed and proposed by the NRC to contain only a list of the actions taken in the AOP without regard to sequence.
Facility POST EXAM comment resulted in this question being DELETED from the exam. The correct sequence is not contained in any of the distractors, so there is no correct answer.
The NRC agreed to the addition of the "sequence" requirement and the inclusion of more of the sequence at the request of V. C. Summer. Categories Tier: 2 Group: 1 KeyWord: RCPS Cog Level: C/A(2.7/3.1)
The question was originally constructed and proposed by the NRC to contain only a list of the actions taken in the AOP without regard to sequence. The NRC agreed to the addition of the sequence "sequence" requirement and the inclusion of more of the sequence at the request of V. C.
Source: N Exam: SM05301 Test: S Author/Reviewer:
Summer.
RFAlSDR 
Categories Categories Tier:
: 78. 005G2.1.27 OOII2/l/RHRIM (2.812.9)/N/SM05301/SIRFAlSDR Which ONE of the following correctly describes the purpose and or function (not all inclusive) of the RHR system and one of its Mode 4 Technical Specification requirements?
Tier:                22                                        Group:               1I Key    Word:
A. Hot Leg Recirculation, Refueling Cavity Cooling, Alternate Water supply to Reactor Building Coolers, Pressurizer Relief Tank Cooling. RHR can be deenergized for up to 2 hour provided that core outlet temperature is maintained at least 50°F below saturation temperature.
KeyWord:             RCPS                                     Cog Level:
B. Cold Leg Recirculation, Hot Leg Recirculation, Simultaneous Cold Leg -Hot Leg Recirculation, Alternate Water supply to Reactor Building Coolers. RHR can be deenergized for up to 1 hour provided that core outlet temperature is maintained at least 100F below saturation temperature.
Level:          C/A(2.7/3.l)
C. Refueling Cavity Draining, Cold Overpressure Protection, Simultaneous Cold Leg -Hot Leg Recirculation, Pressurizer Relief Tank Cooling. RHR can be deenergized for up to 2 hour provided that core outlet temperature is maintained at least 50°F below saturation temperature.
C/A(2.7/3.1)
D)/ Cold Leg Recirculation, Refueling Cavity Draining, Cold Overpressure Protection, Cold Leg Injection.
Source:
RHR can be deenergized for up to 1 hour provided that core outlet temperature is maintained at least 10°F below saturation temperature.
Source:              N                                         Exam:               SM05301 SM05301 Test:                 SS                                        Author/Revi  ewer: RFAISDR Author/Reviewer:     RFAlSDR
Feedback Distractor Analysis:
: 78. 005G2.1.27
A. Incorrect:
: 78. 005G2. 1.27 OOII2/l/RHRIM 001/2/1 /RHRJM (2.812.9)/N/SM05301/SIRFAlSDR (2.8/2.9)/N/SM0530 1/S/RFA/SDR Which ONE Which    ONE of    the following of the   following correctly correctly describes describes the the purpose purpose andand or or function function (not (not all all inclusive) inclusive) of the of   the RHR RHR system system and  and one one ofof its its Mode Mode 44 Technical Technical Specification Specification requirements?
Hot Leg Recirculation, Alternate Water supply to Reactor Building Coolers, Pressurizer Relief Tank Cooling are all incorrect functions.
requirements?
RHR can be deenergized for up to 1 hour provided that core outlet temperature is maintained at least 10 0 F below saturation temperature.
A.A. Hot   Leg Recirculation, Hot Leg  Recirculation, Refueling Refueling Cavity Cavity Cooling, Cooling, Alternate Alternate Water Water supply supply to to Reactor Reactor Building Building Coolers, Pressurizer     Relief   Tank   Cooling.
B. Incorrect:
Coolers, Pressurizer Relief Tank Cooling. RHR can      RHR   can bebe deenergized deenergized for for up up to to 22 hour hour provided that provided  that core core outlet outlet temperature temperature isis maintained maintained at at least least 50°F 50°F below below saturation saturation temperature.
Hot Leg Recirculation, Alternate Water supply to Reactor Building Coolers are incorrect functions.
temperature.
C. Pressurizer Relief Tank Cooling is an incorrect function.
B. Cold B. Cold Leg Leg Recirculation, Recirculation, Hot  Hot Leg Leg Recirculation, Recirculation, Simultaneous Simultaneous Cold Cold Leg Leg - Hot
D. Correct answer  
                                                                                                        -  Hot Leg Leg Recirculation, Alternate Recirculation,      Alternate Water Water supply supply to  Reactor Building to Reactor   Building Coolers.
Coolers. RHR RHR can can be be deenergized for deenergized      for up up to    hour provided to 11 hour   provided that that core core outlet outlet temperature temperature isis maintained maintained at  at least least 10°F  below    saturation    temperature.
100F below saturation temperature.
C. Refueling Cavity C. Refueling    Cavity Draining, Draining, Cold Cold Overpressure Overpressure Protection, Protection, Simultaneous Simultaneous Cold  Cold Leg Leg - Hot
                                                                                                                      -  Hot Leg Leg Recirculation, Pressurizer Recirculation,     Pressurizer Relief Relief Tank Tank Cooling.
Cooling. RHRRHR can be  be deenergized for up      up to 22 hour hour provided that provided  that core    outlet temperature core outlet   temperature is     maintained at is maintained        least 50°F at least 50°F below below saturation saturation temperature.
D Cold Leg Recirculation, D)/               Recirculation, Refueling Cavity Draining, Cold Overpressure Protection, Cold Leg Injection. RHR can be deenergized for up to 11 hour provided that core outlet temperature is maintained at least 10°F below saturation temperature.
Feedback Feedback Distractor Analysis:
A. Incorrect: Hot Leg Recirculation, Recirculation, Alternate Water supply to Reactor Building Coolers, Pressurizer Relief Tank Cooling are all incorrect functions. RHR can be deenergized for up to 11 hour provided that core outlet temperature is maintained at least 10°F                100 F below saturation temperature.
B.
B. Incorrect: Hot Leg Recirculation Recirculation,, Alternate Water supply to Reactor Building Coolers        Coolers are incorrect functions.
C. Pressurizer Pressurizer Relief Tank Cooling Cooling is is an an incorrect incorrect function.
D. Correct D. Correct answer answer
 
==References:==


==References:==
==References:==
AB-7,AB-7, RHR  RHR system, system, pagepage 99 AB-2, AB-2, RCS,RCS, page page 99 lB-i, IB-1, SW SW System, System, pagepage 1717 TS    3.4.1.3,  page  237 TS 3.4.1.3, page 237 and 241  and  241 K/A KIA CATALOGU CATALOGUE      E QUESTION QUESTION DESCRIPTI DESCRIPTION:  ON:
    - Residual Residual Heat Heat Removal Removal System; System; Knowledge Knowledge of  of system system purpose purpose andand oror function.
function.
Categories Categories Tier:
Tier:                22                                      Group:
Group:              11 Key    Word:
KeyWord:              RHR RHR                                      Cog Level:
Cog  Level:        M (2.8/2.9)
M  (2.8/2.9)
Source:
Source:              NN                                      Exam:
Exam:                SM05301 SM05301 Test:
Test:                SS                                      Author/Revie AuthorlReviewer:
wer:  RFAlSDR RFA/SDR
79.007A2.03
: 79.                002/2/1 /PRT PRESSURE/C/A 007A2.03 0021211IPRT            PRESSURE/C/A(3      .6/3 .9)/N/SM0530 I /S/FJE/SDR 3.6/3.9)/N/SM0530IlS/FJE/SDR Plant conditions Plant      conditions are  are asas follows:
follows:
      --    The unit The    unit isis in  Cold Shutdown.
in Cold    Shutdown.
      --    The RCS The    RCS isis water water solid solid with with one one train train of  RHR providing of RHR    providing shutdown shutdown cooling.
cooling.
RHR      letdown isis in RHR letdown          in service service with with PCV-145 PCV-145 controlling controlling RCS RCS pressure pressure in in AUTO.
AUTO.
      --  ALL pressurizer ALL    pressurizer PORV  PORV control control switches switches areare in in AUTO.
AUTO.
RCS    temperature is RCS temperature          is 140 140 of.
                                              °F.
      -    PRT level PRT    level isis 78%.
78%.
      -    PRT pressure PRT    pressure is  is 66 psig.
psig.
PRT    temperature is PRT temperature              95 of is 95  °F Assuming no      no operator operator action, action, aa _ _ _ _ _ will result          in aa pressure result in    pressure increase increase in in the PRT PRT and and the crew can    can restore PRT  PRT parameters parameters by  by _ _ _ _ _ __
A. A HIGH  HIGH failure of        PT-444, pressurizer of PT-444,    pressurizer pressure pressure control channel transmitter.
Spraying down the PRT      PRT using reactor reactor makeup water per SOP-1    SOP-i 01, Reactor Reactor Coolant System.
B.
B  ..... Loss of air to HCV-142, LTDN FROM RHR.
Draining the PRT to the Recycle Holdup Tanks per SOP-1            SOP-i 08, Liquid Waste Processing System.
C. A HIGH failure of PT-444, pressurizer pressure control channel transmitter.
C.
Draining the PRT to the Recycle Holdup Tanks per SOP-1            SOP-i 08, Liquid Waste Processing System.
D. Loss of air to HCV-142, LTDN FROM RHR.
D.
Spraying down the PRT using reactor makeup water per SOP-ioi,              SOP-1 01, Reactor Coolant System.
Feedback Feedback DISTRACTORS:
DISTRACTORS:
A  Incorrect failure.
A Incorrect      failure. AA failure failure of  PT-444 of PT          high will
                                            -444 high      will not not cause cause aa pressurizer pressurizer PORV PORV to  to open open because the because      the P-11 P-i 1 signal signal (2/3 (2/3 pressurizer pressurizer protection protection channels channels less less than than 1985 psig) will 1985  psig)  will prevent  automatic    operation    of the  pressurizer prevent automatic operation of the pressurizer PORVs          PORVs inin this    plant Mode.
this plant  Mode.
Plausible because Plausible    because thethe discharge discharge of of aa pressurizer pressurizer PORV PORV will will cause cause an an increase increase in in PRT PRT pressure.
pressure.
Incorrect corrective corrective action.
action. ???At
                                      ???At 180    o 180°F/6+      psig, the Incorrect                                          F/6+ psig,          PRT isis saturated the PRT      saturated (no(no vapor vapor bubble).???
bubble).  ???
Spraying the Spraying    the PRT PRT would would notnot reduce reduce PRT PRT pressure pressure (but(but would would increase increase PRT PRT pressure pressure as  as PRT level PRT    level increased increased from from the the addition addition of of reactor reactor makeup makeup water).
water). Plausible Plausible because because thisthis action would action            reduce PRT would reduce      PRT pressure pressure following following aa relief relief or or safety safety valve valve discharge discharge at at power.
power.
BB Correct Correct failure.
failure. HCV-142 HCV-142 willwill fail fail shut shut onon loss loss of of air.
air. A  failure of A failure    of HCV-142 HCV-142 in in the the closed closed position  isolates the position isolates          RHR system the RHR    system from from thethe letdown letdown system.
system. With With charging    flow in charging flow    in manaul, manaul, RCS pressure RCS    pressure will increase until the RHR    RHR suction relief valve(s) lift, relieving to the PRT.      PRT.
corrective, action.
Correct corrective      action. Draining the PRT will reduce    reduce PRT pressure.
C Incorrect failure. See A. Correct corrective action. See B.
D Correct failure. See B. Incorrect corrective action. See A.


AB-7, RHR system, page 9 AB-2, RCS, page 9 IB-1, SW System, page 17 TS 3.4.1.3, page 237 and 241 KIA CATALOGUE QUESTION DESCRIPTION:  
==REFERENCES:==
-Residual Heat Removal System; Knowledge of system purpose and or function.
Categories Tier: 2 Group: 1 KeyWord: RHR Cog Level: M (2.8/2.9)
Source: N Exam: SM05301 Test: S AuthorlReviewer:
RFAlSDR 
: 79. 007A2.03 0021211IPRT PRESSURE/C/A 3.6/3.9)/N/SM0530IlS/FJE/SDR Plant conditions are as follows: -The unit is in Cold Shutdown.
-The RCS is water solid with one train of RHR providing shutdown cooling. -RHR letdown is in service with PCV-145 controlling RCS pressure in AUTO. -ALL pressurizer PORV control switches are in AUTO. -RCS temperature is 140 of. -PRT level is 78%. -PRT pressure is 6 psig. -PRT temperature is 95 of Assuming no operator action, a _____ will result in a pressure increase in the PRT and the crew can restore PRT parameters by ______ _ A. A HIGH failure of PT-444, pressurizer pressure control channel transmitter.
Spraying down the PRT using reactor makeup water per SOP-1 01, Reactor Coolant System. B ..... Loss of air to HCV-142, LTDN FROM RHR. Draining the PRT to the Recycle Holdup Tanks per SOP-1 08, Liquid Waste Processing System. C. A HIGH failure of PT-444, pressurizer pressure control channel transmitter.
Draining the PRT to the Recycle Holdup Tanks per SOP-1 08, Liquid Waste Processing System. D. Loss of air to HCV-142, LTDN FROM RHR. Spraying down the PRT using reactor makeup water per SOP-1 01, Reactor Coolant System.
Feedback DISTRACTORS:
A Incorrect failure. A failure of PT -444 high will not cause a pressurizer PORV to open because the P-11 signal (2/3 pressurizer protection channels less than 1985 psig) will prevent automatic operation of the pressurizer PORVs in this plant Mode. Plausible because the discharge of a pressurizer PORV will cause an increase in PRT pressure.
Incorrect corrective action. ???At 180 o F/6+ psig, the PRT is saturated (no vapor bubble). ??? Spraying the PRT would not reduce PRT pressure (but would increase PRT pressure as PRT level increased from the addition of reactor makeup water). Plausible because this action would reduce PRT pressure following a relief or safety valve discharge at power. B Correct failure. HCV-142 will fail shut on loss of air. A failure of HCV-142 in the closed position isolates the RHR system from the letdown system. With charging flow in manaul, RCS pressure will increase until the RHR suction relief valve(s) lift, relieving to the PRT. Correct corrective action. Draining the PRT will reduce PRT pressure.
C Incorrect failure. See A. Correct corrective action. See B. D Correct failure. See B. Incorrect corrective action. See A.


==REFERENCES:==
==REFERENCES:==
: 1. Panel XCP-616, Annunciator Point 4-4 2. AB-2, Reactor Coolant System, Pressurizer Relief Tank 3. AB-7, Residual Heat Removal System 4. SOP-1 01, Reactor Coolant System KJA CATALOGUE QUESTION DESCRIPTION:  
: 1. Panel XCP-616, Annunciator Point 4-4
-Ability to (a) predict the impacts of the following malfunctions or operations on the P S (Pressurizer Relief Tank 1 Quench Tank System); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
: 2. AB-2, Reactor Coolant System, Pressurizer Relief Tank
Overpressurization of the PZR (3.6/3.9)
: 3. AB-7, Residual Heat Removal System SOP-i 01, Reactor Coolant System
Categories Tier: 2 Group: 1 KeyWord: PRT PRESSURE Cog Level: C/A(3.6/3.9)
: 4. SOP-1 K/A CATALOGU KJA   CATALOGUE       E QUESTION DESCRIPTION:
Source: N Exam: SM05301 Test: S Author/Reviewer:
DESCRIPTION:
FJE/SDR
- Ability to (a) predict the impacts of the following malfunctions or operations on the P S 5
: 80. 007EA2.01 002/1/1IREACTOR TRIPICIA(4.1/4.3)/M/SM05301lSIMC/SDR At 50% power, the plant experienced a loss of BOTH running Main Feedwater Pumps with a concurrent failure of the Reactor trip breaker A to open. The crew is performing the immediate actions of EOP-1.0, "Reactor Trip/Safety Injection Actuation." Current plant conditions are as follows: -The Integrated Plant Computer System has failed. -SG LO-LO Level annunciators are lit. -Reactor Power is 7% and slowly decreasing.  
(Pressurizer Relief Tank 1       / Quench Tank System); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequence  consequences     s of those malfunctions or operations: Overpressuri        zation of the PZR (3.6/3.9)
-All EFW Pumps failed to start. Which ONE of the following describes the procedure path based on the above information?
Overpressurization Categories Tier:                 22                                        Group:               11 Key  Word:
A. Remain in EOP-1.0, until directed to monitor Critical Safety Functions then transition to EOP-15.0, "Response To Loss of Secondary Heat Sink." B. Directly enter EOP-15.0, "Response To Loss of Secondary Heat Sink." Cy Remain in EOP-1.0, until directed to monitor Critical Safety Functions then transition to EOP-13.0, "Response To Abnormal Nuclear Power Generation." D ..... Transition from EOP-1.0 to EOP-13.0, "Response To Abnormal Nuclear Power Generation." Feedback DISTRACTORS:
KeyWord:             PRT PRESSURE                             Cog Level:           C/A(3.6/3.9)
A INCORRECT Should transition directly to EOP-13.0.
C/A(3.6!3.9)
B INCORRECT Should transition directly to EOP-13.0.
Source:
C INCORRECT Should transition directly to EOP-13.0.
Source:              N                                         Exam:                 5M05301 SM05301 Test:                 SS                                        Author/Revi Author/Reviewer:
D CORRECT Should transition directly to EOP-13.0.
ewer: FJE!SDR FJE/SDR
Since there are no given conditions  
: 80. 007EA2.01
: 80. 007EA2.0 1 002/1/1IREACTOR 002/1/1/REACTORTRIPICIA(4.1/4.3)/M/SM05301lSIMC/SDR TRJP/C/A(4. 1/4.3)/M/SM0530 1/S/MC/SDR At50%
At     50% power, power, the  the plant plant experienced experienced aa loss  loss ofofBOTH BOTH running running Main Main Feedwater Feedwater Pumps Pumpswith with aa concurrent          failure    of the concurrent failure of the Reactor trip  Reactor    trip breaker breakerAA toto open.
open. TheThe crew crew isis performing performing the  the immediate immediate actions of actions        of EOP-1.0, EOP-1 .0, "Reactor ReactorTrip/Safety Trip/Safety Injection Injection Actuation."
Actuation.
Current plant Current         plant conditions conditions are  are asas follows:
follows:
              -- The Integrated The    Integrated Plant Plant Computer Computer SystemSystem has  has failed.
failed.
              -- SG   LO-LO       Level   annunciators SG LO-LO Level annunciators are              are lit.
lit.
              -- Reactor Power Reactor     Power isis 7% 7% and and slowly slowly decreasing.
decreasing.
              -- All EFW All EFW Pumps Pumps failedfailed toto start.
start.
Which ONE Which         ONE of      the following of the   following describes describes the the procedure procedure path path based based onon the the above above information?
information?
A. Remain A.       Remain in       EOP-1 .0, until in EOP-1.0,        until directed directed to    monitor Critical to monitor     Critical Safety Safety Functions Functions then then transition transition toto EOP-1 EOP-15.0,        Response To 5.0, "Response         To Loss Loss ofof Secondary Secondary Heat  Heat Sink."
Sink.
B. Directly B.        Directly enter enter EOP-15.0, EOP-1 5.0, "Response Response To    To Loss Loss ofof Secondary Secondary Heat Heat Sink."
Sink.
C Remain Cy       Remain in  in EOP-1.0, EOP-1 .0, until directed to monitor Critical      Critical Safety Safety Functions Functions then transition transition toto EOP-13.0,      Response To EOP-13.0, "Response               To Abnormal Nuclear  Nuclear Power Power Generation."
Generation.
DDt    Transition from EOP-1.0
        ..... Transition               EOP-1.0 to EOP-13.0, EOP-13.0, "Response Response To Abnormal Nuclear   Nuclear PowerPower Generation.
Generation."
Feedback Feedback D ISTRACTORS:
DISTRACTORS:
A INCORRECT A      INCORRECT                Should transition directly to EOP-13.0. EOP-1 3.0.
B B INCORREC INCORRECT         T      Should transition directly to EOP-13.0.
C C INCORREC INCORRECT         T      Should transition directly to EOP-13.0.
DD CORRECT CORRECT                   Should transition transition directly directly to to EOP-13.0.
EOP-13.0. SinceSince there there areare nono given given conditions conditions that would would    warrant    an SI, an  SI, the CRS shouldshould follow the the Alternative Alternative Action for    for Step Step 55 of of EOP-1.0 EOP-1.0 and  and transition transition to to EOP-1.1.
EOP-1.1. Upon Upon transition transition from from EOP-1 EOP-1.0, .0, the the STA STA begins begins monitoring monitoring of  of CSFs, CSFs, and and should should infrom infrom CRS CRS of  of Red Red path path toto EOP-13.0 EOP-13.0 based  based on  on power power >5%.
                                                                                            >5%.
REFERENC


==REFERENCES:==
==REFERENCES:==
: 1. that would warrant an SI, the CRS should follow the Alternative Action for Step 5 of EOP-1.0 and transition to EOP-1.1. Upon transition from EOP-1.0, the STA begins monitoring of CSFs, and should infrom CRS of Red path to EOP-13.0 based on power >5%. KIA CATALOGUE QUESTION DESCRIPTION:  
ES:
-Reactor Trip; Ability to determine or interpret the following as they apply to a reactor trip: . Decreasing power level, from available indications.
1.
Facility POST EXAM comment resulted in accepting two answers for this question.
1.
With a decreasing power level the applicant may not transition immediately based on the indications present and wait until directed by the status trees.
KIA KIA CATALOGU CATALOGUE         E QUESTION QUESTION DESCRIPTIDESCRIPTION:      ON:
Categories Tier: KeyWord: Source: Test: REACTOR TRIP M S Group: Cog Level: Exam: 1 C/A(4.1I4.3)
      - Reactor Reactor Trip;  Trip; Ability Ability toto determine determine or    or interpret interpret the the following following as as they they apply apply toto aa reactor reactor trip:
SM05301 AuthorlReviewer:
trip:
MC/SDR
  . Decreasing Decreasing power    power level, level, from from available available indications.
: 81. 008A2.04 002/2111CCW/CIA (3.3/3.5)/M/SM0530IlSIRFAlSDR The Unit is operating at 100% power with all systems in normal lineups when the following annunciators actuate: -L TDN/SL WTR HX FLO LO TEMP HI -CC LOOP A RM-L2A HI RAD -CC SRG TK VENT 7096 CLSD HI RAD -CCW SRG TK LVL HI/LO/LO-LO NO other annunciators are lit and all associated automatic functions have occurred.
indications.
Which ONE of the following is the correct cause and action? A. A leak exists in the Letdown HX; verify closure of PVT-8152, LTDN LINE ISOL, per SOP-102, CHEMICAL AND VOLUME CONTROL SYSTEM, and manually shut PW-7096, CC SURGE TK VL V B ..... A leak exists in the Letdown HX; manually close PVT-8152, LTDN LINE ISOL, per SOP-102, CHEMICAL AND VOLUME CONTROL SYSTEM, and verify closure of PW-7096, CC SURGE TK VLV C. RCP "A" thermal barrier has been breached.
Facility Facility POST  POST EXAM EXAM comment comment resulted resulted inin accepting accepting twotwo answers answers for for this this question.
Conduct a normal shutdown per GOP-4B, POWER OPERATION (MODE 1 -DESCENDING), Stop RCP A within 8 hours per SOP-1 01, REACTOR COOLANT SYSTEM. D. A Phase "B" Containment Isolation has actuated due to RM-L2A&B (Component Cooling) alarming.
question. With With aa decreasing decreasing power     power level level the the applicant applicant may may not  not transition transition immediately immediately based based on on the the indications indications present present and    and wait wait until until directed directed by  by the the status status trees.
Immediately trip the reactor and trip ALL RCPs and enter EOP 1.0. Feedback Distractor Analysis:
trees.
 
Categories Categories Tier:
Tier:        I            Group:
Group:           11 Key    Word:
KeyWord:     REACTOR TRIP REACTOR TRIP  Cog Level:
Cog Level:     C/A(4.1I4.3)
C/A(4.1/4.3)
Source:
Source:      MM            Exam:
Exam:            SM05301 SM05301 Test:
Test:        SS            Author/Reviewer:
AuthorlReviewer: MC/SDR MC/SDR
: 81. 008A2.04
: 81. 008A2.04002/2111CCW/CIA 002/2/1/CCW/C/A(3.3/3.5)/M/SM0530IlSIRFAlSDR (3.3/3.5)/M/SM05301/S/RFA/SDR The Unit The         Unit isis operating operating atat 100%
100% power powerwith      all systems with all   systems inin normal normal lineups lineups when when thethe following following annunciators annunciators actuate:    actuate:
              - LLTDN/SL TDN/SL WTR    WTR HX       FLO LO HX FLO        LO TEMP TEMP HI   HI
              --CC     LOOP AA RM-L2A CC LOOP              RM-L2A HI HI RAD  RAD
              - CC
              -      SRG TK CC SRG       TK VENT VENT 70967096 CLSD  CLSD HI HI RAD RAD CCW      SRG    TK  LVL
              - CCW SRG TK LVL HI/LO/LO-LO HI/LO/LO-L          O NO other NO         other annunciators annunciators are   are litlit and and all all associated associated automatic automatic functions functions have have occurred.
occurred.
Which ONE Which         ONE of  of the   following isis the the following          the correct correct cause cause andand action?
action?
A. AA leak A.            leak exists exists inin the the Letdown Letdown HX;    HX; verify verify closure closure ofof PVT-8152, PVT-8152, LTDNLTDN LINE LINE ISOL, ISOL, perper SOP-i      02,  CHEMICAL SOP-102, CHEMICAL AND VOLUME     AND        VOLUME CONTROL CONTROL SYSTEM, SYSTEM, and  and manually manually shut shut PW-7096, PW-7096, CCSURGET CC   SURGE TK       KVLVVL V B B.
        ..... A    leak exists A leak     exists inin the the Letdown Letdown HX;    HX; manually manually close close PVT-8152, PVT-8152, LTDNLTDN LINELINE ISOL, ISOL, perper SOP-i 02, CHEMICAL SOP-102,         CHEMICAL AND    AND VOLUME  VOLUME CONTROL CONTROL SYSTEM, SYSTEM, and and verify closure of verify closure   of PW-7096, CC SURGE TK VLV PW-7096, C. RCP C.        RCP "A" A thermal barrier has been breached. Conduct a normal shutdown per GOP-4B, POWER OPERATION POWER          OPERATION (MODE 11 - DESCENDING),  - DESCENDING), Stop RCP A within 8 hours per SOP-lOl, SOP-1     01, REACTOR COOLANT SYSTEM.
D. A D.       A Phase Phase "B" B Containment Isolation has actuated due to RM-L2A&B (Component Cooling) alarming.
alarming. Immediately trip the reactor and trip ALL RCPs and enter EOP 1.0.
Feedback Feedback Distractor Distractor Analysis:Analysis:
A.
A. Incorrect.
A. Incorrect.
PVT-8152 must be manually shut and PW-7096 should close automatically and be verified closed. B. Correct: C. Incorrect:
Incorrect. PVT-81 PVT-8152   52 must be manually shut and PVV-7096      PW-7096 should close automatically and          and be be verified verified closed.
RCP seals have not failed nor has the thermal barrier been breached.
B.
Therefore, Stopping RCP A within 8 hours per SOP-1 01, REACTOR COOLANT SYSTE, does not apply. D. Incorrect:
B. Correct:
RM-L2A&B 9 will not cause a Phase B Containment Isolation.  
Correct:
C.
C. Incorrect:
Incorrect: RCP  RCP seals seals have have not  not failed failed nor nor has has the the thermal thermal barrier barrier been been breached.
breached. Therefore, Therefore, Stopping Stopping RCP      RCP A  A within within 88 hours hours per    per SOP-i SOP-1 01,01, REACTOR REACTOR COOLANTCOOLANT SYSTE, SYSTE, does does notnot apply.
apply.
D.
D. Incorrect:
Incorrect: RM-L2A&B RM-L2A&B 99 will  will not not cause cause aa Phase Phase BB Containment Containment Isolation.
Isolation.


==References:==
==References:==


AOP 101, Reactor Coolant Pump Seal Failure, page 8 SOP 102.2, CHEMICAL AND VOLUME CONTROL SYSTEM, page 70, ARP-001-XCP-601, page 16 KIA CATALOGUE QUESTION DESCRIPTION:  
==References:==
-Component Cooling Water System (CCWS); Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malufunctions or operations:
 
PRMS alarm.
AOP AOP 101,     101, Reactor Reactor Coolant Coolant Pump Pump Seal  Seal Failure, Failure, page page 88 SOP SOP 102.2,  102.2, CHEMICAL CHEMICAL AND    AND VOLUME VOLUME CONTROLCONTROL SYSTEM,SYSTEM, page page 70,70, ARP-001-XC ARP-001-XCP-601, page 16  P-601,    page    16 KIA CATALOGU K/A        CATALOGUE           E QUESTION QUESTION DESCRIPTI  DESCRIPTION:    ON:
Categories Tier: 2 Group: 1 KeyWord: CCW Cog Level: CIA (3.3/3.5)
    -  Component
Source: M Exam: SM05301 Test: S Author/Reviewer:
    - Component Cooling WaterCooling    Water SystemSystem (CCWS);
RFAlSDR
(CCWS); Ability Ability to   (a) predict to (a)  predict the the impacts impacts ofofthe the following following malfunctions malfunctions or         or operations operations onon the  the CCWS, CCWS, and  and (b)
: 82. 009EG2.4.30 002/1/I1REPORTABILITYIM(2.2/3.6)/N/SM0530IlSIRFAlSDR Which ONE of the following identifies an event that is required to be reported to the NRC within 1 hour per EPP-002, COMMUNICATION AND NOTIFICATION.
(b) based based on  on those those predictions, predictions, use use procedures procedures toto correct, correct, control, control, or or mitigate mitigate the the consequence consequences     s of ofthose those malufunction malufunctions     or operations:
A. An unplanned ECCS initiation that does not discharge to the RCS during an SI surveillance test. B ..... An ECCS discharge to the RCS in response to a small break LOCA. C. An airborne release of > 2X Appendix B limits. D. A liquid release of> 2X Appendix B limits. Feedback Distractor Analysis:
s or  operations: PRMS PRMS alarm.
alarm.
 
Categories Categories Tier:
Tier:      22  Group:
Group:           11 Key  Word:
KeyWord:     CCW CCW Cog Level:
Cog Level:      CIA C/A (3.3/3.5)
(3.3/3.5)
Source:
Source:    MM  Exam:
Exam:           SM05301 SM05301 Test:
Test:      SS  Author/Reviewer:
Author/Reviewer:  RFAJSDR RFAlSDR
: 82. 009EG2.4.30
: 82. 009EG2.4.30 002/1/I1REPORTABILITYIM(2.2/3.6)/N/SM0530IlSIRFAlSDR 002/1/1/REPORTABILITY/M(2.2/3 .6)/N/SM0530 1/SIRFAJSDR Which ONE Which        ONE of of the the following following identifies identifies an an event event that that isis required required to to be be reported reported to to the the NRC NRC withinwithin hour per 11 hour     per EPP-002, EPP-002, COMMUNICATION COMMUNICATION AND       AND NOTIFICATION.
NOTIFICATION.
A. An A.            unplanned ECCS An unplanned        ECCS initiation initiation that that does does not not discharge discharge to to the the RCS RCS during during an an SISI surveillance surveillance test.
test.
BB.v    An ECCS
        ..... An   ECCS discharge discharge to  to the the RCS RCS inin response response to to aa small small break break LOCA.
LOCA.
C. An C.        An airborne airborne release release ofof>
                                            > 2X2X Appendix Appendix BB limits.
limits.
D.          liquid release D. AA liquid       release of> of> 2X 2X Appendix Appendix BB limits.
limits.
Feedback Feedback Distractor Analysis:
Distractor        Analysis:
A. Incorrect:
A. Incorrect:
This is a non-emergency event that does not discharge to the RCS this is a 4 hour notification requirement.
A.      Incorrect: This This is is aa non-emergency non-emergency event  event that that does does notnot discharge discharge to  to the the RCS RCS this this is is aa 44 hour notification hour       notification requirement.
B. Correct: A LOCA is an emergency event which requires notification.
requirement.
C. Incorrect:
B.       Correct: A LOCA is an emergency event B. Correct:                                          event which requires notification.
This is a 4 hour notification requirement D. Incorrect:
C. Incorrect: This is a 4 hour notification requirement D. Incorrect: This is a 4 hour notification requirement D.
This is a 4 hour notification requirement  
 
==Reference:==
EPP-002,


==Reference:==
==Reference:==
EPP-002, page 27 K/A CATALOGUE KIA      CATALOGUE QUESTION DESCRIPTION:    DESCRIPTION:
Small
    - Small
    -            Break  LOCA;      Knowledge    of which events related to system operations/status operations/status should be      be reported reported        to outside    agencies.
Categories Categories Tier:
Tier:                      I                                      Group:                1 Key KeyWord: Word:            REPORTAB REPORTABILITYILITY                      Cog Level:            M(2.2/3.6)
Source:
Source:                  N                                        Exam:                  SM05301 Test:
Test:                    SS                                      Author/Revi Author/Reviewer:
ewer: RFAJSDR RFAlSDR
: 83. 022AG2.4.49 OOl/1/l1RCS
: 83. 022AG2.4.49      00 1/1/1/RCS MAKEUP/CIA MAKEUP/C/A(4.0/4.0)/N/SM05301lSIRFAlSDR (4.0/4.O)/N/SM05301/S/RFAJSDR The plant The    plant was was operating operating at  at 80%
80% power power when when the      following annunciators the following      annunciators (not (not all all inclusive) inclusive) came came in:
in:
            -      REGEN HX REGEN          HX LLTDN TDN OUTOUT TEMPTEMP HI  HI
            -      VCT LVL VCT    LVL HIILO HI/LO
            -      CHG LINE CHG      LINE FLO  FLO HIILO HI/LO
            -      PZR  LCS PZR LCS DEV HIILO DEV    HI/LO Charging pump Charging      pump amps  amps are are fluctuating fluctuating between between 25  25 andand 3030 amps amps Charging flow Charging      flow isis fluctuating fluctuating between between 25  25 and and 30    gpm 30 gpm Charging pressure Charging      pressure isis oscillating oscillating between between 25002500 andand 2600 2600 psig psig Which ONE Which    ONE of of the the following following set    of actions set of  actions should should thethe supervisor supervisor direct direct his his board board operators operators toto perform    (These      actions perform (These actions are not      are      all inclusive)?
not all inclusive)?
A.% Secure A.II  Secure the the operating operating charging charging pump, pump, close close allall letdown letdown isolation isolation valves, valves, andand close close FCV-122, charging FCV-122,      charging flow  flow control control valve.
valve.
B. Verify at least one      one charging charging pump pump is operating, verify FCV-122 is open, and verify CCW                COW flow to the RCP Thermal Barriers is GREATER THAN 90 gpm on FI-7273A(B),                      FI-7273A(B), THERM BARR FLOW GPM.
C. Secure the operating charging pump, realign charging pump suction, and close both LCV-1 15B(D), RWST TO CHG PP SUCT.
LCV-115B(D),
D. Verify at least one charging pump is operating, verify FCV-122 is open, and open both D.
LCV-115C(E), VCT OUTLET ISOL.
LCV-115C(E),
Feedback Feedback Distractor Analysis:
A.
A. Correct answer per AOP-1                02.2, page 4-6 AOP-102.2, B,C, and D. Charging flow is abnormal - must go to the RNO column. Closing
                                                              -                                          ClOSing both LCV-1    1 5B(D), RWST TO CHG PP SUCT, LCV-115B(D),                                      SUCT, is  is an an action action ifif charging charging was initially initially aligned aligned toto the the RWST.


EPP-002, page 27 KIA CATALOGUE QUESTION DESCRIPTION:  
==Reference:==
-Small Break LOCA; Knowledge of which events related to system operations/status should be reported to outside agencies.
Categories Tier: Group: 1 KeyWord: REPORT ABILITY Cog Level: M(2.2/3.6)
Source: N Exam: SM05301 Test: S Author/Reviewer:
RFAlSDR 
: 83. 022AG2.4.49 OOl/1/l1RCS MAKEUP/CIA (4.0/4.0)/N/SM05301lSIRFAlSDR The plant was operating at 80% power when the following annunciators (not all inclusive) came in: REGEN HX L TDN OUT TEMP HI VCT LVL HIILO CHG LINE FLO HIILO PZR LCS DEV HIILO Charging pump amps are fluctuating between 25 and 30 amps Charging flow is fluctuating between 25 and 30 gpm Charging pressure is oscillating between 2500 and 2600 psig Which ONE of the following set of actions should the supervisor direct his board operators to perform (These actions are not all inclusive)?
A.II Secure the operating charging pump, close all letdown isolation valves, and close FCV-122, charging flow control valve. B. Verify at least one charging pump is operating, verify FCV-122 is open, and verify CCW flow to the RCP Thermal Barriers is GREATER THAN 90 gpm on FI-7273A(B), THERM BARR FLOW GPM. C. Secure the operating charging pump, realign charging pump suction, and close both LCV-115B(D), RWST TO CHG PP SUCT. D. Verify at least one charging pump is operating, verify FCV-122 is open, and open both LCV-115C(E), VCT OUTLET ISOL. Feedback Distractor Analysis:
A. Correct answer per AOP-102.2, page 4-6 B,C, and D. Charging flow is abnormal -must go to the RNO column. ClOSing both LCV-115B(D), RWST TO CHG PP SUCT, is an action if charging was initially aligned to the RWST.


==Reference:==
==Reference:==


AOP-102.2, page 4-6 KIA CATALOGUE QUESTION DESCRIPTION:  
AOP-1    02.2, page AOP-102.2,       page 4-6 4-6 K/A KIA CATALOGU CATALOGUE         E QUESTION QUESTION DESCRIP11 DESCRIPTION:    ON:
-Loss of Reactor Coolant Makeup; Ability to perform without reference to procedures those actons that require immediate operation of system components and controls.
    -  Loss  of
Categories Tier: Group: 1 KeyWord: RCSMAKEUP Cog Level: CIA (4.0/4.0)
    - Loss of Reactor Reactor Coolant Coolant Makeup; Makeup; Ability     to perform Ability to  perform without without reference reference to  to procedures procedures those those actons actons thatthat require require immediate immediate operation operation of  of system system components components and  and controls.
Source: N Exam: SM05301 Test: S AuthorlReviewer:
controls.
RFAlSDR 
Categories Categories Tier:
: 84. 032AA2.08 003/l/2/SRNIIM(2.2/3.1  
Tier:                    1                                          Group:
)/N/SM0530 l/SIMCIRF AlSDR Refueling operations are in progress, with SR monitor N33 out of service, when power is suddenly lost to source range neutron flux monitor N31 and subsequently regained 30 minutes later. Which ONE of the following describes the action to be taken for this situation when power is lost? A." Suspend all core alterations and perform an analog channel operational test of source range neutron flux monitor N31 within 8 hours prior to the initial start.of core alterations.
Group:                1 Key  Word:
B. Suspend all core alterations and perform a neutron flux response time test AND operational test of source range neutron flux detector N31 within 8 hours prior to the initial start of core alterations.
KeyWord:               RCS    MAKEUP RCSMAKEUP                                 Cog Cog Level:
C. Determine boron concentration and perform a channel check of source range neutron flux monitor N31 within 12 hours. D. Determine boron concentration and perform a neutron flux response time test of source range neutron flux detector N31 within 12 hours. Feedback DISTRACTORS:
Level:          CIA (4.0/4.0)
A CORRECT T.S. 3.9.2 requires immediate suspension of CORE ALTERATIONS when one of the two SR monitors are lost B INCORRECT Per T.S. Table 3.3-2 (* and Note 1), neutron detectors (not the channel) are exempt from response time testing. C INCORRECT Boron concentration measurements are only required when both monitors are down. D INCORRECT Boron concentration measuriments are only required when both monitors are down. Neutron detectors are exempt from response time testing.  
C/A  (4.0/4.0)
Source:
Source:                NN                                          Exam:
Exam:                 SM05301 SM05301 Test:
Test:                  SS                                          Author/Revie AuthorlReviewer:       RFAlSDR wer: RFAJSDR
: 84. 032AA2.08
: 84. 032AA2.08 003/l/2/SRNIIM(2.2/3.1 003/112/SRNI/M(2.2/3. 1)IN/SM053
                                                    )/N/SM053001/S/MCIRF      AISDR l/SIMCIRF AlSDR Refueling operations Refueling      operations are     are inin progress, progress, with with SR     monitor N33 SR monitor    N33 out     of service, out of  service, when when power power isis suddenly     lost   to   source   range   neutron suddenly lost to source range neutron flux monitor N31    flux monitor   N31 andand subsequently subsequently regained regained 30  30 minutes minutes later.
later.
Which ONE Which      ONE of  of the the following following describes describes the the action action to   be taken to be  taken forfor this this situation situation when when powerpower isis lost?
lost?
A."A. Suspend Suspend all  all core core alterations alterations andand perform perform an an analog analog channel channel operational operational testtest ofof source source range    neutron      flux range neutron flux monitor N31monitor          within 88 hours N31 within     hours prior prior toto the the initial initial start.of startof core core alterations.
alterations.
B.B. Suspend Suspend all  all core core alterations alterations andand perform perform aa neutron neutron fluxflux response response time time test test AND AND operational operational test of test      source range of source      range neutron neutron flux flux detector detector N31N31 within within 88 hours hours prior prior to to the the initial initial start start of of core core alterations.
alterations.
C.      Determine boron C. Determine         boron concentration concentration and       perform aa channel and perform        channel checkcheck of  of source source range range neutron neutron flux flux monitor monitor N31 N31 withinwithin 1212 hours.
hours.
D.D. Determine Determine boron concentration and perform a neutron              neutron flux response response time test of source   source range neutron range     neutron flux detector detector N31N31 within 12  12 hours.
hours.
Feedback Feedback DISTRACTORS:
DISTRACTORS:
A CORRECT                       T.S. 3.9.2 requires immediate suspension of CORE ALTERATIONS          ALTERATIONS when one of the two SR monitors are lost INCORRECT B INCORRECT                                                 (*
B                                Per T.S. Table 3.3-2 (* and Note 1), neutron detectors (not the channel) are exempt from response time testing.
C INCORREC INCORRECT       T        Boron concentration measuremen measurements     ts are only required when both monitors are down.
D INCORREC D      INCORRECT       T        Boron concentration measuriment measuriments     s are only required when both monitors are down. Neutron Neutron detectors are exempt from response time              time testing.
REFERENC


==REFERENCES:==
==REFERENCES:==
: 1. TS 3.9.2, "Instrumentation." 2. TS 3.9.1, "Boron Concentration." 3. TS Table 3.3-2, "Reactor Trip System Instrumentation Response Times." 4. IC-8, "Nuclear Instrumentation," pages 24,48, & 50. KIA CATALOGUE QUESTION DESCRIPTION:  
ES:
-Loss of Source Range Nuclear Instrumentation; Ability to determine and interpret the following as they apply to the Loss of Source Range Nuclear Instrumentation:
: 1.     TS 3.9.2,
Testing required if power is lost, then restored.
: 1. TS 3.9.2, Instrumenta "Instrumentation." tion.
Categories Tier: KeyWord: Source: Test: SRNI N S Group: Cog Level: 2 M(2.2/3.1)
: 2. TS
Exam: SM0530 1 AuthorlReviewer:
: 2.     TS 3.9.1, 3.9.1, Boron "Boron Concentratio Concentration." n.
MC/RF AlSDR 
: 3. TS
: 85. 035G2.4.20 002/2/2/SGIC/A (3.3/3.4)/N/SM05301lSIRFAlSDR The crew has just entered EOP-15.0, "Response to Loss of Secondary Heat Sink" from EOP-12.0, Monitoring of Critical Safety Functions.
: 3.     TS Table Table 3.3-2, 3.3-2, Reactor "Reactor TripTrip System System Instrumentat Instrumentationion Response Response Times.
The following conditions exist: -WR SG "A" level is 25% -WR SG "B" level is 12% -WR SG "c" level is 11% -Total Feed Flow is 290 gpm Which ONE of the following sets of actions (not all inclusive) should be taken as directed by EOP-15.0, "Response to Loss of Secondary Heat Sink"? A. Ensure all EFW valves are open and establish EFW flow to at least one SG. B. Reset SI and establish MFW flow to either the "B" or "c" Steam Generators.
Times."
C. Reset SI, dump steam to the condenser and feed using a condensate pump. Trip ALL RCPs, actuate SI, establish an RCS bleed path: Feedback NOTE: No other initial conditions are needed. The caution prior to step 4 of EOP-15 is a stand alone statement.
4.
If the SRO has entered this procedure and these conditions exist, there is no other option. Distractor Analysis:
: 4. IC-8, IC-8, Nuclear "Nuclear Instrumentat Instrumentation,"ion, pages pages 24,   48, && 50.
A, B, C. Incorrect:
24,48,      50.
Not allowed due to caution prior to step 4. These steps are bypassed when the CAUTION prior to Step 4 is implemented.
K/A KIA CATALOGU CATALOGUE         E QUESTION QUESTION DESCRIPTIDESCRIPTION:  ON:
D Correct:  
    -  Loss    of  Source
    - Loss of Source Range       Range Nuclear Nuclear Instrumentat Instrumentation;ion; Ability Ability toto determine determine and and interpret interpret thethe following following as as they they apply apply to      the Loss to the     Loss ofof Source Source Range Range Nuclear Nuclear Instrumentat Instrumentation:         Testing required ion: Testing       required ifif power power isis lost, lost, then then restored.
restored.
Categories Categories Tier:
Tier:                       1                                          Group:
Group:                22 Key KeyWord:Word:             SRNI SRNI                                       Cog Level:
Cog   Level:           M(2.2/3.1)
M(2.2/3.1)
Source:
Source:                  N N                                        Exam:
Exam:                  SM05301 SM0530 1 Test:
Test:                      SS                                        Author/Revie    wer:
AuthorlReviewer:       MC/RFAlSDR MC/RFAJSD      R
: 85. 035G2.4.20
: 85. 035G2.4.20 002/2/2/SGIC/A 002/2/2/SG/C/A (3.3/3.4)/N/SM05301lSIRFAlSDR (3.3/3.4)/N/SM0530 1/SIRFAJSDR The crew The  crew hashas just just entered entered EOP-15.0, EOP-15.O, "Response Response to  to Loss Loss ofof Secondary Secondary Heat Heat Sink" Sink from from EOP-12.O,    Monitoring        of Critical EOP-12.0, Monitoring of Critical Safety         Safety Functions.
Functions.
The following The  following conditions conditions exist:exist:
              -- WR SG WR   SG "A"A level level isis 25%
25%
              -- WR SG WR  SG "B" B level level isis 12%
12%
              - WR SG "c" level is 11%
WR  SG    C    level  is  11%
              -- Total  Feed Total Feed Flow isFlow  is 290 290 gpm gpm Which ONE Which    ONE of    the following of the     following sets sets of  actions (not of actions (not all all inclusive) inclusiye) should should be be taken taken as as directed directed byby EOP-1 5.0, "Response EOP-15.0,     Response to      to Loss Loss of of Secondary Secondary Heat Heat Sink"?
Sink?
A. Ensure A. Ensure allall EFW EFW valves valves are are open open and and establish establish EFWEFW flow flow to  at least to at least one one SG.
SG.
B. Reset B. Reset SI    and establish SI and   establish MFW  MFW flow to either either the "B"   or "c" B or  C Steam Steam Generators.
Generators.
Reset SI, dump steam to the condenser and feed using a condensate pump.
C. Reset C.
D D~  Trip ALL RCPs, actuate SI, establish an RCS bleed path:
Feedback Feedback NOTE: No NOTE:      No other initial conditions are needed. The caution prior to step 4 of EOP-15               EOP-1 5 isis a stand stand alone alone   statement.       If the SRO     has   entered this procedure and these conditions exist, there is           is no no other option.
other Distractor Analysis:
Distractor A, B, C. Incorrect:
Incorrect: Not allowed due to caution prior to step 4. These steps are bypassed when                       when the  CAUTION the CAUTION         prior   to Step   4 is implemented implemented..
D D Correct:
Correct:


==Reference:==
==Reference:==


EOP-12, page 9 EOP-15, page 3 caution prior to step 4 KIA CATALOGUE QUESTION DESCRIPTION:  
==Reference:==
-Steam Generator; Knowledge of operational implications of EOP warnings, cautions, and notes. Categories Tier: 2 Group: 2 KeyWord: SG Cog Level: CIA (3.3/3.4)
 
Source: N Exam: SM05301 Test: S Author/Reviewer:
EOP-12, EOP-12,     page page 99 EOP-15, EOP-15,      page page 33 caution prior to step     step 44 K/A KIA CATALOGU CATALOGUE       E QUESTION QUESTION DESCRIPTI  DESCRIPTION:  ON:
RFAlSDR
    - Steam Steam Generator; Generator; Knowledge Knowledge of      of operational operational implications implications of  of EOP EOP warnings, warnings, cautions, cautions, and and notes.
: 86. 054AA2.03 0021111/MFW/C/A (4.1I4.2)/N/SM05301lSIRFAlSDR The following conditions exist: -A plant startup was in progress.  
notes.
-Power level was at 38% -The reactor tripped -SG blowdown isolation valves (PVG-503A(B)(C), A(B)(C) ISOL) closed -Current SG narrow range levels in "A", "B", and "c" SGs are 8%,10%, and 10%, respectively, and decreasing Which ONE of the following correctly states the initiating event that caused the trip and the expected automatic actions based on these conditions?
Categories Categories Tier:
A. The operating MFP tripped and ONLY the motor driven EFW pumps have a current start signal. B ..... The operating MFP tripped and BOTH the turbine driven AND motor driven EFW pumps have a current start signal. C. All SG flow control valves drifted closed and AMSAC should have actuated.
Tier:                 22                                          Group:
D. All SG flow control valves drifted closed and ONLY the turbine driven EFW pump has a current start signal. Feedback Unless the applicant keys on the fact that SG blowdown isolation valves (PVG-503A(B)(C), A(B)(C) ISOL) closed, he may consider C or D. Distractor Analysis:
Group:               22 Key  Word:
KeyWord:             SG SG                                        Cog Cog Level:
Level:          CIA (3.3/3.4)
C/A  (3.3/3.4)
Source:
Source:              NN                                          Exam:
Exam:                 SM05301 SM05301 Test:
Test:                 SS                                          Author/Revi Author/Reviewer:
ewer:    RFAlSDR RFAJSDR
: 86. 054AA2.03
: 86. 054AA2.03 0021111/MFW/C/A 002/1/1/MFW/C/A (4.1I4.2)/N/SM05301lSIRFAlSDR (4. 1/4.2)/N/SM0530 1!SIRFA!SDR The following The       following conditions conditions exist:
exist:
                  - AA plant
                  -    plant startup startup was was inin progress.
progress.
Power level
                  - Power
                  -          level was was at   38%
at 38%
The reactor
                  - The
                  -      reactor tripped tripped SG  blowdown      isolation valves
                  - SG blowdown isolation
                  -                                valves (PVG-503A(B)(C),
(PVG-503A(B)(C), A(B)(C) A(B)(C) ISOL)
ISOL) closed closed Current    SG  narrow    range
                  - Current SG narrow range levels
                  -                                    levels inin "A",
A, "B",   and "c" B, and  C SGs SGs are are 8%,10%,
8%, 10%, and and 10%, respectively, 10%,  respectively, and and decreasing decreasing Which ONE Which        ONE of of the the following following correctly correctly states states the    initiating event the initiating event that that caused caused thethe trip trip and and the the expected automatic expected          automatic actions actions based based on on these these conditions?
conditions?
A. The A.      The operating operating MFPMFP tripped tripped and     ONLY the and ONLY      the motor motor driven driven EFW EFW pumps pumps havehave aa current current start start signal.
signal.
BB.v    The operating
      ..... The     operating MFPMFP tripped and         BOTH the turbine driven and BOTH                      driven AND AND motor motor driven driven EFW EFW pumps pumps have aa current have      current start start signal.
signal.
C. All SG flow control valves drifted closed and AMSAC should                    should have actuated.
D. All D.      All SG flow control valves drifted closed and ONLY the turbine driven EFW pump has aa current start signal.
current Feedback Unless the applicant keys on the fact that SG blowdown isolation valves (PVG-503A(B)(C),
Unless                                                                                              (PVG-503A(B)(C),
A(B)(C)
A(B)(C) ISOL) closed, he may consider C or D.
Distractor Analysis:
A. Incorrect:
A. Incorrect:
LO LO level both MDEFP AND TDEFP will start B. Correct: C. Incorrect:
A.      Incorrect: LO LO level both MDEFP AND TDEFP will start B. Correct:
All SG flow control valves drifting closed could cause this. ????However, SG blowdown isolation valves (PVG-503A(B)(C), A(B)(C) ISOL) closed which don't according to ARP XCP-624. ???? Additionally, AMSAC will not actuate since initial power was < 40% D. Incorrect:
C.
All SG flow control valves drifting closed could cause this. ????However, SG blowdown isolation valves (PVG-503A(B)(C), A(B)(C) ISOL) closed which don't according to ARP XCP-624. ???? Additionally, both MDEFP AND TDEFP will start.  
C. Incorrect:
Incorrect: All SG  SG flow control control valves drifting drifting closed couldcould cause cause this.
this. ????Howeve
                                                                                                          ????However,        SG r, SG blowdown blowdown isolationisolation valves valves (PVG-503A(
(PVG-503A(B)(C),B)(C), A(B)(C) ISOL)  ISOL) closed which dont  don't according according to ARP XCP-624.???
XCP-624. ????      ? Additionally Additionally,, AMSAC AMSAC will not  not actuate since initial initial power power was <40%< 40%
D. Incorrect:
D.        Incorrect: All     SG flow control All SG          control valves valves drifting drifting closed closed could could cause cause this.
this. ????Howeve
                                                                                                          ????However,        SG r, SG blowdown          isolation blowdown isolation valves    valves (PVG-503A(
(PVG-503A(B)(C),B)(C), A(B)(C)
A(B)(C) ISOL)
ISOL) closed closed which which dont don't according according to  to ARP ARP XCP-624.
XCP-624. ???? ???? Additionally Additionally,, both both MDEFP MDEFP AND   AND TDEFP TDEFP will will start.
start.


==Reference:==
==Reference:==


ARP-001-XCP-624, page 22 and 26 KIA CATALOGUE QUESTION DESCRIPTION:  
==Reference:==
-Loss of Main Feedwater (MFW); Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW): Conditions and reasons for AFW pump startup.
 
Categories Tier: Group: 1 KeyWord: MFW Cog Level: CIA (4.114.2)
ARP-001-XC ARP-001-XCP-624,    P-624, page page 22 22 and and 26 26 KIA CATALOGU K/A      CATALOGUE       E QUESTION QUESTION DESCRIPTIDESCRIPTION:  ON:
Source: N Exam: SM05301 Test: S AuthorlReviewer:
    -  Loss      of  Main  Feedwater      (MEW);
RFA/SDR B7. 068G2.1.20 002/2/2/U DID RADWASTE/C/A(4.3/4.2  
    - Loss of Main Feedwater (MFW); Ability to       Ability  to determine determine and  and interpret interpret the the following following asas they they apply apply to  the    Loss  of Main    Feedwater to the Loss of Main Feedwater (MFW):          (MFW): Conditions Conditions and  and reasons reasons for for AFW AFW pump pump startup.
/N/SM05301/SIRFAlSDR A Liquid Radwaste Release is been in progress:  
startup.
-XCP-646 2-5, MON TK DISCH RM-L5 HI RAD, has just actuated for the second time. -RCV0001B-WL, Liquid Radioactive Waste Control Valve, indicates shut. -Within 30 seconds of the alarm, RM-L5's reading returns to below the setpoint.
 
Which ONE of the following correctly states the next procedure steps to be taken. A." The tank must be sampled and activity levels verified, then open RCV0001B-WL and resume the release per SOP-10B. B. Verify that the RM-L5's reading is below the setpoint, then open RCV0001B-WL and resume the release per SOP-1 OB. C. Verify that the RM-L5's reading is below the setpoint, then open RCV0001B-WL and resume the release per SOP-1 OB. Direct Heath Physics to continue to monitor the release and reduce the release rate. Dy Notify Health Physics and request a radiological survey. The release can not be reinitiated under the current release permit. Feedback DISTRACTORS:
Categories Categories Tier:
A CORRECT As per XCP-646-2-5, this is the first step of the supplemental actions. B INCORRECT This is the action if this is the first time the release has been automatically terminated.
Tier:        1  Group:
C INCORRECT This is the action if this is the first time the release has been automatically terminated, ????coupled with the actions for a malfunctioning RM-L5. ???? D INCORRECT This would be plausible if it is believed that the release can not be continued.  
Group:           11 Key  Word:
KeyWord:     MFW MFW  Cog Level:
Cog Level:       CIA C/A (4.114.2)
(4.1/4.2)
Source:
Source:    NN  Exam:
Exam:           SM05301 SM05301 Test:
Test:      SS  Author/Reviewer:
AuthorlReviewer: RFA/SDR RFAISDR
: 87. 068G2.1.20 B7. 068G2. 1.20002/2/2/U 002/2/2/LIQU DIDiDRADWASTE/C/A(4.3/4.2 RADWASTE/C/A(4.3/4.2/N/SM05301/SIRFAlSDR
                                                                        )/N/SM05301/S/RFA/SDR Liquid Radwaste AA Liquid     Radwaste Release Release isis been been inin progress:
progress:
          -- XCP-646 2-5, XCP-646      2-5, MON MON TK TK DISCH DISCH RM-L5RM-L5 HI HI RAD, RAD, hashasjust just actuated actuated for forthe the second second time.
time.
          --  RCV0001 8-WL, Liquid RCV0001B-WL,           Liquid Radioactive Radioactive Waste Waste Control Control Valve, Valve, indicates indicates shut.
shut.
          -- Within 30 Within  30 seconds seconds of ofthe the alarm, alarm RM-L5's
                                                        ,  RM-L5s reading reading returns returns toto below below thethe setpoint.
setpoint.
Which ONE Which      ONE of of the the following following correctly correctly states states the the next next procedure procedure steps steps toto be be taken.
taken.
A. The A."     The tank tank must must be be sampled sampled and and activity activity levels levels verified, verified, then then open open RCV0001B-WL RCV00018-WL and      and resume the resume          release per the release     per SOP-10B.
SOP-108.
B.     Verify that B. Verify      that the the RM-L5's RM-L5s reading reading isis below below thethe setpoint, setpoint, then then open open RCV0001B-WL RCV00018-WL and      and resume    the  release  per resume the release per SOP-1 OB.SOP-i    08.
C.     Verify that C. Verify      that the the RM-L5's RM-L5s reading reading is is below below thethe setpoint, setpoint, then then open open RCV0001B-WL RCV00018-WL and       and resume the resume           release per the release     per SOP-1 SOP-108.        Direct Heath OB. Direct       Heath Physics Physics to to continue continue to to monitor monitor thethe release release and reduce and    reduce the     release rate.
the release    rate.
Dv Notify Dy     Notify Health Health Physics Physics andand request request aa radiological radiological survey.
survey. TheThe release release cancan not not be be reinitiated reinitiated under the current release under                  release permit.
permit.
Feedback Feedback DISTRACTORS:
DISTRACTORS:
A CORRECT                   As per XCP-646-2-5, XCP-646-2-5, this is the first step of the supplemental supplemental actions.
B  INCORRECT B INCORRECT                 This is the action if this is the first time the release has been automatically terminated.
INCORRECT C INCORRECT                 This is the action if this is the first time the release has been automatically terminated, ????coupled with the actions for a malfunctioni      malfunctioning       RM-L5. ????
ng RM-L5.????
D INCORREC D    INCORRECT       T      This would be plausible if itit is believed that the release can not be continued.
continued.
REFERENC


==REFERENCES:==
==REFERENCES:==
: 1. XCP-646 2-5 & 2-6, pages 12 & 13. 2. XCP-644 2-5, page 15. 3. XCP-643 4-1, page 22. KIA CATALOGUE QUESTION DESCRIPTION:  
ES:
-Liquid Radwaste System; Ability to execute procedure steps. Facility POST EXAM comment resulted in accepting two answers for this question.
1.
The additional information provided by the facility in HPP-710 supports distractor D as an additional correct answer. Additionally, this additional answer was not identified by the facility during the examination review and validation activities.
: 1. XCP-646 XCP-646 2-5  2-5 && 2-6, 2-6, pages pages 12 12 && 13.
HPP-710 indicates that the current release permit must be closed.
13.
Categories Tier: KeyWord: Source: Test: 2 LIQUID RADW ASTE N S Group: Cog Level: Exam: 2 C/A(4.3/4.2)
: 2. XCP-644      2-5,
SM05301 AuthorlReviewer:
: 2. XCP-644 2-5, page 15. page  15.
RF AlSDR
: 3. XCP-643
: 88. I03G2.1.30 002/2/I/CONTAINMENT AlRLOCKIM (3.9/3.4)/N/SM05301/SIFJEIRFNSDR Plant conditions are as follows: -The unit is currently in MODE 4, with temperature and pressure increasing.  
: 3. XCP-643 4-i,  4-1, page page 22.
-All major work inside containment was completed two hours ago and there are NO personnel inside the Reactor Building.  
22.
-An auxiliary operator has just called to report that the red indicating light above the Personnel Escape Airlock is LIT and that he was unable to operate the Fuel Handling Building door using the handwheel.
K/A KIA CATALOGU CATALOGUE       E QUESTION QUESTION DESCRIPTI DESCRIPTION:    ON:
Which ONE of the following is correct regarding the status of the Personnel Escape Airlock AND Containment Integrity?
    - Liquid Liquid Radwaste Radwaste System; System; Ability    to execute Ability to   execute procedure procedure steps.
A.v The Reactor Building door is OPEN. The Personnel Escape Airlock is INOPERABLE.
steps.
B. The Reactor Building door is CLOSED. The Personnel Escape Airlock is INOPERABLE.
Facility Facility POST POST EXAMEXAM comment comment resulted             accepting two resulted inin accepting       two answers answers for for this this question.
C. Only the Reactor Building door position indicator has malfunctioned.
question. The The additional     information     provided additional information provided by        by the the facility facility inin HPP-710 HPP-710 supports supports distractor distractor DD as as an an additional additional correct correct answer.
The Personnel Escape Airlock is OPERABLE.
answer. Additionally Additionally,, this this additional additional answer answer was was not not identified identified by by the the facility facility during during the the examination examination review review andand validation validation activities.
activities. HPP-710 HPP-710 indicates indicates that that the the current current release release permit permit must must be   be closed.
closed.
 
Categories Categories Tier:
Tier:      22                Group:
Group:           22 Key  Word:
KeyWord:     LIQUID RADW LIQUID  RADWASTE ASTE Cog Level:
Cog Level:       C/A(4.3/4.2)
C/A(4.3/4.2)
Source:
Source:    NN                Exam:
Exam:            SM05301 SM05301 Test:
Test:      SS                Author/Reviewer:
AuthorlReviewer: RFA/SDR RF AlSDR
: 88. I03G2.1.30
: 88. 1 03G2. 1.30 002/2/I/CONTAINMENT 002/211 /CONTAfNMENT AlRLOCKIM     AIRLOCKJM (3.9/3.4)/N/SM05301/SIFJEIRFNSDR (3.9/3 .4)/N1SM0530 1 /SIFJE/RFAISDR Plant conditions Plant     conditions are are asas follows:
follows:
The unit
            - The
            -      unit isis currently currently inin MODE MODE 4,4, with with temperature temperature and  and pressure pressure increasing.
increasing.
            - All major work
            - All major     work inside inside containment containment was  was completed completed two  two hours hours agoago and and there there are are NO NO personnel inside personnel      inside thethe Reactor Reactor Building.
Building.
            - An
            -      auxiliary operator An auxiliary      operator has has just just called called toto report report that that the the red red indicating indicating light light above above the the Personnel      Escape      Airlock    is LIT  and Personnel Escape Airlock is LIT and that he was unablethat  he  was    unable to to operate operate the the Fuel Fuel Handling Handling Building door Building   door usingusing the the handwheel.
handwhee!.
Which ONE Which     ONE of of the the following following isis correct correct regarding regarding the the status status of of the the Personnel Personnel Escape Escape Airlock Airlock AND Containment AND     Containment Integrity?
Integrity?
A The A.v   The Reactor Reactor Building Building door door isis OPEN.
OPEN.
The    Personnel        Escape The Personnel Escape Airlock is     Airlock  is INOPERABLE.
INOPERABLE.
B. The Reactor B. The      Reactor Building Building door door is     CLOSED.
is CLOSED.
The Personnel The   Personnel Escape Escape Airlock Airlock isis INOPERABLE.
INOPERABLE.
C. Only the Reactor C.                Reactor Building Building door position position indicator indicator has has malfunctioned.
malfunctioned.
The Personnel Escape Airlock is               is OPERABLE.
OPERABLE.
D. The Personnel Escape Airlock is OPERABLE.
D. The Personnel Escape Airlock is OPERABLE.
The Personnel Escape Airlock door interlock is INOPERABLE.
D.                                                    OPERABLE.
Feedback Distractor Analysis A Correct. The red bulkhead light and the inability to operate door operating handle NO.4 (after unlocking it) indicate that the remote (containment side) door is open. Per Tech Spec 3.6.1.3, Containment Air Locks, both airlock doors are required to be CLOSED in Mode 4 unless the air lock is being used for normal transit entry and exit. With NO personnel in containment for two hours, the air lock is NOT being used for normal transit entry and exit. B Incorrect.
The Personnel The   Personnel Escape Airlock door interlock is INOPERABLE.        INOPERABLE.
Incorrect equipment status, correct Tech Spec application.
Feedback Feedback Distractor Analysis Distractor A Correct.
See A. C. The indicator is a positive indication of the status of the door. The door is open. The Personnel Escape Airlock is INOPERABLE.
A    Correct. The red bulkhead light and the inability to operate door operating handle NO.4                          No. 4 (after unlocking (after  unlocking it) indicate that the remote (containment side) door is open. Per Tech Spec 3.6.1.3, Containment Air Locks, both airlock doors are required to be CLOSED in Mode 4 unless the air lock is being used for normal transit entry and exit. With NO personnel personnel in containment for two hours, the air lock is NOT being used for normal transit entry and exit.
D. The indicator is a positive indication of the status of the door. The door is open. The Personnel Escape Airlock is INOPERABLE.  
BB Incorrect.
Incorrect. Incorrect equipment status, correct Tech Spec application. See A.
C.C. The The indicator indicator is  is aa positive positive indication indication of of the status of of the the door.
door. The The door door isis open.
open. The The Personnel Personnel Escape Escape AirlockAirlock isis INOPERAB INOPERABLE. LE.
D.D. The The indicator indicator is  is aa positive positive indication indication of of the the status status ofof the the door.
door. The The door door isis open.
open. The The Personnel        Escape      Airlock Personnel Escape Airlock is INOPERABLE.is  INOPERABL        E.
 
==Reference:==


==Reference:==
==Reference:==


Technical Specification 3.6.1.3, Containment Air Locks KIA CATALOGUE QUESTION DESCRIPTION:  
Technical Technical Specification Specification 3.6.1.3, 3.6.1.3, Containment Containment Air   Air Locks Locks KJA KIA CATALOGU CATALOGUE         E QUESTION QUESTION DESCRIPTIDESCRIPTION:   ON:
-103 Containment System -G2.1.30 Ability to locate and operate components, including controls (3.9/3.4)
    -  103    Containment
Categories Tier: KeyWord: Source: Test: 2 CONTAINMENT AIRLOCK N S Group: Cog Level: Exam: AuthorlReviewer:
      - 103 Containment System     System
1 M (3.9/3.4)
      - G2.1  .30 Ability G2.1.30     Ability toto locate locate and and operate operate components, components, including including controls controls (3.9/3.4)
SM05301 FJEIRF AlSDR 
(3.9/3.4)
: 89. G2.I.l3 002/3//ADMINIM (2.0/2.9)/N/SM05301lSIRFAlSDR Which ONE of the following (as stated in SAP-200, Conduct of Operations) has the final authority, per Management Directive 11, for a case where an individual's condition for work inside the protected area is in question?
 
A. General Manager, Nuclear Plant Operations B ..... Shift Supervisor  
Categories Categories Tier:
: c. Management Duty Supervisor D. Security Manager Feedback Distractor Analysis:
Tier:      22                  Group:
Group:           1 Key Word:
KeyWord:     CONTAINMENTAIRLOCK CONTAINMENT AIRLOCK Cog Level:
CogLevel:       MM(3.9/3.4)
(3.9/3.4)
Source:
Source:    NN                  Exam:
Exam:            SM05301 5M05301 Test:
Test:      SS                  Author/Reviewer:
AuthorlReviewer:  FJEIRF AlSDRR FJE/RFAJSD
: 89. G2.I.l3
: 89. G2.1.13002/3//ADMINIM 002/3//ADMINIM(2.0/2.9)/N/SM05301lSIRFAlSDR (2 .O/2.9)IN/SM0530 1 !S/RFAISDR Which ONE Which         ONE of ofthe the following following (as  (as stated stated inin SAP-200, SAP-200, Conduct Conductof  ofOperations)
Operations) has has the the final final authority,    per  Management            Directive  11, authority, per Management Directive 11, for aa case where    for  case   where anan individual's individuals condition condition for forwork work inside the inside      the protected protected areaarea isis inin question?
question?
A.A. General General Manager, Manager, Nuclear Nuclear Plant Plant Operations Operations BB.v    Shift Supervisor
        ..... Shift Supervisor Management Duty c.C. Management             Duty Supervisor Supervisor D.       Security Manager D. Security        Manager Feedback Feedback Distractor Analysis:
Distractor       Analysis:
A. Incorrect:
A. Incorrect:
per SAP 200, Paragraph 6.5.2 H, page 10 B. Correct: per SAP 200, Paragraph 6.5.2 H, page 10 C. Incorrect:
A.      Incorrect: per per SAPSAP 200, 200, Paragraph Paragraph 6.5.26.5.2 H, H, page page 1010 B.      Correct: per B. Correct:       per SAP SAP 200,200, Paragraph Paragraph 6.5.2 6.5.2 H, H, page page 1010 C.      Incorrect: per C. Incorrect:       per SAPSAP 200, 200, Paragraph Paragraph 6.5.26.5.2 H, H, page page 1010 D. Incorrect:
per SAP 200, Paragraph 6.5.2 H, page 10 D. Incorrect:
D.      Incorrect: per per SAPSAP 200, Paragraph Paragraph 6.5.2 H,      H, page page 1010
per SAP 200, Paragraph 6.5.2 H, page 10
 
==Reference:==


==Reference:==
==Reference:==


SAP 200, Conduct of Operations, Paragraph 6.5.2 H, page 10 KIA CATALOGUE QUESTION DESCRIPTION:  
SAP 200, SAP        200, Conduct of Operations, Paragraph 6.5.2 H, page 10 KIA       CATALOGUE QUESTION DESCRIPTION:
-Knowledge of facility requirements for controlling vital/controlled access. Categories Tier: 3 Group: KeyWord: ADMIN Cog Level: M (2.0/2.9)
K/A CATALOGUE                                  DESCRIPTION:
Source: N Exam: SM05301 Test: S Author/Reviewer:
Knowledge of facility requirements for controlling vital/controlled
RFAlSDR 
    - Knowledge vital I controlled access.
: 90. G2.1.34 002/311CONDUCT OF OPS/CIA(2.3/2.9)/B/SM0530l/SIMC/SDR The unit is undergoing a normal heatup. Plant conditions are as follows: -Hydrazine was added when RCS temperature was 185&deg;F. -RCS temperature is 200&deg;F. -A reactor coolant sample shows dissolved oxygen concentrations of 1.1 ppm. Given the above conditions and in accordance with GOP-2,"Plant Startup and Heatup," and Tech Spec 3.4.7, "Chemistry," which ONE of the following is correct? A. Secure the Heatup, plant chemistry is NOT in compliance with GOP-2; an LCO HAS been entered. B ...... Secure the Heatup to prevent plant chemistry from NOT being in compliance with GOP-2; an LCO has NOT been entered. C. The heatup can continue, plant chemistry IS in compliance with GOP-2; an LCO HAS been entered. D. The heatup can continue, plant chemistry IS in compliance with GOP-2; an LCO has NOT been entered. Feedback DISTRACTORS:
Categories Categories Tier:
A INCORRECT Per GOP-2, RCS temperature should not be permitted to exceed 200&deg;F until oxygen scavenging of the primary is complete and chemistry is within specification.
Tier:                    33                                          Group:
B CORRECT Per GOP-2, RCS temperature should not be permitted to exceed 200&deg;F until oxygen scavenging of the primary is complete and chemistry is within specification.
Key KeyWord: Word:          ADMN ADMIN                                       Cog Level:         M (2.0/2.9)
Although the Steady State Limit for Oxygen is 0.1 ppm in Modes 1 -4, it is not applicable with Tavg 250&deg;F (per
M Source:
* note below Table 3.4-2). C INCORRECT Plant temperature has exceeded the GOP-2 limit of 200&deg;F but not the TS limit of 250&deg;F. D INCORRECT Plant temperature has exceeded the GOP-2 limit of 200&deg;F.  
Source:                 N N                                            Exam:
Exam:               SM05301 SM05301 Test:
Test:                    SS                                          Author/Revi Author/Reviewer:   RFAlSDR ewer: RFA/SDR
: 90. G2.1.34
: 90. G2.1.34 002/311CONDUCT 002/3//CONDUCT OF      OF OPS/CIA(2.3/2.9)/B/SM0530l/SIMC/SDR OPS/C/A(2.3/2.9)/B/SM0530 1/S/MC/SDR The unit The        unit isis undergoing undergoing aa normal normal heatup.
heatup. Plant Plant conditions conditions areare asas follows:
follows:
Hydrazine was
              - Hydrazine       was added added whenwhen RCSRCS temperature temperature was    was 185&deg;F.
185&deg;F.
RCS      temperature
              - RCS temperature isis 200&deg;F.
                -                                200&deg; F.
              - AA reactor
                -     reactor coolant coolant sample sample shows shows dissolved dissolved oxygen oxygen concentrations concentrations of    of 1.1 1.1 ppm.
ppm.
Given the Given          the above above conditions conditions and and inin accordance accordance with with GOP-2,"Plant GOP-2,Plant Startup Startup andand Heatup,"
Heatup, and and Tech Spec Tech                  3.4.7, "Chemistry,"
Spec 3.4.7,      Chemistry, which which ONEONE ofof the the following following isis correct?
correct?
A.A. Secure Secure the the Heatup, Heatup, plantplant chemistry chemistry isis NOT NOT inin compliance compliance with with GOP-2; GOP-2; an   an LCO LCO HASHAS been been entered.
entered.
BB.      Secure the
        ...... Secure       the Heatup Heatup to  to prevent prevent plant plant chemistry chemistry from      NOT being from NOT     being inin compliance compliance with  with GOP-2; GOP-2; an  LCO an LCO has    has NOT NOT beenbeen entered.
entered.
C. The C.        The heatup heatup cancan continue, continue, plant plant chemistry chemistry IS IS in in compliance compliance withwith GOP-2; GOP-2; an   an LCO LCO HASHAS been been entered.
entered.
D. The heatup D.                heatup can continue, plant    plant chemistry IS   IS in in compliance with GOP-2;GOP-2; an LCO   LCO hashas NOT NOT been entered.
been Feedback Feedback DISTRACTORS:
DISTRACTORS:
INCORRECT A INCORRECT                       Per GOP-2, RCS temperature should not be permitted to exceed 200&deg;F until oxygen scavenging of the primary is complete and chemistry is within specification specification..
B CORRECT                       Per GOP-2, RCS temperature should not be permitted to exceed 200&deg;F until oxygen scavenging of the primary is complete and chemistry is within specification specification.. Although the Steady State Limit for Oxygen is 0.lppm              0.1 ppm in Modes 11 - 4, it is not applicable with Tavg ~
                                                    -                                            250&deg;F
                                                                                                < 250&deg;F    (per
* note below Table 3.4-2).
CC INCORREC INCORRECT         T      Plant Plant temperature has    has exceeded the GOP-2  GOP-2 limit limit of 200&deg;F 200&deg;F but  but not not the TS TS limit limit ofof 250&deg;F.
250&deg;F.
DD INCORREC INCORRECT         T      Plant Plant temperature has    has exceeded exceeded the  the GOP-2 GOP-2 limit limit of of 200&deg;F.
200&deg;F.
REFERENC
 
==REFERENCES:==
ES:
: 1. Tech
: 1.        Tech SpecSpec Table Table 1.1,1.1, Operational "Operational Modes.
Modes."
2.
: 2. Tech  Tech SpecSpec 3.4.7, 3.4.7, Chemistry, "Chemistry," and  and Table Table 3.4-2, 3.4-2, Chemistry "Chemistry Limits.
Limits."
2:
: 2. GOP-2,Plan GOP-2,"Plantt StartupStartup and and Heatup Heatup (Mode (Mode 55 to to Mode Mode 3),    Step 2.la 3)," Step    2.1a page page 2,  2, Step Step 3.1 3.1 page page 5, 5,
              && the    Reference the Reference Page. Page.
KIA CATALOGU K/A        CATALOGUE        E QUESTION QUESTION DESCRIPTI DESCRIPTION:  ON:
      - Ability Ability to    to maintain maintain primary primary and and secondary secondary plant plant chemistry chemistry within within allowable allowable limits.
limits.
Categories Categories Tier:
Tier:                      33                                        Group:
Group:
Key KeyWord: Word:              CONDUCT CONDUCT OF      OF OPS OPS                    Cog Cog Level:
Level:          CIA(2.3/2.9)
C/A(2.3/2.9)
Source:
Source:                    BB                                        Exam:
Exam:                  SM05301 SM05301 Test:
Test:                      SS                                        Author/Reviewer: MC/SDR AuthorlReviewer:      MC/SDR
: 91. G2.2.20 OO1l31ITROUBLESHOOTINGIM2.2/3.3IMISM05301lSIFJE/SDR
: 91. G2.2.20  001 /3//TROTJBLESHOOTING/M2.2/3 .3/M/SM0530 I /S/FJE/SDR Which ONE Which    ONE of  of the the following following isis aa VIOLATION VIOLATION of        administrative procedures of administrative    procedures whenwhen troubleshooti  ng    an  INOPERABL        E system troubleshooting an INOPERABLE system or component,        or component, the      condition of the condition  of which which isis specified specified by by aa Technical Technical Specification Specification Action Action Statement.
Statement.
A AA Temporary A:"      Temporary Restoration Restoration to    Service isis used to Service        used even even though though an    alternative method an alternative  method of of completing the completing      the work work that that will will meet meet the the action action statement statement requirement requirement waswas identified.
identified.
B.B. The The troubleshooting troubleshooting requires requires posting posting aa plant plant operator operator to    immediately restore to immediately    restore an an affected affected component.
component.
C. The Temporary C. The    Temporary Inoperable Inoperable Status Status Change Change required required toto perform perform the the troubleshooting troubleshooting was  was approved by approved    by thethe Duty Duty Shift Shift Supervisor.
Supervisor.
D. The D. The Work Work Document Document also  also includes includes an an approved approved Bypass Bypass Authorization Authorization Request Request to to install install electrical electrical  jumpers.
Feedback Feedback DISTRACTORS:
DISTRACTORS:
A Correct per SAP-205, 6.7.2.B B Incorrect. Acceptable per 6.7.3.A.1. and 6.7.3.A.2. Plausible if applicant believes that immediately restore" the need to "immediately          restore would prevent a troubleshooting troubleshooting activity.
C Incorrect. SAP-205, Attachment V, Temporary Inoperable Status Change, requires approval by the Duty Shift Supervisor. Plausible because the Manager, Operations, approves some plant activities (e.g. extending the time an invalid nuisance annunciator may be removed from service).
D Incorrect. Allowed per SAP-0148 section 2.2. Plausible if applicant believes a Bypass Authorizatio Authorization  n Request is not used to authorize installation of electrical jumpers or that administrativ administrative    e procedures prohibit the use of electrical jumers during troubleshoot troubleshooting.ing.
REFERENC


==REFERENCES:==
==REFERENCES:==
: 1. Tech Spec Table 1.1, "Operational Modes." 2. Tech Spec 3.4.7, "Chemistry," and Table 3.4-2, "Chemistry Limits." 2. GOP-2,"Plant Startup and Heatup (Mode 5 to Mode 3)," Step 2.1a page 2, Step 3.1 page 5, & the Reference Page. KIA CATALOGUE QUESTION DESCRIPTION:  
ES:
-Ability to maintain primary and secondary plant chemistry within allowable limits. Categories Tier: 3 Group: KeyWord: CONDUCT OF OPS Cog Level: CIA(2.3/2.9)
1.
Source: B Exam: SM05301 Test: S AuthorlReviewer:
: 1. SAP-0205, Status Control and Removal and Restoration
MC/SDR
: 2. SAP-0148, Temporary Bypass, Jumper, and Lifted Lead Control KIA CATALOGU K/A    CATALOGUE       E QUESTION QUESTION DESCRIPTI DESCRIPTION:    ON:
: 91. G2.2.20 OO1l31ITROUBLESHOOTINGIM2.2/3.3IMISM05301lSIFJE/SDR Which ONE of the following is a VIOLATION of administrative procedures when troubleshooting an INOPERABLE system or component, the condition of which is specified by a Technical Specification Action Statement.
    - Knowledge of the process for managing managing troubleshoot troubleshootinging activities (2.2/3.3)
A:" A Temporary Restoration to Service is used even though an alternative method of completing the work that will meet the action statement requirement was identified.
Categories Tier:
B. The troubleshooting requires posting a plant operator to immediately restore an affected component.
Tier:                  33                                        Group:
C. The Temporary Inoperable Status Change required to perform the troubleshooting was approved by the Duty Shift Supervisor.
Group:
D. The Work Document also includes an approved Bypass Authorization Request to install electrical jumpers. Feedback DISTRACTORS:
Key  Word:
A Correct per SAP-205, 6.7.2.B B Incorrect.
KeyWord:               TROUBLES    HOOTfNG TROUBLESHOOTING                          Cog Cog Level:
Acceptable per 6.7.3.A.1.
Level:        M2.2/3.3 M2.2/3.3 Source:
and 6.7.3.A.2.
Source:               MM                                        Exam:
Plausible if applicant believes that the need to "immediately restore" would prevent a troubleshooting activity.
Exam:               SM05301 SM05301 Test:
C Incorrect.
Test:                  SS                                        Author/Revi AuthorlReviewer:   FJE/SDR ewer: FJE/SDR
SAP-205, Attachment V, Temporary Inoperable Status Change, requires approval by the Duty Shift Supervisor.
: 92. G2 .2.7 001l311EQUIPMENT
Plausible because the Manager, Operations, approves some plant activities (e.g. extending the time an invalid nuisance annunciator may be removed from service).
: 92. G2.2.7  001/3//EQUIPMENT CONTROLlM(2.0/3.2)/B/SM05301/S/MC/SDR CONTROL/M(2.0/3 .2)/B/SM0530 1/S/MC/SDR AA bypass bypass authorization authorization request, request, prepared prepared per per SAP-148, SAP-i 48, "Temporary Temporary Bypass, Bypass, Jumper, Jumper, and and Lifted  Lead Control,"
D Incorrect.
Lifted Lead    Control, requires requires prior prior PSRC PSRC and and NSRC NSRC review review for  which ONE for which  ONE ofof the the following following conditions?
Allowed per SAP-0148 section 2.2. Plausible if applicant believes a Bypass Authorization Request is not used to authorize installation of electrical jumpers or that administrative procedures prohibit the use of electrical jumers during troubleshooting.
conditions?
A. AA review A.      review indicates indicates that that system system operability operability will will be be affected.
affected.
B. AA review B.       review indicates indicates that that 10 10 CFR CFR 50 50 Appendix Appendix RR fire fire protection protection criteria criteria are are impacted.
impacted.
C.       review indicates C. AA review    indicates that  Seismic or that Seismic      or blowout blowout provisions provisions areare being being diminished.
diminished.
Dy      review indicates Dy AA review  indicates that that aa full  safety evaluation full safety  evaluation isis required required per   10 CFR per 10  CFR 50.59.
50.59.
Feedback Feedback DISTRACTORS:
DISTRACTORS:
INCORRECT A INCORRECT B INCORRECT INCORRECT C INCORRECT C    INCORRECT D CORRECT D   CORRECT


==REFERENCES:==
==REFERENCES:==
: 1. SAP-0205, Status Control and Removal and Restoration
: 2. SAP-0148, Temporary Bypass, Jumper, and Lifted Lead Control KIA CATALOGUE QUESTION DESCRIPTION:
-Knowledge of the process for managing troubleshooting activities (2.2/3.3)
Categories Tier: 3 Group: KeyWord: TROUBLESHOOTING Cog Level: M2.2/3.3 Source: M Exam: SM05301 Test: S AuthorlReviewer:
FJE/SDR 
: 92. G2.2.7 001l311EQUIPMENT CONTROLlM(2.0/3.2)/B/SM05301/S/MC/SDR A bypass authorization request, prepared per SAP-148, "Temporary Bypass, Jumper, and Lifted Lead Control," requires prior PSRC and NSRC review for which ONE of the following conditions?
A. A review indicates that system operability will be affected.
B. A review indicates that 10 CFR 50 Appendix R fire protection criteria are impacted.
C. A review indicates that Seismic or blowout provisions are being diminished.
Dy A review indicates that a full safety evaluation is required per 10 CFR 50.59. Feedback DISTRACTORS:
A INCORRECT B INCORRECT C INCORRECT D CORRECT


==REFERENCES:==
==REFERENCES:==
: 1. SAP-148, "Temporary Bypass, Jumper, and Lifted Lead Control." Attachment 1, page 14 of 20. KIA CATALOGUE QUESTION DESCRIPTION:  
: 1. SAP-148,
-Knowledge of the process for conducting tests or experiments not described in the safety analysis report. Categories Tier: 3 Group: KeyWord: EQUIPMENT CONTROL Cog Level: M(2.0/3.2)
: 1. SAP-i 48, "Temporary Temporary Bypass, Jumper, and Lifted Lead Control."   Control. Attachment 1, page 14 of 20.
Source: B Exam: SM05301 Test: S AuthorlReviewer:
KIA   CATALOGUE QUESTION DESCRIPTION:
MC/SDR
K/A CATALOGUE                          DESCRIPTION:
: 93. G2.3.2 002/3///M(2.5/2.9  
    - Knowledge     of the process   for conducting tests or experiments not described in the safety analysis report.
/N/SM0530l/S/RFAlSDR Which ONE of the following is correct per HPP-709, Sampling and Release of Radioactive Gaseous Effluents:
analysis    report.
Aol Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should be avoided when the wind is from the East-Southeast.
Categories Tier:
This will prevent the released activity from being drawn into the Auxiliary Building ventilation.
Tier:                33                                    Group:
B. Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should be avoided when the wind is from the West-Southwest.
Key  Word:
This will prevent the released activity from being drawn into the Auxiliary Building ventilation.
KeyWord:             EQUIPMEN EQUIPMENT   T CONTROL                 Cog Level:         M(2.0/3.2)
C. Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should be avoided when the wind is from the East-Southeast.
Source:
This will prevent the released activity from being drawn into the Control Building ventilation.
Source:              BB                                    Exam:               SM05301 Test:
D. Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should be avoided when the wind is from the West-Southwest.
Test:                SS                                    Author/Revi ewer: MC/SDR AuthorlReviewer:
This will prevent the released activity from being drawn into the Control Building ventilation.
: 93. G2.3.2
: 93. G2.3 .2 002/3///M(2.5/2.9 002/3///M(2.5/2.9)/N/SM    0530 1/SIRFA!SDR
                                /N/SM0530l/S/RFAlSDR Which ONE Which    ONE of of the the following following isis correct correct per per HPP-HPP- 709, 709, Sampling Sampling and and Release Release ofof Radioactive Radioactive Gaseous Effluents:
Gaseous      Effluents:
A. Discharges Aol   Discharges from from the    Waste Gas the Waste       Gas Decay Decay Tank Tank or or other other high high activity activity gaseous gaseous releases releases should should be  avoided    when    the  wind    is from  the  East-Southea be avoided when the wind is from the East-Southeast.             st. This  will prevent This will prevent the the released released activity activity from being from   being drawn drawn into into the  Auxiliary Building the Auxiliary   Building ventilation.
ventilation.
B.B. Discharges Discharges from from the the Waste Waste Gas   Gas Decay Decay Tank Tank or or other other high high activity activity gaseous gaseous releases releases should should be  avoided when be avoided     when thethe wind wind isis from from the the West-Southwest.
West-Southwest. This This will will prevent prevent the the released released activity from activity  from being being drawn drawn into into the the Auxiliary Auxiliary Building Building ventilation.
ventilation.
C. Discharges C. Discharges from the  the Waste Gas   Gas Decay Decay Tank Tank or or other other high high activity activity gaseous gaseous releases releases should should be  avoided be avoided when when thethe wind wind isis from from the the East-Southeast.
East-Southeast. This This will will prevent prevent the the released released activity activity from being from   being drawn drawn intointo the the Control Control Building Building ventilation.
ventilation.
D. Discharges D. Discharges from from the Waste Gas     Gas Decay Decay Tank or other high  high activity gaseous releases releases should be avoided when the wind is        is from the West-Southwest.
West-Southwest. This  This will prevent prevent the    released the released activity from being drawn into activity                          into the Control Control Building Building ventilation.
Feedback Distractor Analysis:
Feedback Distractor Analysis:
A: Correct: Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should be avoided when the wind is from the East-Southeast.
Correct: Discharges A: Correct:     Discharges from the Waste Gas Decay Tank or other high activity gaseous releases gaseous      releases should be avoided when the wind is from the East-Southeast. This will prevent the released activity from being East-Southeast.
This will prevent the released activity from being drawn into the Auxiliary Building ventilation.
drawn into drawn    into the Auxiliary Building ventilation. Per HPP-709 NOTE 5.1.H B, C, B,  C, D   Incorrect D Incorrect
Per HPP-709 NOTE 5.1.H B, C, D Incorrect  
 
==Reference:==


==Reference:==
==Reference:==


HPP-709, Sampling and Release of Radioactive Gaseous Effluents, page 10 KIA CATALOGUE QUESTION DESCRIPTION:  
HPP-HPP- 709, Sampling Sampling and Release of Radioactive Gaseous Effluents, page 10                          10 KIA CATALOGU K/A    CATALOGUE       E QUESTION DESCRIPTIDESCRIPTION:  ON:
-Knowledge of facility ALARA program. Categories Tier: 3 KeyWord: Source: N Test: S Group: Cog Level: Exam: M(2.5/2.9)
    - Knowledge of of facility ALARA ALARA program.
SM05301 AuthorlReviewer:
program.
RF AlSDR 
Categories Tier:
: 94. G2.4.33 002/311INOPERABLE ALARMIM2.4/2.8/B/SM05301lSIFJE/SDR Which ONE of the following individual's approval is required to extend the time that an invalid nuisance annunciator is removed from service past 96 hours? A. Duty Shift Engineeer B. Duty Shift Supervisor Cy Manager, Operations D. General Manager, Nuclear Plant Operations Feedback DISTRACTORS:
Tier:                  33                                      Group:
A B C Correct per OAP-100.5, Section 14.0 D  
Group:
Key  Word:
KeyWord:                                                       Cog Cog Level:
Level:         M(2.5/2.9)
M(2.5/2.9)
Source:
Source:                N N                                      Exam:
Exam:                SM05301 SM05301 Test:
Test:                  SS                                      Author/Revie  wer: RFAJSDR AuthorlReviewer:     RFAlSDR
: 94. G2.4.33
: 94. G2 .4.33 002/311INOPERABLE 002/3//iNOPERABLEALARMIM2.4/2.8/B/SM05301lSIFJE/SDR ALARM/M2.4/2 8/B/SM0530 I /S/FJE/SDR Which ONE Which      ONE of of the the following following individual's individuals approval approval isis required required to to extend extend the the time time that that an an invalid invalid nuisance   annunciator isis removed nuisance annunciator            removed from from service service past past 96 96 hours?
hours?
A. Duty A. Duty Shift Shift Engineeer Engineeer B. Duty Shift
: 8. Duty    Shift Supervisor Supervisor Manager, Operations C Manager, Cy                 Operations D. General Manager, D. General     Manager, Nuclear Nuclear Plant Plant Operations Operations Feedback Feedback DISTRACTORS:
DISTRACTORS:
A A
B B
C  Correct per C Correct     per OAP-100.5, CAP-i 00.5, Section Section 14.0 14.0 D
D


==REFERENCES:==
==REFERENCES:==
: 1. KIA CATALOGUE QUESTION DESCRIPTION:
-Knowledge of the process used to track inoperable alarms. Categories Tier: 3 Group: KeyWord: INOPERABLE ALARM Cog Level: Source: B Exam: Test: S AuthorlReviewer:
M2.4/2.8 SM05301 FJE/SDR 
: 95. G2.4.38 002/311EMERGENCY PROCEDURESIM(2.2/4.0)IMISM05301lSIMC/SDR Plant conditions are as follows: An event has occurred resulting in substantial core degradation with potential loss of containment integrity.
A General Emergency has been declared.
The prevailing wind is blowing from the south. Which ONE of the following must assume the duties of Interim Emergency Director, and to which area should he direct non-essential personnel be evacuated?
A. Shift Supervisor; Evacuate to their personal residence.
B ..... Shift Supervisor; Evacuate to the Southern Offsite Holding Area. C. Manager, Operations; Evacuate to their personal residence.
D. Manager, Operations:
Evacuate to the Southern Offsite Holding Area. Feedback DISTRACTORS:
A INCORRECT Correct individual; however, if there is a potential for personnel or vheicle contamination, the evacuation would NOT be to peronal residence.
B CORRECT C INCORRECT If there is a potential for personnel or vheicle contamination, the evacuation would NOT be to peronal residence.
D INCORRECT


==REFERENCES:==
==REFERENCES:==
: 1. SAP-109, "Management Duty Supervisor." 2. EPP-012, "Onsite Personnel Accountability and Evacuation," pages 5 and 9. KIA CATALOGUE QUESTION DESCRIPTION:  
 
-Ability to take actions called for in the facility emergency plan, including (if required) supporting or acting as emergency coordinator.
1.
Categories Tier: 3 Group: KeyWord: EMERGENCY PROCEDURES Cog Level: M(2.2/4.0)
1.
Source: M Exam: SM05301 Test: S AuthorlReviewer:
K/A CATALOGUE KIA  CATALOGUE QUESTION DESCRIPTION:    DESCRIPTION:
MC/SDR
Knowledge of the process used to track inoperable alarms.
: 96. W/E02EG2.4.6 OOl/l/2/SI TERMINATION/CIA(3.1/4.0)INISM05301/S/FJE/SDR Plant conditions are as follows: -A reactor trip and SI have occurred due to a steam break. -ALL Main Steam Isolation Valves initially failed to close. -EOP-3.1, Uncontrolled Depressurization of All Steam Generators, is in progress at Step 17, Establish Normal Charging.  
    - Knowledge Categories Categories Tier:
-PZR level is 58%. -EFW flowrate is 50 gpm to each Steam Generator due to required operator action. -All Steam Generator Narrow Range levels are 4%. -Reactor Building pressure has remained below 1 psig. -RCS pressure is 1750 psig and going UP. -Core Exit TCs are 435 OF and going DOWN. The "c" Main Steam Isolation Valve closed 30 seconds ago and "c" Steam Generator pressure has changed from 80 to 130 psig. Which ONE of the following correctly describes the actions the crew should take? A. Must remain in EOP-3.1 until the Critical Safety Function Status Trees direct entering an orange or red path Emergency Operating Procedure.
Tier:                  33                                  Group:
B. IMMEDIATELY transition to EOP-3.0, Faulted Steam Generator Isolation, Step 1. C ..... Complete EOP-3.1 thrQugh Step 20, verify SI Flow is NOT required, and then transition to EOP-3.0, Faulted Steam Generator Isolation, Step 1. D. Complete ALL steps of EOP-3.1 and then transition to EOP-1.2, Safety Injection Termination, Step 1.
Key  Word:
Feedback DISTRACTORS:
KeyWord:              INOPERAB INOPERABLE  LE ALARM                Cog Level:          M2.4/2.8 Source:
A Incorrect.
Source:                B                                  Exam:                SM05301 Test:
The C SG pressure has increased.
Test:                  SS                                  Author/Revi AuthorlReviewer:
Per EOP-3.1 Reference Page item 2, Secondary Integrity Transition Criteria, the crew should go to EOP-3.0, Faulted Steam Generator Isolation, Step 1, after completing EOP-3.0 SI Termination steps 15 through 20. Plausible if applicant does not recognize secondary integrity transition criteria.
ewer: FJE/SDR
B Incorrect.
: 95. G2.4.38
Per EOP-3.1, Reference Page item 2, the crew should go to EOP-3.0 if any SG pressure increases at any time EXCEPT while performing SI Termination in steps 15 through 20. Plausilbe if applicant does not recognize step number or step description as an SI Termination step or does not remember an exception to Secondary Integrigy Transition Critierion.
: 95. G2.4.38 002/311EMERGENCY 002/3//EMERGENCY PROCEDURESIM(2.2/4.0)IMISM05301lSIMC/SDR PROCEDURESJM(2 .2/4.0)/M/SM0530 1/S/MC/SDR Plant conditions Plant      conditions are are as as follows:
C Correct per EOP-3.1, Reference Page, item 2, Secondary Integrity Transition Criterion.
follows:
D Incorrect.
* An event An  event hashas occurred occurred resulting resulting inin substantial substantial core core degradation degradation with with potential potential loss of loss  of containment containment integrity.
Per EOP-3.1 Reference Page, item 2, the crew should transition to EOP-3.0 after completing SI Termination in Steps 15 through 20. Plausible because the last step of EOP-3.0, Faulted Steam Generator Isolation, directs a transition to EOP-1.2.  
integrity.
* AA General General Emergency Emergency has    has been been declared.
declared.
* The  prevailing    wind    is  blowing The prevailing wind is blowing from the    from  the south.
south.
Which ONE Which        ONE of of the  following must the following      must assume assume thethe duties duties of of Interim Interim Emergency Emergency Director, Director, and and to to which area which      area should should he    direct non-essential he direct    non-essential personnel personnel be be evacuated?
evacuated?
A. Shift A.        Shift Supervisor; Supervisor; Evacuate Evacuate to    to their their personal personal residence.
residence.
BB.%    Shift Supervisor;
        ..... Shift Supervisor; Evacuate Evacuate to    to the the Southern Southern Offsite Offsite Holding Holding Area.
Area.
C.        Manager, Operations; C. Manager,        Operations; Evacuate Evacuate to    to their personal personal residence.
residence.
D.      Manager, Operations:
D. Manager,        Operations: Evacuate Evacuate to    to the the Southern Southern Offsite Offsite Holding Holding Area.
Area.
Feedback Feedback DISTRACTORS:
DISTRACTORS:
A        INCORRECT A INCORRECT                  Correct individual; however, if there is a potential for personnel or vheicle contamination, the evacuation would NOT be to peronal residence.
contamination, B CORRECT B      CORRECT C INCORRECT C        INCORRECT          If there is a potential for personnel or vheicle contaminatio contamination,  n, the evacuation would NOT be to peronal residence.
D D INCORREC INCORRECT    T REFERENC
 
==REFERENCES:==
ES:
1.
: 1. SAP-109, Managemen "Managementt Duty Supervisor.
Supervisor."
: 2.        EPP-012,    Onsite    Personnel
: 2. EPP-012, "Onsite Personnel Accountability     Accountabili    ty and and Evacuation, Evacuation," pages pages 55 and and 9.
9.
KIA CATALOGU K/A      CATALOGUE       E QUESTION QUESTION DESCRIPTIDESCRIPTION:  ON:
    - Ability Ability to to take take actions actions called called forfor in in the the facility facility emergency emergency plan, plan, including including (if (if required) required) supporting supporting or    or acting acting asas emergcy emergency coordinator.
coordinator.
Categories Categories Tier:
Tier:                    33                                          Group:
Group:
Key KeyWord: Word:          EMERGENC EMERGENCY     Y PROCEDUR PROCEDURES     ES        Cog Cog Level:
Level:        M(2.2/4.0)
M(2.2/4.0)
Source:
Source:                 MM                                          Exam:
Exam:               SM05301 5M05301 Test:
Test:                   SS                                          Author/Revi AuthorlReviewer:
ewer: MC/SDR MC/SDR
: 96. W/E02EG2.4.6
: 96. W/EO2EG2 .4.6 OOl/l/2/SI 001/1/2/SITERMINATION/CIA(3.1/4.0)INISM05301/S/FJE/SDR TERMINATION/C/A(3.1 /4.0)/N/SM0530 I /S/FJE/SDR Plant conditions Plant       conditions areare as as follows:
follows:
    - AA reactor
      -       reactor trip   and SI trip and    SI have    occurred due have occurred     due toto aa steam steam break.
break.
    - ALL
      -   ALL Main Main Steam Steam Isolation Isolation Valves Valves initially initially failed failed to to close.
close.
EOP-3.1, Uncontrolled
    - EOP-3.1,
      -                Uncontrolled Depressurization Depressurization of   of All All Steam Steam Generators, Generators, isis inin progress progress at at Step Step 17, 17, Establish Normal Establish    Normal Charging.
Charging.
    - PZR
      -   PZR level level isis 58%.
58%.
      -    EFW    flowrate
    - EFW flowrate isis 50    50 gpm gpm to   each Steam to each  Steam Generator Generator due  due to to required required operator operator action.
action.
All  Steam    Generator Narrow
    - All Steam Generator
      -                                Narrow Range Range levels levels areare 4%.
4%.
Reactor Building
    - Reactor
    -              Building pressure pressure has has remained remained belowbelow 11 psig.
psig.
    - RCS
    -     RCS pressure pressure isis 1750 1750 psig      and going psig and   going UP.
UP.
    - Core
    -            Exit TCs Core Exit    TCs areare 435 435 OF &deg;F and  going DOWN.
and going     DOWN.
The "c" The            Main Steam C Main    Steam Isolation Isolation Valve Valve closed closed 30 30 seconds seconds ago       and "c" ago and  C Steam Steam Generator Generator pressure pressure has changed has       changed from 80  80 to 130130 psig.
psig.
Which ONE    ONE of the following following correctly correctly describes describes the actions actions the the crew crew should should take?
take?
A. Must remain in EOP-3.1 until the Critical Safety Function A.                                                                      Function Status Trees direct entering an orange or red path Emergency Operating Procedure.
IMMEDIATELY transition to EOP-3.0, Faulted Steam Generator Isolation, Step 1.
B. IMMEDIATELY Cv C ..... Complete EOP-3.1 thrQugh through Step 20, verify SI Flow is NOT required, and then transition to              to EOP-3.0, Faulted Steam Generator Isolation, Step 1.
D. Complete ALL steps of EOP-3.1 and then transition to EOP-1.2, Safety Injection D.
Termination, Step 1.
 
Feedback Feedback DISTRACTORS:
DISTRACTORS:
AA Incorrect.
Incorrect. The The CC SGSG pressure pressure has  has increased.
increased. Per Per EOP-3.1 EOP-3.1 Reference Reference Page  Page item item 2,2, Secondary Integrity Secondary        Integrity Transition Transition Criteria, Criteria, the the crew crew should should go go to to EOP-3.0, Faulted Steam EOP-3.0,     Faulted     Steam Generator    Isolation,  Step    1,  after  completing Generator Isolation, Step 1, after completing EOP-3.0 SI       EOP-3.0    SI Termination Termination steps steps 15 15 through through 20.
20.
Plausible ifif applicant Plausible       applicant does does notnot recognize recognize secondary secondary integrity integrity transition transition criteria.
criteria.
Incorrect. Per BB Incorrect.       Per EOP-3.1, EOP-3.1, Reference Reference Page    Page item item 2,2, the  crew should the crew   should go  go to to EOP-3.0 EOP-3.0 ifif any any SG SG pressure pressure increases increases at     any time at any  time EXCEPT EXCEPT while while performing performing SI  SI Termination Termination inin steps steps 1515 through through 20.20. Plausilbe Plausilbe ifif applicant applicant does does not    recognize step not recognize     step number number or or step step description description as an as   an SI SI Termination Termination stepstep oror does does notnot remember remember an    an exception exception to  to Secondary Secondary Integrigy Integrigy Transition     Critierion.
Transition Critierion.
CC Correct Correct per    EOP-3.1, Reference per EOP-3.1,     Reference Page,  Page, item item 2,2, Secondary Secondary Integrity Integrity Transition Transition Criterion.
Criterion.
D     Incorrect. Per D Incorrect.      Per EOP-3.1 EOP-3.1 Reference Reference Page,  Page, item item 2,2, the crew crew should transition to     to EOP-3.0 EOP-3.0 after    completing    SI Termination      in  Steps after completing SI Termination in Steps 15 through      15  through 20.20. Plausible Plausible because because the the last last step step of of EOP-3.0, Faulted EOP-3.0,      Faulted Steam Steam Generator Generator Isolation, Isolation, directs a transition to EOP-1.2.EOP-1 .2.
 
==REFERENCES:==


==REFERENCES:==
==REFERENCES:==
: 1. EOP-3.1, Uncontrolled Depressurization of All Steam Generators  
: 1. EOP-3.1, Uncontrolled Depressurization
: 2. EOP-3.1 LP, Uncontrolled Depressurization of All Steam Generators Lesson Plan KIA CATALOGUE QUESTION DESCRIPTION:  
: 1.                                Depressurization of All Steam Generators
-W/E02 SI Termination  
: 2. EOP-3.1 EOP3. 1 LP, Uncontrolled Depressurization Depressurization of All Steam Generators Lesson Plan K/A CATALOGUE KIA     CATALOGUE QUESTION DESCRIPTION:    DESCRIPTION:
-Knowledge symptom based EOP mitigation strategies (3.1/4.0).
- W/E02 SI Termination Knowledge symptom based EOP mitigation strategies (3.1/4.0).
Categories Tier: Group: 2 KeyWord: SI TERMINATION Cog Level: CI A(3 .114.0) Source: N Exam: SM05301 Test: S AuthorlReviewer:
- Knowledge Categories Tier:                   1                                          Group:               22 Key KeyWord:Word:          SI TERMINAT TERMINATION ION                        Cog Level:             CIA(3 .114.0)
FJE/SDR
C/A(3.l/4O)
: 97. W/EOSEA2.1 00 1111 1 IHEAT SINK/CIA (3.4/4.4)/B/SMOS30IlS/GWLIRFAlSDR The Crew has entered EOP-16.0 "Response to Pressurized Thermal Shock" due to an Orange path on the integrity CSF status tree. The Crew is at the step for Checking RCS Tcold Stable or Increasing.
Source:
While checking EFW flow it is determined that a Red path condition exists on the Heat Sink CSF status tree. Which ONE of the following correctly describes the action that should be taken by the crew? A. Remain in EOP-16.0 until it is completed, then transition to EOP-1S.0, Response to Loss of Secondary Heat Sink. B. Remain in EOP-16.0 until the Orange path is cleared, then tranistion to EOP-1S.0.
Source:               N                                           Exam:                   SM05301 Test:
CY' IMMEDIATELY transition to EOP-1S.0.
Test:                  SS                                          Author/Revi AuthorlReviewer:
D. The transition to EOP-1S.0 is NOT required since EOP 16.0 provides actions for adjusting EFW. Feedback DISTRACTORS:
ewer: FJE/SDR
: 97. W/EOSEA2.1
: 97. W/EO5EA2. 00   001/1/1/HEA 1111 1IHEATT SINK/CIA SNKJC/A (3.4/4.4)/B/SMOS30IlS/GWLIRFAlSDR (3 .4/4.4)/B/SM0530 1/S/GWL/RFAJSDR The Crew The   Crew has      entered EOP-16.0 has entered       EOP-16.0 "Response Response to      Pressurized Thermal to Pressurized       Thermal Shock" Shock duedue to to an an Orange Orange pathpath on      the integrity on the   integrity CSF  CSF status status tree.
tree. The The Crew Crew isis at at the the step step for for Checking Checking RCS RCS Tcold Tcold Stable or Stable    or Increasing.
Increasing.
While checking While    checking EFW EFW flowflow itit isis determined determined that         Red path that aa Red   path condition condition exists exists on on the the Heat Heat Sink Sink CSF    status  tree.
CSF status tree.
Which ONE Which     ONE of  of the the following following correctly correctly describes describes thethe action action that that should should bebe taken taken byby the the crew?
crew?
A. Remain A. Remain in  in EOP-16.0 EOP-16.O untiluntil itit isis completed, completed, then then transition transition toto EOP-1S.0, EOP-15.0, Response Response to  to Loss Loss of of Secondary Heat Secondary        Heat Sink.
Sink.
B. Remain in B. Remain          EOP-16.0 until in EOP-16.0       until the OrangeOrange path path is is cleared, cleared, then then tranistion tranistion to to EOP-1S.0.
EOP-15.O.
CY'   IMMEDIATELY transition C IMMEDIATELY             transition to        EOP-15.0.
to EOP-1S.0.
D. The transition to EOP-1S.0 D.                            EOP-15.0 is      is NOT NOT required required since EOP EOP 16.0       provides actions for adjusting 16.0 provides E FW.
EFW.
Feedback DISTRACTORS:
DISTRACTORS:
A Incorrect, a red path exists for heat sink and it has priorty over integrity, the operator should tranistion immediately.
A Incorrect, a red path exists for heat sink and it has priorty over integrity, the operator should tranistion immediately.
B Incorrect, a red path exists for heat sink and it has priorty over integrity, the operator should tranistion immediately.
immediately.
C Correct, the operator should transition to EOP-1S.0 immediately.
B Incorrect, a red path exists for heat sink and it has priorty over integrity, the operator should immediately.
D Incorrect, a red path exists for heat sink and it has priorty over integrity, the operator should tranistion immediately.
tranistion immediately.
EOP-1S.0 has a caution that states: If total EFW flow is LESS THAN 4S0 gpm due to operator action, this procedure should NOT be performed, since these actions are NOT appropriate if 4S0 gpm EFW flow is available.
C Correct, the operator should transition to EOP-1S.0           EOP-15.0 immediately.
The stem does not support this and EOP-1S.0 must be transitioned to for this CAUTION to apply.  
immediately.
D D Incorrect, aa red path exists for heat sink and it has priorty over integrity, the operator should tranistion immediately.
immediately. EOP-1S.0 EOP-15.0 has a caution that states:
If total EFW flow is LESS THAN 450                4S0 gpm due to operator action, this procedure should NOT be performed, since these actions are NOT appropriate if 450                        4S0 gpm EFW flow is available.
The stem does not support this and EOP-1              EOP-1S.05.0 must be transitioned to for this CAUTION to apply.
REFERENC


==REFERENCES:==
==REFERENCES:==
: 1. EOP-1S.0, 16.0, 12.0.
ES:
Summer Exam bank question EOPS 38S. KIA CATALOGUE QUESTION DESCRIPTION:
1.
WEOSEA2.1 Ability to operate and 1 or monitor the folowing as they apply to the (Loss of Secondary Heat Sink) Facility conditions and selection of appropriate procedures during abnormal and emergency operations.  
: 1. EOP-EOP- 15.0, 1S.0, 16.0, 16.0, 12.0.
12.0. Summer Summer Exam      Exam bank bank question question EOPS EOPS 385. 38S.
K/A KIA CATALOGU CATALOGUE       E QUESTION QUESTION DESCRIPTI  DESCRIPTION:    ON:
WEO5EA2.1 WEOSEA2.1 Ability  Ability to to operate operate and   and I1oror monitor monitor the the folowing folowing as  as they they apply apply toto the the (Loss (Loss ofof Secondary Secondary Heat Heat Sink)
Sink) Facility Facility conditions conditions and and selection selection of of appropriate appropriate procedures procedures during during abnormal abnormal and and emergency emergency operations.
operations. (3.4/4.4) (3.4/4.4)
 
Categories Categories Tier:
Tier:        I        Group:
Group:          1I Key    Word:
KeyWord:      HEAT SINK HEAT  SINK Cog Level:
Cog Level:      CIA C/A (3.4/4.4)
(3.4/4.4)
(3.4/4.4)
Categories Tier: KeyWord: Source: Test: HEAT SINK B S Group: 1 Cog Level: CIA (3.4/4.4)
Source:
Exam: SM0530 1 AuthorlReviewer:
Source:     BB        Exam:
GWLlRF AlSDR 
Exam:           SM0530 SM05301  1 Test:
: 98. W/E09EA2.2 OOll112!NATURAL CIRCIC/A(3.4/3.8)IMISM05301lS/GWLlSDR A Reactor Trip with a loss of Off-site power has occurred.
Test:        SS        Author/Reviewer:
Power will not be restored for at least eight hours, and a cooldown is desired. -RCS temperature is currently 557 of -Only one CRDM fan is operable.
AuthorlReviewer: GWLlRF GWL/RFAJSAlSDRDR
Which ONE of the following correctly describes the actions to be taken in accordance with EOP-1.3 "Natural Circulation Cooldown"?
: 98. W/E09EA2.2
A. Reduce RCS pressure to below 1925 psig, maintain RCS subcooing greater than 80 of, cooldown shall not exceed 50 of/hr. B.",; Maintain RCS pressure above 1925 psig, maintain RCS subcooling greater than 130 of and cooldown shall not exceed 50 of/hr. C. Reduce RCS pressure to below 1925 psig, maintain RCS subcooing greater than 130 of, cooldown shall not exceed 25 of/hr. D. Maintain RCS pressure above 1925 psig, maintain RCS subcooling greater than 80 of and cooldown shall not exceed 25 of/hr. Feedback DISTRACTORS:
: 98. W/EO9EA2.2 OOll112!NATURAL 001 / 1 /2/NATURALCIRCIC/A(3.4/3.8)IMISM05301lS/GWLlSDR CIRC/C/A(3 .4/3. 8)/M/SM0530 1/S/GWL/SDR AA Reactor Reactor TripTrip with with aa loss loss of   Off-site power of Off-site  power hashas occurred.
A Incorrect, RCS pressure should not be reduced, subcooling must be greater than 130 0 F. B Correct, RCS pressure should be maintained above 1925, subcooling must be greater than 130 0 F, and cooldown is limited to 50 0 F/hr. C Incorrect, RCS pressure should not be reduced, subcooling must be greater than 130 of, and the cooldown is limited to 50 of/hr. D Incorrect, the cooldown is limited to 50 of/hr.  
occurred. Power Power willwill not not be be restored restored for for atat least   eight hours, and least eight hours,          and aa cooldown cooldown isis desired.
desired.
RCS temperature
            - RCS
            -      temperature isis currently currently 557 557 of&deg;F Only one
            - Only
            -              CRDM fan one CRDM         fan isis operable.
operable.
Which ONE Which      ONE of    the following of the   following correctly correctly describes describes the    actions to the actions   to be be taken taken inin accordance accordance with with EOP-1      .3 Natural      Circulation EOP-1.3 "Natural Circulation Cooldown"?      Cooldown?
A. Reduce A.      Reduce RCSRCS pressure pressure to       below 1925 to below    1925 psig, psig, maintain maintain RCS RCS subcooing subcooing greater greater than than 80 80 of,
                                                                                                                              &deg;F, cooldown shall cooldown      shall not not exceed exceed 50  50 of/hr.
                                                        &deg;F/hr.
B. Maintain B.",;   Maintain RCS RCS pressure pressure aboveabove 1925 1925 psig, psig, maintain maintain RCSRCS subcooling subcooling greater greater than than 130 130&deg;F of and cooldown cooldown shall not    not exceed 50 of/hr.F/hr.
0 Reduce RCS C. Reduce         RCS pressure to below      below 1925 1925 psig, maintain RCS subcooing greater than 130            130 of,&deg;F, cooldown shall not exceed 25 of/hr.       &deg;F!hr.
D. Maintain RCS pressure above 1925 psig, maintain RCS subcooling greater than 80                                   80&deg;Fof and cooldown shall not exceed 25 of/hr.       &deg;F/hr.
Feedback DISTRACTORS:
DISTRACTORS:
A Incorrect, RCS pressure should not be reduced, subcooling must be greater than 130                               130&deg;F.0 F.
BB Correct, RCS pressure should be maintained above 1925,                      1925, subcooling must be greater than 130&deg;F, 0
130 F,   and   cooldown         is limited to 50F 0  0 50/hr.
F/hr.
CC Incorrect, Incorrect, RCS pressure should not be reduced, subcooling must be greater than 130                           130 &deg;F,of, and  the  cooldown and the cooldown is       is limited limited toto 50 50 &deg;F/hr.
of/hr.
DD Incorrect, Incorrect, the cooldown is         is limited limited to   50 0 to 50  F /hr.
of/hr.
REFERENC


==REFERENCES:==
==REFERENCES:==
: 1. EOP-1.3 Natrual Circulation Cooldown.
ES:
KIA CATALOGUE QUESTION DESCRIPTION:
1.
WE09EA2.2 Ability to operate and / or monitor the following as they apply to the (Natural Circulation Operations)
: 1. EOP-1 EOP-1.3 .3 Natrual Natrual Circulation Circulation Cooldown.
Adherence to appropriate procedures and operation within the limits in the facilitys's license and amendments.  
Cooldown.
K/A KIA CATALOGU CATALOGUE       E QUESTION QUESTION DESCRIPTI DESCRIPTION:  ON:
WEO9EA2.2 WE09EA2.2 Ability   Ability to to operate operate and        or monitor and // or           the following monitor the   following as as they they apply apply toto the the (Natural (Natural Circulation       Operations)
Circulation Operations) Adherence    Adherence to  to appropriate appropriate procedures procedures and and operation operation within within the the limits limits inin the the facilityss facilitys's license license and and amendments amendments.     . (3.4/3.8)
(3.4/3.8)
(3.4/3.8)
Categories Tier: Group: 2 KeyWord: NATURAL CIRC Cog Level: C/A(3.4/3.8)
Categories Categories Tier:
Source: M Exam: SM05301 Test: S AuthorlReviewer:
Tier:                    1                                          Group:
GWLlSDR
Group:              22 Key    Word:
: 99. W/E12EG2.4.4 0021111/STEAM LINE RUPTURE/C/A(4.014.3  
KeyWord:               NATURAL NATURAL CIRC   CIRC                      Cog Cog Level:
/N/SM05301lSIFJE/SDR Plant conditions are as follows: -The Unit experienced a Steam Generator Tube Rupture (SGTR) on the "8" Steam Generator (SG). -The crew is currently performing EOP-4.0, Steam Generator Tube Rupture, Step 3, Isolate flow from each RUPTURED SG. When the crew transitioned from EOP-1.0 to EOP-4.0, FOUR (4) minutes ago, plant parameters were as listed below: Loop A Loop 8 Loop C SG Pressure 800 psig 1200 psig 800 psig SG NR Level 40% 80% 45% SG PORV SHUT OPEN SHUT RCS Temperature 557 of 556 of 557 of RCS Pressure:
Level:          C/A(3.4/3.8)
1350 psig NOTE: ALL plant parameters were stable, with the exception of 8 SG NR Level, which was going UP. CURRENT plant parameters are as follows: SG Pressure SG NR Level SG PORV RCS Temperature RCS Pressure:
C/A(3.4/3.8)
1000 psig Loop A 500 psig 20% SHUT 520 of Loop 8 1050 psig 85% SHUT 550 of Loop C 750 psig 45% SHUT 550 of ALL above parameters are all decreasing (going DOWN), with Loop A parameters decreasing faster than Loops 8 and C. Which ONE of the following correctly describes the NEXT action the crew should take in accordance with Emergency Operating Procedures?
Source:
A. IMMEDIATELY go to EOP-2.0, Loss of Reactor or Secondary Coolant. B.II IMMEDIATELY go to EOP-3.0, Faulted Steam Generator Isolation.
Source:                M M                                         Exam:
C. RETURN to EOP-4.0, Steam Generator Tube Rupture, Step 1. D. COMPLETE EOP-4.0, Step 3 and THEN go to EOP-3.0, Faulted Steam Generator Isolation.
Exam:               SM05301 SM05301 Test:
Feedback DISTRACTORS:
Test:                    SS                                        Author/Revie AuthorlReviewer:
A Incorrect.
wer:    GWLlSDR GWL/SDR
Plausible if applicant believes a LOCA is now in progress.
: 99. W/E12EG2.4.4
A LOCA would be indicated by decreasing RCS pressure and Loop B SG pressure ONLY, NOT a large decrease in Loop A SG pressure, level, and RCS temperature.
: 99. W/E 1 2EG2.4.4 0021111/STEAM 002/1/1/STEAM LINE  LINE RUPTURE/C/A(4.014.3 RUPTURE/C/A(4.0/4.3)/N    /SM0530 1/S/FJE/SDR
B Correct per EOP-4.0, Reference Page, Secondary Integrity Transition Criteria C Incorrect.
                                                                        /N/SM05301lSIFJE/SDR Plant conditions Plant    conditions are are as   follows:
Plausible because this is item 4 (Multiple Tube Rupture Criteria) on the EOP-4.0 reference page. D Incorrect.
as follows:
EOP rules of usage require immediate transition after performing applicable immediate actions. EOP-4.0 does not contain any immediate actions. Plausible if applicant believes that completely isolating the ruptured SG is a higher priority than isolating the faulted SG.  
The Unit
          - The
            -      Unit experienced experienced aa Steam Steam Generator Generator Tube Tube Rupture Rupture (SGTR)
(SGTR) on on the the "8" B Steam Steam Generator (SG).
Generator      (SG).
The crew
          - The
            -      crew isis currently currently performing performing EOP-4.0, EOP-4.0, Steam Steam Generator Generator Tube Tube Rupture, Rupture, Step Step 3, 3,
Isolate flow  from    each  RUPTURED Isolate flow from each RUPTURED SG.           SG.
When the When      the crew crew transitioned transitioned from from EOP-1.0 EOP-1 .0 to  EOP-4.0, FOUR to EOP-4.0,     FOUR (4)(4) minutes minutes ago, ago, plant plant parameters were parameters       were asas listed listed below:
below:
Loop AA Loop              Loop 8B Loop            Loop Loop C C SG Pressure SG     Pressure                     800 psig 800  psig        1200 psig 1200   psig    800 psig 800   psig SG    NR SG NR Level Level                        40%
40%                  80%
80%            45%
45%
SGPORV SG   PORV                           SHUT SHUT               OPEN OPEN           SHUT SHUT RCS    Temperature RCS Temperature                     557 of 557  &deg;F          556 556 of&deg;F      557 557 of&deg;F RCS Pressure: 1350 psig NOTE: ALL plant parameters were stable, with the exception of 8B SG NR Level, which was going UP.
CURRENT plant parameters are as follows:
CURRENT Loop A            Loop 8  B        Loop C SG Pressure                         500 psig          1050 psig      750 psig SG NR Level                           20%                85%            45%
SGPORV SG   PORV                           SHUT              SHUT          SHUT RCS Temperature                     520 &deg;Fof          550 &deg;Fof        550 &deg;Fof RCS Pressure: 1000    1000 psig ALL above parameters are       are all all decreasing (going (going DOWN),
DOWN), withwith Loop Loop A parameters decreasing faster than Loops   Loops B8 and and C.
Which ONE ONE ofof the the following correctly describes describes thethe NEXT NEXT action action the the crew crew should should take take in in accordance accordance with with Emergency Emergency Operating Operating Procedures?
Procedures?
A. IMMEDIAT A. IMMEDIATELY   ELY go    to EOP-2.0, go to   EOP-2.0, Loss Loss of of Reactor Reactor or or Secondary Secondary Coolant.
Coolant.
B B.II IMMEDIAT IMMEDIATELY   ELY go go to to EOP-3.0, EOP-3.0, Faulted Faulted Steam Steam Generator Generator Isolation.
Isolation.
C. RETURN C. RETURN to     to EOP-4.0, EOP-4.0, Steam Steam Generator Generator Tube Tube Rupture, Rupture, Step Step 1.1.
D. COMPLETE D. COMPLETE EOP-4.0, EOP-4.0, Step Step 33 and and THEN THEN gogo toto EOP-3.0, EOP-3.0, Faulted Faulted Steam Steam Generator Generator Isolation.
Isolation.
 
Feedback Feedback DISTRACTORS:
DISTRACTORS:
AA Incorrect.
Incorrect. Plausible Plausible ifif applicant applicant believes believes aa LOCALOCA isis now now inin progress.
progress. AA LOCA LOCA would would bebe indicated by indicated   by decreasing decreasing RCS  RCS pressure pressure and  and Loop Loop BB SG SG pressure ONLY, NOT a large pressure      ONLY,    NOT    a  large decrease inin Loop decrease       Loop AA SG SG pressure, pressure, level, level, and and RCSRCS temperature.
temperature.
BB Correct Correct per    EOP-4.0, Reference per EOP-4.0,       Reference Page, Page, Secondary Secondary Integrity Integrity Transition Transition Criteria Criteria C  Incorrect. Plausible C Incorrect. Plausible because because this this isis item item 44 (Multiple (Multiple Tube Tube Rupture Rupture Criteria)
Criteria) on on the the EOP-4.O reference EOP-4.0     reference page.
page.
DD Incorrect.
Incorrect. EOPEOP rules rules of   usage require of usage  require immediate immediate transition transition after after performing performing applicable applicable immediate    actions. EOP-4.0 immediate actions.       EOP-4.0 doesdoes not not contain contain anyany immediate immediate actions.         Plausible ifif actions. Plausible applicant believes applicant   believes that that completely completely isolating isolating thethe ruptured ruptured SGSG is is aa higher higher priority priority than than isolating the isolating      faulted SG.
the faulted  SG.
 
==REFERENCES:==


==REFERENCES:==
==REFERENCES:==
: 1. EOP-4.0, Steam Generator Tube Rupture, Reference Page, item 2, Secondary Integrity Transition Criteria.  
: 1. EOP-4.0,
: 2. EO-2, Usage of Emergency Operating Procedures.
: 1. EOP-4.0, Steam Generator Generator Tube Tube Rupture, Rupture, Reference Page,   Page, item item 2, Secondary Integrity Integrity Transition Criteria.
KIA CATALOGUE QUESTION DESCRIPTION:  
Emergency Operating Procedures.
-W/E12 Steam Line Rupture -Excessive Heat Transfer -G2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures (4.0/4.3).
: 2. EO-2, Usage of Emergency                           Procedures.
Categories Tier: KeyWord: Source: Test: STEAM LINE RUPTURE N S Group: 1 Cog Level: CIA(4.0/4.3)
KIA   CATALOGUE QUESTION DESCRIPTION:
Exam: SM0530 1 AuthorlReviewer:
K/A CATALOGUE                          DESCRIPTION:
FJE/SDR 100. W/E13EG2.2.25 00ll1l2/S/G OVERPRESSUREIM2.5/3.7/N/SM05301lSIFJE/SDR Which ONE of the following describes the basis for reducing the Power Range Neutron Flux High Trip Setpoint, in accordance with Summer Technical Specification Table 3.7-1, if one or more main steam line code safety valves are inoperable for more than 4 hours? A.II To ensure that sufficient relieving capacity is available to limit secondary system pressure to within 110% of design pressure.
- W/E12     Steam   Line Rupture     -
B. To minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown of the INOPERABLE safety valve(s).
                                      - Excessive     Heat Transfer
C. To limit the pressure rise within the reactor building to within the values assumed in the accident analysis in the event of a steam line rupture within the reactor building.
- G2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures (4.0/4.3).
D. To ensure that pressure induced stresses in the steam generator with the INOPERABLE safety valve(s) do not exceed the maximum allowable fracture toughness stress limits. Feedback DISTRACTORS:
entry-level Categories Categories Tier:                 1                                        Group:               11 Key  Word:
A Correct per Summer Technical Specification Bases 3/4.7.1.1, page B 3/4 7-1, paragraph  
KeyWord:             STEAM LINE RUPTURE                       Cog Level:           CIA(4.0/4.3)
: 2. B Incorrect.
C/A(4.O/4.3)
Plausible because this is part of the basis for the operability of MSIVs and FWIVs. C Incorrect.
Source:
Plausible because this is part of the basis for the operability of the MSIVs and FWIVs. D Incorrect.
Source:            N                                          Exam:               SM0530 1 SM05301 Test:
Plausible because this is the basis for the Steam Generator Pressure / Temperature limitiation (3.7.2). Fracture toughness (brittle fracture) is not a concern at NOP/NOT.  
Test:                SS                                        Author/Revi AuthorlReviewer:     FJE/SDR ewer: FJE!SDR
 
1 00.W/E13EG2.2.25 100. W/E1 3EG2.2.2500ll1l2/S/G 00 1/1/2/S/GOVERPRESSUREIM2.5/3.7/N/SM05301lSIFJE/SDR OVERPRESSURE/M2.5/3.7/N/SM0530 1/SIFJE/SDR Which ONE Which      ONEofofthe thefollowing following describes describesthe  thebasis basisforforreducing reducingthe  thePower PowerRange Range Neutron Neutron FluxFlux High    Trip Setpoint,      in  accordance High Trip Setpoint, in accordance with            with Summer SummerTechnical Technical Specification SpecificationTableTable3.7-1, 3.7-1, ififone oneor or more main more      main steam steam lineline code codesafety safetyvalves valves are are inoperable inoperablefor  formore morethanthan 44 hours?
hours?
A.v To A.II   To ensure ensure that thatsufficient sufficient relieving relieving capacity capacityisis available availabletoto limit limit secondary secondarysystem system pressure pressure to  within  110%    of  design to within 110% of design pressure. pressure.
B.B. To To minimize minimize the the positive positive reactivity reactivity effects effects ofofthe the Reactor Reactor Coolant Coolant System System cooldown cooldown associated      with associated with the    the blowdown blowdown of  of the the INOPERABLE INOPERABLE safety  safety valve(s).
valve(s).
C.C. To To limit limit the   pressure rise the pressure      rise within within the the reactor reactor building building to to within within thethe values values assumed assumed inin thethe accident    analysis    in the event    of  a  steam    line accident analysis in the event of a steam line rupture within    rupture    within the the reactor reactor building.
building.
D.D. To To ensure ensure thatthat pressure pressure induced induced stresses stresses inin the the steam steam generator generator with with the the INOPERABLE INOPERABLE safety  valve(s) do safety valve(s)       do not not exceed exceed the the maximum maximum allowable allowable fracture fracture toughness toughness stress stress limits.
limits.
Feedback Feedback DISTRACTORS:
DISTRACTORS:
A Correct A    Correct per per Summer Summer Technical Specification Specification Bases 3/4.7.1.1, 3/4.7.1.1, page page B B 3/4 3/4 7-1, 7-1, paragraph paragraph 2. 2.
BB Incorrect.
Incorrect. Plausible because this is part of the basis for the operability of MSIVs and FWIVs.
FWIVs.
C Incorrect.
C    Incorrect. Plausible because this is part of the basis for the operability of the MSIVs and FWIVs.
and    FWIVs.
D Incorrect.
D    Incorrect. Plausible Plausible because this is the basis for the Steam Generator Pressure I/
Temperature Temperature limitiation (3.7.2). Fracture toughness (brittle fracture) is not a concern at                            at NOP/NOT.
NOP/NOT.
REFERENC


==REFERENCES:==
==REFERENCES:==
: 1. Summer Technical Specification Bases 3/4.7.1.1, 3/4.7.1.5, 3/4.7.1.6, 3/4.7.2 KJA CATALOGUE QUESTION DESCRIPTION:  
ES:
-W/E 13 Steam Generator Over-pressure.
: 1. SummerTech
G2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits (2.5/3.7).
: 1. Summer Technical     nical Specification Bases Bases 3/4.7.1.1, 3/4.7.1.1, 3/4.7.1.5, 3/4.7.1.5, 3/4.7.1.6, 3/4.7.1.6, 3/4.7.2 3/4.7.2 KJA CATALOGU K/A    CATALOGUE       E QUESTION QUESTION DESCRIPTI DESCRIPTION:   ON:
Categories Tier: Group: 2 KeyWord: S/G OVERPRESSURE Cog Level: M2.5/3.7 Source: N Exam: SM05301 Test: S AuthorlReviewer:
      - W/E      13
FJE/SDR Final Submittal (Slue Paper) FINAL SRO WRITTEN EXAMINATION 2/9/06
      - W/E 13 Steam Steam Generator Generator Over-pressur Over-pressure. e.
: 76. 002A2.04 001 VC Summer Nuclear Plant 2005-301 SRO Inital Exam A large LOCA has occurred.
G2.2.25 G2.2.25 Knowledge Knowledge of      of bases bases inin technical technical specification specifications s for for limiting limiting conditions conditions for for operations operations and    safety    limits  (2.5/3.7).
Which ONE of the following actions are corrrect given the following conditions:
and safety limits (2.5/3.7).
RWST level is 17% and continues to decrease.
Categories Categories Tier:
RHR sump level is 410 feet and increasing.
Tier:                   1                                          Group:
All RCPs were tripped (by procedure) when RCS pressure dropped below 1400 psig The crew is currently performing the actions of EOP-2.0, LOSS OF REACTOR OR SECONDARY COOLANT The following EOPs are being considered:
Group:                  22 Key  Word:
EOP-2.2, TRANSFER TO COLD LEG RECIRCULATION EOP-2.4, LOSS OF EMERGENCY COOLANT RECIRCULATION Transition to: A. EOP-2.4 from EOP-2.0. When RHR sump level reaches the required level, transition to EOP-2.2. B. EOP-2.4 from EOP-2.0. When RHR sump level reaches the required level, return to EOP-2.0 and transition to EOP-2.2. C. EOP-2.2 from EOP-2.0 then transition to EOP-2.4. When RHR sump level reaches the required level, return to EOP-2.0 and transition to EOP-2.2. D ..... EOP-2.2 from EOP-2.0 then transition to EOP-2.4. When RHR sump level reaches the required level, transition back to EOP-2.2.
KeyWord:               S/G S/G OVERPRES OVERPRESSURE SURE                    Cog Cog Level:
: 77. 003A2.03 002 The following conditions exist: -Reactor Power is 9%. VC Summer Nuclear Plant 2005-301 SRO Inital Exam -A Total Loss of All Service Water has occurred.  
Level:             M2.5/3.7 M2.5/3.7 Source:
-AOP-117.1, "Total Loss of Service Water," has been entered. -RCP temperatures are beginning to rise. -Service Water can not be restored.
Source:                NN                                          Exam:
Exam:                   SM05301 SM05301 Test:
Test:                  SS                                          Author/Revi AuthorlReviewer:
ewer:      FJE/SDR FJE/SDR
 
Final Submittal (Btue Paper)
(Slue FINAL SRO WRITTEN EXAMINATION 2/9/06
 
VC Summer Nuclear Plant 2005-301 SRO Inital Exam
: 76. 002A2.04 001 A large LOCA has occurred. Which ONE of the following actions are corrrect given the following conditions:
* RWST level is 17% and continues to decrease.
* RHR sump level is 410 feet and increasing.
* All RCPs were tripped (by procedure) when RCS pressure dropped below 1400 psig
* The crew is currently performing the actions of EOP-2.0, LOSS OF REACTOR OR SECONDARY COOLANT The following EOPs are being considered:
* EOP-2.2, TRANSFER TO COLD LEG RECIRCULATION
* EOP-2.4, LOSS OF EMERGENCY COOLANT RECIRCULATION Transition to:
A.     EOP-2.4 from EOP-2.0. When RHR sump level reaches the required level, transition to EOP-2.2.
B. EOP-2.4 from EOP-2.0. When RHR sump level reaches the required level, return to EOP-2.0 and transition to EOP-2.2.
C. EOP-2.2 from EOP-2.0 then transition to EOP-2.4. When RHR sump level reaches the required level, return to EOP-2.0 and transition to EOP-2.2.
D9 D ..... EOP-2.2 from EOP-2.0 then transition to EOP-2.4. When RHR sump level reaches the required level, transition back to EOP-2.2.
 
Summer Nuclear VC Summer      Nuclear Plant Plant 2005-301 SRO SRO Inital Inital Exam Exam
: 77. 003A2.03
: 77. 003A2.03 002002 The following conditions The                conditions exist:
exist:
        - Reactor Power is 9%.
        - A Total Loss of All Service Water has occurred.
Total Loss of Service Water,"
        - AOP-117.1, "Total
        -                                        Water, has been entered.
        - RCP temperatures are beginning to rise.
        - Service Water can not be restored.
Which ONE of the following describes the action(s) the operators must take and the sequence of those actions (in accordance with AOP-117.1)?
Which ONE of the following describes the action(s) the operators must take and the sequence of those actions (in accordance with AOP-117.1)?
A.>I Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1 -DESCENDING).
A. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 11 -
Stop up to TWO RCPs. Isolate unnecessary CCW loads, and ensure FS is aligned to the DIGs. When an RCP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, stop the affected RCP. B. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1 -DESCENDING).
A.>I                                                                                      -
Isolate unnecessary CCW loads, and ensure FS is aligned to the DIGs. Secure an RCP only if motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit. C. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1 -DESCENDING).
DESCEND ING). Stop up to TWO RCPs. Isolate unnecessary CCW DESCENDING).                                                        COW loads, and ensure FS D/Gs. When an RCP motor bearing temperatures or lower seal water is aligned to the DIGs.
Stop at least TWO RCPs. Isolate unnecessary CCW loads, and ensure FS is aligned to the DIGs. When the running RCP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, increase monitoring and continue pump operation until the unit is shutdown then stop the affected pump. D. Stop ONE RCP. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1 -DESCENDING).
bearing temperature exceeds the specified limit, stop the affected RCP.
When an RCP motor bearing temperatures or lower seal : water bearing temperature exceeds the specified limit, trip the reactor and stop the affected!
B. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1                1 -
RCP.
DESCENDING). Isolate unnecessary CCW       COW loads, and ensure FS is aligned to the DIGs.
: 78. 005G2.1.27 001 VC Summer Nuclear Plant 2005-301 SRO Inital Exam Which ONE of the following correctly describes the purpose and or function (not all inclusive) of the RHR system and one of its Mode 4 Technical Specification requirements?
Secure an RCP only if motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit.
A. Hot Leg Recirculation, Refueling Cavity Cooling, Alternate Water supply to Reactor Building' Coolers, Pressurizer Relief Tank Cooling. RHR can be deenergized for up to 2 hour provided that core outlet temperature is maintained at least 50&deg;F below saturation temperature.
C. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1                1 -
B. Cold Leg Recirculation, Hot Leg Recirculation, Simultaneous Cold Leg -Hot Leg Recirculation, Alternate Water supply to Reactor Building Coolers. RHR can be deenergized for up to 1 hour provided that core outlet temperature is maintained at least 100F below saturation temperature.
DESCENDING). Stop at least TWO RCPs. Isolate unnecessary CCW         COW loads, and ensure D/Gs. When the running RCP FS is aligned to the DIGs.                         ROP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, increase monitoring and continue pump operation until the unit is shutdown then stop the affected pump.
C. Refueling Cavity Draining, Cold Overpressure Protection, Simultaneous Cold Leg -Hot Leg Recirculation, Pressurizer Relief Tank Cooling. RHR can be deenergized for up to 2 hour provided that core outlet temperature is maintained at least 500F below saturation temperature. Cold Leg Recirculation, Refueling Cavity Draining, Cold Overpressure Protection, Cold Leg Injection.
D. Stop ONE RCP. Initiate a        a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1    1 - DESCENDING). When an RCP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, trip the reactor and stop the affected!
RHR can be deenergized for up to 1 hour provided that core outlet temperature is maintained at least 100F below saturation temperature.
affected RCP.
: 79. 007A2.03 002 Plant conditions are as follows: -The unit is in Cold Shutdown.
 
VC Summer Nuclear Plant 2005-301 SRO Inital Exam -The RCS is water solid with one train of RHR providing shutdown cooling: -RHR letdown is in service with PCV-145 controlling RCS pressure in AUTO. -ALL pressurizer PORV control switches are in AUTO. -RCS temperature is 140 of. -PRT level is 78%. -PRT pressure is 6 psig. -PRT temperature is 95 of Assuming no operator action, a
VC Summer VC Summer Nuclear Nuclear Plant Plant 2005-301  SRO Inital 2005-301 SRO     Inital Exam Exam
_____ will result in a pressure increase in the PRT and the crew can restore PRT parameters by ______ _ A. A HIGH failure of PT-444, pressurizer pressure control channel transmitter.
: 78. 005G2.1.27 005G2.1.27 001 001 Which ONE Which  ONE of of the the following correctly correctly describes describes the the purpose purpose and and or or function (not (not all all inclusive) inclusive) of the RHR system and one of its Mode 4 Technical Specification requirements?
Spraying down the PRT using reactor makeup water per SOP-1 01, Reactor Coolant System. B ...... Loss of air to HCV-142, LTDN FROM RHR. Draining the PRT to the Recycle Holdup Tanks per SOP-108, Liquid Waste Processing System. c. A HIGH failure of PT-444, pressurizer pressure control channel transmitter.
A. Hot Leg Recirculation, Refueling Cavity Cooling, Alternate Water supply to Reactor Building'   Building Coolers, Pressurizer Relief Tank Cooling. RHR can be deenergized for up to 2 hour provided that core outlet temperature is maintained at least 50&deg;F below saturation temperature.
Draining the PRT to the Recycle Holdup Tanks per SOP-108, Liquid Waste Processing System. D. Loss of air to HCV-142, LTDN FROM RHR. Spraying down the PRT using reactor makeup water per SOP-1 01, Reactor Coolant System.
B. Cold Leg Recirculation,     Hot Leg Recirculation, Simultaneous Cold Leg - Hot Leg Recirculation, Alternate   Water supply to Reactor Building Coolers. RHR can be deenergized for up to 11  hour provided that core outlet temperature is maintained at least 10&deg;F below saturation temperature.
: 80. 007EA2.01 002 VC Summer Nuclear Plant 2005-301 SRO Inital Exam At 50% power, the plant experienced a loss of BOTH running Main Feedwater Pumps with a concurrent failure of the Reactor trip breaker A to open. The crew is performing the immediate actions of EOP-1.0, "Reactor Trip/Safety Injection Actuation." Current plant conditions are as follows: -The Integrated Plant Computer System has failed. -SG LO-LO Level annunciators are lit. -Reactor Power is 7% and slowly decreasing.  
100F C. Refueling Cavity Draining, Cold Overpressure Protection, Simultaneous Cold Leg - Hot Leg   -
-All EFW Pumps failed to start. Which ONE of the following describes the procedure path based on the above information?
Recirculation, Pressurizer Relief Tank Cooling. RHR can be deenergized for up to 2 hour 50&deg;F below saturation provided that core outlet temperature is maintained at least 500F temperature.
A. Remain in EOP-1.0, until directed to monitor Critical Safety Functions then transition to EOP-15.0, "Response To Loss of Secondary Heat Sink." B. Directly enter EOP-15.0, "Response To Loss of Secondary Heat Sink." C. Remain in EOP-1.0, until directed to monitor Critical Safety Functions then transition to EOP-13.0, "Response To Abnormal Nuclear Power Generation." Dy Transition from EOP-1.0 to EOP-13.0, "Response To Abnormal Nuclear Power Generation. " 
D D~  Cold Leg Recirculation, Refueling Cavity Draining, Cold Overpressure Protection, Cold Leg Injection. RHR can be deenergized for up to 1    1 hour provided that core outlet temperature 10&deg;F below saturation temperature.
: 81. 008A2.04 002 c--------'--c--c--
is maintained at least 100F
------------------------VC Summer Nuclear Plant 2005-301 SRO Inital Exam The Unit is operating at 100% power with all systems in normal lineups when the following annunciators actuate: -L TDN/SL WTR HX FLO LO TEMP HI -CC LOOP A RM-L2A HI RAD -CC SRG TK VENT 7096 CLSD HI RAD -CCW SRG TK LVL HI/LO/LO-LO NO other annunciators are lit and all associated automatic functions have occurred.
 
Which ONE of the following is the correct cause and action? A. A leak exists in the Letdown HX; verify closure of PVT-8152, L TON LINE ISOL, per SOP-102, CHEMICAL AND VOLUME CONTROL SYSTEM, and manually shut PVV-7096, CC SURGE TK VLV B ..... A leak exists in the Letdown HX; manually close PVT-8152, L TON LINE ISOL, per SOP-102, CHEMICAL AND VOLUME CONTROL SYSTEM, and verify closure of PVV-7096, CC SURGE TK VLV C. RCP "A" thermal barrier has been breached.
Summer Nuclear VC Summer     Nuclear Plant Plant 2005-301   SRO Inital 2005-301 SRO    Inital Exam Exam
Conduct a normal shutdown per GOP-4B, POWER OPERATION (MODE 1 -DESCENDING), Stop RCP A within 8 hours per SOP-1 01, REACTOR COOLANT SYSTEM. D. A Phase "B" Containment Isolation has actuated due to RM-L2A&B (Component Cooling) alarming.
: 79. 007A2.03
Immediately trip the reactor and trip ALL RCPs and enter EOP 1.0. 
: 79. 007A2.03 002  002 Plant conditions are Plant                  are as as follows:
: 82. 009EG2.4.30 002 VC Summer Nuclear Plant 2005-301 SRO Inital Exam Which ONE of the following identifies an event that is required to be reported to the NRC within 1 hour per EPP-002, COMMUNICATION AND NOTIFICATION.
    - The unit is in Cold Shutdown.
A. An unplanned ECCS initiation that does not discharge to the RCS during an SI surveillance test. B ..... An ECCS discharge to the RCS in response to a small break LOCA. C. An airborne release of> 2X Appendix B limits. D. A liquid release of > 2X Appendix B limits.
    - The RCS is water solid with one train of RHR providing shutdown cooling:
: 83. 022AG2.4.49 001 VC Summer Nuclear Plant 2005-301 SRO Inital Exam The plant was operating at 80% power when the following annunciators (not all inclusive) came in: REGEN HX L TDN OUT TEMP HI VCT LVL HI/LO CHG LINE FLO HIILO PZR LCS DEV HI/LO Charging pump amps are fluctuating between 25 and 30 amps Charging flow is fluctuating between 25 and 30 gpm Charging pre,ssure is oscillating between 2500 and 2600 psig Which ONE of the following set of actions should the supervisor direct his board operators to perform (These actions are not all inclusive)?
    - RHR letdown is in service with PCV-145 controlling RCS pressure in AUTO.
A.>I Secure the operating charging pump, close all letdown isolation valves, and close FCV-122, charging flow control valve. B. Verify at least one charging pump is operating, verify FCV-122 is open, and verify CCW flow to the RCP Thermal Barriers is GREATER THAN 90 gpm on FI-7273A(B), THERM BARR FLOW GPM. C. Secure the operating charging pump, realign charging pump suction, and close both LCV-115B(D), RWST TO CHG PP SUCT. D. Verify at least one charging pump is operating, verify FCV-122 is open, and open both LCV-115C(E), VCT OUTLET ISOL.
    - ALL pressurizer PORV control switches are in AUTO.
: 84. 032AA2.08 003 VC Summer Nuclear Plant 2005-301 SRO Inital Exam Refueling operations are in progress, with SR monitor N33 out of service, when power is suddenly lost to source range neutron flux monitor N31 and subsequently regained 30 minutes j later. Which ONE of the following describes the action to be taken for this situation when power is lost? A>o/ Suspend all core alterations and perform an analog channel operational test of source range neutron flux monitor N31 within 8 hours prior to the initial start of core alterations.
    - RCS temperature is 140 of.
    -                                &deg;F.
    -    PRT  level is 78%.
    - PRT pressure is 6 psig.
    - PRT temperature is 95 of
    -                             &deg;F Assuming no operator action, a _____ will result in a pressure increase in the PRT and the crew can restore PRT parameters by _ _ _ _ _ __
A. A HIGH failure of PT-444, pressurizer pressure control channel transmitter.
Spraying down the PRT using reactor makeup water per SOP-1 SOP-i 01, Reactor Coolant System.
B.
B . . . Loss of air to HCV-142, LTDN FROM RHR.
SOP-i 08, Liquid Waste Processing Draining the PRT to the Recycle Holdup Tanks per SOP-108, System.
c.
C. A HIGH failure of PT-444, pressurizer pressure control channel transmitter.
Draining the PRT to the Recycle Holdup Tanks per SOP-108, SOP-i 08, Liquid Waste Processing System.
HCV-i42, LTDN FROM RHR.
D. Loss of air to HCV-142, Spraying down the PRT using reactor makeup water per SOP-1 SOP-i 01, Reactor Coolant System.
 
VC Summer Summer Nuclear PlantPlant Inital Exam 2005-301 SRO Inital      Exam
: 80. 007EA2.01 002
: 80. 007EA2.01 At 50% power, the plant experienced a loss of BOTH runningrunning Main Main Feedwater Pumps Pumps with aa concurrent failure of the Reactor trip breaker A to open. The crew is performing the immediate FOP-i .0, "Reactor actions of EOP-1.0,   Reactor Trip/Safety Injection Actuation."
Actuation.
Current plant conditions are as follows:
        - The Integrated Plant Computer System has failed.
      - SG LO-LO Level annunciators are lit.
      - Reactor Power is 7% and slowly decreasing.
FFW Pumps failed to start.
      - All EFW Which ONE of the following describes the procedure path based on the above information?
A.              FOP-i .0, until directed to monitor Critical Safety Functions then transition to Remain in EOP-1.0, EOP-15.0,  Response To Loss of Secondary Heat Sink."
FOP-i 5.0, "Response                                  Sink.
FOP-i5.0, "Response B. Directly enter EOP-15.0,    Response To Loss of Secondary Heat Sink."
Sink.
FOP-i .0, until directed to monitor Critical Safety Functions then transition to C. Remain in EOP-1.0, EOP-13.0,  Response To Abnormal Nuclear Power Generation."
FOP-i 3.0, "Response                                    Generation.
D Transition from EOP-1.0 Dy                                FOP-i 3.0, "Response FOP-i .0 to EOP-13.0,    Response To Abnormal Nuclear Power Generation."
Generation.
 
VC Summer VC    Summer Nuclear Nuclear Plant Plant 2005-301 SRO 2005-301     SRO Inital Inital Exam Exam
: 81. 008A2.04 81.
c--------'--c--c--
008A2.04 002 002 The Unit  Unit is is operating operating at      at 100%
100% power power with all all systems in in normal normal lineups lineups when the following annunciators actuate:
                          - LLTDN/SL
                          -  TDN/SL WTR HX FLO LO              [0 TEMP HI
                          - CC LOOP A RM-L2A HI RAD
                          - CC SRG TK VENT 7096 CLSD HI RAD
                          - CCW SRG TK LVL HI/LO/LO-LO NO other annunciators are lit and all associated automatic functions have occurred.
Which ONE of the following is the correct cause and action?
A.     A leak exists in the Letdown HX; verify closure of PVT-8152, LLTDN          TON LINE ISOL, per SOP-i 02, CHEMICAL AND VOLUME CONTROL SYSTEM, and manually shut PVV-7096, SOP-102, CCSURGETKVLV CC SURGE TK VLV BB.
                    ..... A leak exists in the Letdown HX; manually close PVT-8152,     PVT-8i52, LLTDN TON LINE ISOL, per SOP-i 02, CHEMICAL AND VOLUME CONTROL SYSTEM, and verify closure of SOP-102, PVV-7096, CC SURGE TK VLV C. RCP "A"     A thermal barrier has been breached. Conduct a normal shutdown per GOP-4B, POWER OPERATION (MODE 1                  1 - DESCENDING), Stop RCP A within 8 hours per SOP-lOi, SOP-1   01, REACTOR COOLANT SYSTEM.
D. A Phase "B"        B Containment Isolation has actuated due to RM-L2A&B (Component Cooling) alarming. Immediately trip the reactor and trip ALL RCPs and enter EOP 1.0.
 
VC Summer VC    Summer Nuclear Nuclear Plant Plant 2005-301 SRO 2005-301    SRO Inital InitaJ Exam Exam
: 82. 009EG2.4.30
: 82. 009EG2.4.30 002002 Which ONE  ONE of the following identifies identifies an event that is is required required to be be reported reported toto the NRC NRC within 11 hour per EPP-002, COMMUNICATION AND NOTIFICATION.
A. An unplanned ECCS initiation that does not discharge to the RCS during an SI surveillance test.
B.%
B ..... An ECCS discharge to the RCS in response to a small break LOCA.
C. An airborne release of> 2X Appendix B limits.
D. A liquid release of  of>> 2X Appendix B limits.
 
VC Summer Nuclear Plant 2005-301 SRO Inital Exam
: 83. 022AG2.4.49 001 The plant was operating at 80% power when the following annunciators (not all inclusive) came in:
          -  REGEN HX L   LTDN TDN OUT TEMP HI
          -  VCT LVL HI/LO
          -    CHG LINE FLO HIILO Hl!LO
          -          LOS DEV HI/LO PZR LCS        Hl!LO Charging pump amps are fluctuating between 25 and 30 amps Charging flow is fluctuating between 25 and 30 gpm pressure is oscillating between 2500 and 2600 psig Charging pre,ssure Which ONE of the following set of actions should the supervisor direct his board operators to perform (These actions are not all inclusive)?
A.
A.>I Secure the operating charging pump, close all letdown isolation valves, and close FCV-122, charging flow control valve.
B. Verify at least one charging pump is operating, verify FCV-122 is open, and verify CCW COW flow to the RCP Thermal Barriers is GREATER THAN 90 gpm on FI-7273A(B),
Fl-7273A(B), THERM BARR FLOW GPM.
C. Secure the operating charging pump, realign charging pump suction, and close both LCV-115B(D),
LCV-1 1 5B(D), RWST TO CHG PP SUCT.
D. Verify at least one charging pump is operating, verify FCV-122 is open, and open both LCV-1 150(E), VCT OUTLET ISOL.
LCV-115C(E),
 
VC Summer VC  Summer Nuclear Nuclear Plant Plant 2005-301 2005-301 SRO SRO Inital Inital Exam Exam
: 84. 032AA2.08
: 84. 032AA2.08 003003 Refueling operations Refueling               are in operations are in progress, progress, with SR SR monitor monitor N33 N33 out out of of service, service, when power power is is suddenly lost to source range neutron flux monitor N31 and subsequently regained 30 minutes           j later.
Which ONE of the following describes the action to be taken for this situation when power is lost?
A. Suspend all core alterations and perform an analog channel operational test of source A>o/
range neutron flux monitor N31 within 8 hours prior to the initial start of core alterations.
B. Suspend all core alterations and perform a neutron flux response time test AND operational test of source range neutron flux detector N31 within 8 hours prior to the initial start of core alterations.
B. Suspend all core alterations and perform a neutron flux response time test AND operational test of source range neutron flux detector N31 within 8 hours prior to the initial start of core alterations.
C. Determine boron concentration and perform a channel check of source range neutron flux monitor N31 within 12 hours. D. Determine boron concentration and perform a neutron flux response time test of source range neutron flux detector N31 within 12 hours.
C. Determine boron concentration and perform a channel check of source range neutron flux monitor N31 within 12 hours.
: 85. 035G2.4.20 002 VC Summer Nuclear Plant 2005-301 SRO Inital Exam The crew has just entered EOP-15.0, "Response to Loss of Secondary Heat Sink" from EOP-12.0, Monitoring of Critical Safety Functions.
D. Determine boron concentration and perform a neutron flux response time test of source range neutron flux detector N31 within 12 hours.
The following conditions exist: -WR SG "A" level is 25% -WR SG "8" level is 12% -WR SG "c" level is 11% -Total Feed Flow is 290 gpm Which ONE of the following sets of actions (not all inclusive) should be taken as directed by EOP-15.0, "Response to Loss of Secondary Heat Sink"? A. Ensure all EFW valves are open and establish EFW flow to at least one SG. B. Reset SI and establish MFW flow to either the "8" or "c" Steam Generators.
 
C. Reset SI, dump steam to the condenser and feed using a condensate pump. D ..... Trip ALL RCPs, actuate SI, establish an RCS bleed path:
VC Summer Nuclear Plant 2005-301 SRO Inital Exam
The following conditions exist: -A plant startup was in progress.  
: 85. 035G2.4.20 002 The crew has just entered EOP-15.0, "Response Response to Loss of Secondary Heat Sink" Sink from EOP-12.0, Monitoring of Critical Safety Functions.
-Power level was at 38% -The reactor tripped VC Summer Nuclear Plant 2005-301 SRO Inital Exam -SG blowdown isolation valves (PVG-503A(B)(C), A(B)(C) ISOL) closed -Current SG narrow range levels in "A", "B", and "C" SGs are 8%, 10%, and 10%, respectively, and decreasing Which ONE of the following correctly states the initiating event that caused the trip and the expected automatic actions based on these conditions?
The following conditions exist:
A. The operating MFP tripped and ONLY the motor driven EFW pumps have a current start signal. B ..... The operating MFP tripped and BOTH the turbine driven AND motor driven EFW pumps have a current start signal. C. All SG flow control valves drifted closed and AMSAC should have actuated.
                - WR SG "A"
D. All SG flow control valves drifted closed and ONLY the turbine driven EFW pump has a current start signal.
                -        A level is 25%
: 87. 068G2.1.20 002 A Liquid Radwaste Release is been in progress:
                - WR SG "8"
VC Summer Nuclear Plant 2005-301 SRO Inital Exam -XCP-646 2-5, MON TK DISCH RM-L5 HI RAD, has just actuated for the second time. -RCV00018-WL, Liquid Radioactive Waste Control Valve, indicates shut. -Within 30 seconds of the alarm, RM-L5's reading returns to below the setpoint.
                -        B level is 12%
Which ONE of the following correctly states the next procedure steps to be taken. A. .... The tank must be sampled and activity levels verified, then open RCV00018-WL and resume the release per SOP-1 08. B. Verify that the RM-L5's reading is below the setpoint, then open RCV00018-WL and resume the release per SOP-1 08. c. Verify that the RM-L5's reading is below the setpoint, then open RCV00018-WL and resume the release per SOP-1 08. Direct Heath Physics to continue to monitor the release and reduce the release rate. D. Notify Health Physics and request a radiological survey. The release can not be reinitiated under the current release permit.
                - WR SG "c"
Plant conditions are as follows: VC Summer Nuclear Plant 2005-301 SRO Inital Exam -The unit is currently in MODE 4, with temperature and pressure increasing.  
                -        C level is 11%
-All major work inside containment was completed two hours ago and there are NO personnel inside the Reactor Building.  
                - Total Feed Flow is 290 gpm Which ONE of the following sets of actions (not all inclusive) should be taken as directed by EOP-1 5.0, "Response EOP-15.0,       Response to Loss of Secondary Heat Sink"?
-An auxiliary operator has just called to report that the red indicating light above the Personnel Escape Airlock is LIT and that he was unable to operate the Fuel Handling Building door using the handwheel.
Sink?
A. Ensure all EFW valves are open and establish EFW flow to at least one SG.
B. Reset SI and establish MFW flow to either the "8" B or "c" C Steam Generators.
C. Reset SI, dump steam to the condenser and feed using a condensate pump.
D..... Trip ALL RCPs, actuate SI, establish an RCS bleed path:
D
 
VC Summer Summer Nuclear Nuclear Plant Plant 2005-301 2005-301 SRO SRO Inital Inital Exam Exam
: 86. 054AA2.03 002 following conditions The following       conditions exist:
                - A plant startup was in progress.
                - Power level was at 38%
                - The reactor tripped
                - SG blowdown isolation valves (PVG-503A(B)(C), A(B)(C) ISOL)
                -                                                          SQL) closed A, "B",
                - Current SG narrow range levels in "A",
                -                                        B, and "C" C SGs are 8%, 10%, and 10%, respectively, and decreasing Which ONE of the following correctly states the initiating event that caused the trip and the expected automatic actions based on these conditions?
A. The operating MFP tripped and ONLY the motor driven EFW pumps have a current start signal.
B.v B ..... The operating MFP tripped and BOTH the turbine driven AND motor driven EFW pumps have a current start signal.
C. All SG flow control valves drifted closed and AMSAC should have actuated.
D. All SG flow control valves drifted closed and ONLY the turbine driven EFW pump has a    a current start signal.
 
VC Summer Nuclear Plant 2005-301 SRO Inital Inital Exam
: 87. 068G2.1.20 002002 A Liquid Radwaste Release is been in progress:
          - XCP-646 2-5, MON TK DISCH RM-L5 HI RAD, has just actuated for the second time.
RCV00018-WL, Liquid Radioactive Waste Control Valve, indicates shut.
          - Within 30 seconds of the alarm, alarm RM-L5's
                                            , RM-L5s reading returns to below the setpoint.
Which ONE of the following correctly states the next procedure steps to be taken.
A.
A..... The tank must be sampled and activity levels verified, then open RCV00018-WL and resume the release per SOP-1 SOP-i 08.
RM-L5s reading is below the setpoint, then open RCV00018-WL B. Verify that the RM-L5's                                              RCV000i8-WL and SOP-i 08.
resume the release per SOP-1
: c.                   RM-L5s reading is below the setpoint, then open RCV00018-WL and C. Verify that the RM-L5's SOP-i08.
resume the release per SOP-1   08. Direct Heath Physics to continue to monitor the release and reduce the release rate.
D. Notify Health Physics and request a radiological survey. The release can not be reinitiated under the current release permit.
 
VC Summer Nuclear Plant 2005-301 SRO Inital Exam
: 88. 103G2.1.30 002 Plant conditions are as follows:
          - The unit is currently in MODE 4, with temperature and pressure increasing.
          - All major work inside containment was completed two hours ago and there are NO personnel inside the Reactor Building.
        - An auxiliary operator has just called to report that the red indicating light above the Personnel Escape Airlock is LIT and that he was unable to operate the Fuel Handling Building door using the handwheel.
Which ONE of the following is correct regarding the status of the Personnel Escape Airlock AND Containment Integrity?
Which ONE of the following is correct regarding the status of the Personnel Escape Airlock AND Containment Integrity?
A.<I The Reactor Building door is OPEN. The Personnel Escape Airlock is INOPERABLE.
A.<I The Reactor Building door is OPEN.
B. The Reactor Building door is CLOSED. The Personnel Escape Airlock is INOPERABLE.
A.
The Personnel Escape Airlock is INOPERABLE.
B. The Reactor Building door is CLOSED.
The Personnel Escape Airlock is INOPERABLE.
C. Only the Reactor Building door position indicator has malfunctioned.
C. Only the Reactor Building door position indicator has malfunctioned.
The Personnel Escape Airlock is OPERABLE.
The Personnel Escape Airlock is OPERABLE.
D. The Personnel Escape Airlock is OPERABLE.
D. The Personnel Escape Airlock is OPERABLE.
The Personnel Escape Airlock door interlock is INOPERABLE.
The Personnel Escape Airlock door interlock is INOPERABLE.
: 89. G2.1.13 002 VC Summer Nuclear Plant 2005-301 SRO Inital Exam Which ONE of the following (as stated in SAP-200, Conduct of Operations) has the final authority, per Management Directive 11, for a case where an individual's condition for work inside the protected area is in question?
 
A. General Manager, Nuclear Plant Operations B ..... Shift Supervisor  
VC Summer Nuclear Plant 2005-301 SRO Inital Exam
: c. Management Duty Supervisor D. Security Manager
: 89. G2.1.13 002 Which ONE of the following (as stated in SAP-200, Conduct of Operations) has the final authority, per Management Directive 11, for a case where an individual's individuals condition for work inside the protected     area is in question?
: 90. G2.1.34 002 VC Summer Nuclear Plant 2005-301 SRO Inital Exam The unit is undergoing a normal heatup. Plant conditions are as follows: -Hydrazine was added when RCS temperature was 185&deg;F. -RCS temperature is 200&deg;F. -A reactor coolant sample shows dissolved oxygen concentrations of 1.1 ppm. Given the above conditions and in accordance with GOP-2,"Plant Startup and Heatup," and Tech Spec 3.4.7, "Chemistry," which ONE of the following is correct? A. Secure the Heatup, plant chemistry is NOT in compliance with GOP-2; an LCO HAS been entered. B ..... Secure the Heatup to prevent plant chemistry from NOT being in compliance with GOP-2; an LCO has NOT been entered. C. The heatup can continue, plant chemistry IS in compliance with GOP-2; an LCO HAS been i entered. D. The heatup can continue, plant chemistry IS in compliance with GOP-2; an LCO has NOT been entered.
A. General Manager, Nuclear Plant Operations B ..... Shift Supervisor B.
: 91. G2.2.20 001 VC Summer Nuclear Plant 2005-301 SRO Inital Exam Which ONE of the following is a VIOLATION of administrative procedures when troubleshooting an INOPERABLE system or component, the condition of which is specified by a Technical Specification Action Statement.
c.
A.o.I A Temporary Restoration to Service is used even though an alternative method of completing the work that will meet the action statement requirement was identified.
C. Management Duty Supervisor D. Security Manager
 
VC Summer Nuclear Plant 2005-301 SRO Inital Exam
: 90. G2.1.34 002 The unit is undergoing a normal heatup. Plant conditions are as follows:
          - Hydrazine was added when RCS temperature was 185&deg;F.
200&deg; F.
          - RCS temperature is 200&deg;F.
          - A reactor coolant sample shows dissolved oxygen concentrations of 1.1 ppm.
Given the above conditions and in accordance with GOP-2,"Plant GOP-2,Plant Startup and Heatup,"
Heatup, and Chemistry, which ONE of the following is correct?
Tech Spec 3.4.7, "Chemistry,"
A. Secure the Heatup, plant chemistry is NOT in compliance with GOP-2; an LCO HAS been entered.
B.
B..... Secure the Heatup to prevent plant chemistry from NOT being in compliance with GOP-2; an LCO has NOT been entered.
C. The heatup can continue, plant chemistry IS in compliance with GOP-2; an LCO HAS been     i entered.
D. The heatup can continue, plant chemistry IS in compliance with GOP-2; an LCO has NOT been entered.
 
VC Summer Summer Nuclear Nuclear Plant Plant 2005-301 SRO 2005-301   SRO Inital Inital Exam Exam
: 91. G2.2.20
: 91. G2.2.20 001 001 Which ONE ONE of of the following is is aa VIOLATION of administrative administrative procedures procedures when troubleshooting an INOPERABLE system or component, the condition of which is specified by a Technical Specification Action Statement.
A. A Temporary Restoration to Service is used even though an alternative method of A.o.I completing the work that will meet the action statement requirement was identified.
B. The troubleshooting requires posting a plant operator to immediately restore an affected component.
B. The troubleshooting requires posting a plant operator to immediately restore an affected component.
C. The Temporary Inoperable Status Change required to perform the troubleshooting was approved by the Duty Shift Supervisor.
C. The Temporary Inoperable Status Change required to perform the troubleshooting was approved by the Duty Shift Supervisor.
D. The Work Document also includes an approved Bypass Authorization Request to install electrical jumpers.
D. The Work Document also includes an approved Bypass Authorization Request to install electrical jumpers.
: 92. G2.2.7 001 VC Summer Nuclear Plant 2005-301 SRO Inital Exam A bypass authorization request, prepared per SAP-148, "Temporary Bypass, Jumper, and Lifted Lead Control," requires prior PSRC and NSRC review for which ONE of the following conditions?
 
VC Summer Nuclear Plant 2005-301 SRO Inital Exam
: 92. G2.2.7 001 A bypass authorization request, prepared per SAP-148, "Temporary Temporary Bypass, Jumper, and Control, requires prior PSRC and NSRC review for which ONE of the following Lifted Lead Control,"
conditions?
A. A review indicates that system operability will be affected.
A. A review indicates that system operability will be affected.
B. A review indicates that 10 CFR 50 Appendix R fire protection criteria are impacted.
B. A review indicates that 10 CFR 50 Appendix R fire protection criteria are impacted.
C. A review indicates that Seismic or blowout provisions are being diminished.
C. A review indicates that Seismic or blowout provisions are being diminished.
D!&#xa5;'" A review indicates that a full safety evaluation is required per 10 CFR 50.59.
D A review indicates that a full safety evaluation is required per 10 CFR 50.59.
: 93. G2.3.2 002 VC Summer Nuclear Plant 2005-301 SRO Inital Exam Which ONE of the following is correct per HPP-709, Sampling and Release of Radioactive Gaseous Effluents:
D!&#xa5;'"
A>oI Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should be avoided when the wind is from the East-Southeast.
 
This will prevent the released activity from being drawn into the Auxiliary Building ventilation.
VC Summer VC  Summer Nuclear Nuclear Plant Plant 2005-301 SRO SRO Inital Inital Exam Exam
B. Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should: be avoided when the wind is from the West-Southwest. This will prevent the released activity from being drawn into the Auxiliary Building ventilation.
: 93. G2.3.2
C. Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should be avoided when the wind is from the East-Southeast.
: 93. G2.3.2 002 002 Which ONEONE of                  is correct of the following is correct per per HPP-HPP- 709, 709, Sampling Sampling and and Release Release ofof Radioactive Radioactive Gaseous Effluents:
This will prevent the released activity from being drawn into the Control Building ventilation.
A.. Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should A>oI be avoided when the wind is from the East-Southeast. This will prevent the released activity from being drawn into the Auxiliary Building ventilation.
D. Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should be avoided when the wind is from the West-Southwest.
B. Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should:     should be avoided when the wind is from the West-Southwest. This will prevent the released activity from being drawn into the Auxiliary Building ventilation.
This will prevent the released activity from being drawn into the Control Building ventilation.
C. Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should be avoided when the wind is from the East-Southeast. This will prevent the released activity from being drawn into the Control Building ventilation.
: 94. G2.4.33 002 VC Summer Nuclear Plant 2005-301 SRO Inital Exam Which ONE of the following individual's approval is required to extend the time that an invalid nuisance annunciator is removed from service past 96 hours? A. Duty Shift Engineeer B. Duty Shift Supervisor Cy Manager, Operations D. General Manager, Nuclear Plant Operations
D. Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should be avoided when the wind is from the West-Southwest. This will prevent the released activity from being drawn into the Control Building ventilation.
: 95. G2.4.38 002 Plant conditions are as follows: VC Summer Nuclear Plant 2005-301 SRO Inital Exam An event has occurred resulting in substantial core degradation with potential loss of containment integrity.
 
A General Emergency has been declared.
VC Summer Summer Nuclear Nuclear Plant Plant 2005-301 SROSRO Inital Inital Exam Exam
The prevailing wind is blowing from the south. Which ONE of the following must assume the duties of Interim Emergency Director, and to which area should he direct non-essential personnel be evacuated?
: 94. G2.4.33
A. Shift Supervisor; Evacuate to their personal residence.
: 94. G2.4 33 002 002 ONE of Which ONE  of the following individual's individuals approval is is required required to extend the the time that an an invalid invalid nuisance annunciator is removed from service past 96 hours?
B ..... Shift Supervisor; Evacuate to the Southern Offsite Holding Area. C. Manager, Operations; Evacuate to their personal residence.
A. Duty Shift Engineeer B. Duty Shift Supervisor C Manager, Operations Cy D. General Manager, Nuclear Plant Operations
D. Manager, Operations:
 
Evacuate to the Southern Offsite Holding Area.
VC Summer Nuclear Plant 2005-301 SRO Inital Exam
: 96. W/E02EG2.4.6 001 Plant conditions are as follows: VC Summer Nuclear Plant 2005-301 SRO Inital Exam -A reactor trip and SI have occurred due to a steam break. -ALL Main Steam Isolation Valves initially failed to close. -EOP-3.1, Uncontrolled Depressurization of All Steam Generators, is in progress at Step 17, Establish Normal Charging.  
: 95. G2.4.38 002 Plant conditions are as follows:
-PZR level is 58%. -EFW flowrate is 50 gpm to each Steam Generator due to required operator action. -All Steam Generator Narrow Range levels are 4%. -Reactor Building pressure has remained below 1 psig. -RCS pressure is 1750 psig and going UP. -Core Exit TCs are 435 of and going DOWN. The "C" Main Steam Isolation Valve closed 30 seconds ago and "C" Steam Generator pressure has changed from 80 to 130 psig. Which ONE of the following correctly describes the actions the crew should take? A. Must remain in EOP-3.1 until the Critical Safety Function Status Trees direct entering an orange or red path Emergency Operating Procedure.
* An event has occurred resulting in substantial core degradation with potential loss of containment integrity.
B. IMMEDIATELY transition to EOP-3.0, Faulted Steam Generator Isolation, Step 1. C ..... Complete EOP-3.1 through Step 20, verify SI Flow is NOT required, and then transition to EOP-3.0, Faulted Steam Generator Isolation, Step 1. D. Complete ALL steps of EOP-3.1 and then transition to EOP-1.2, Safety Injection Termination, Step 1.
* A General Emergency has been declared.
: 97. W/EOSEA2.1 001 VC Summer Nuclear Plant 2005-301 SRO Inital Exam The Crew has entered EOP-16.0 "Response to Pressurized Thermal Shock" due to an Orange path on the integrity CSF status tree. The Crew is at the step for Checking RCS Tcold I Stable or Increasing.
* The prevailing wind is blowing from the south.
While checking EFW flow it is determined that a Red path condition exists on the Heat Sink CSF status tree. Which ONE of the following correctly describes the action that should be taken by the crew? A. Remain in EOP-16.0 until it is completed, then transition to EOP-15.0, Response to Loss of I Secondary Heat Sink. B. Remain in EOP-16.0 until the Orange path is cleared, then tranistion to EOP-15.0.
Which ONE of the following must assume the duties of Interim Emergency Director, and to which area should he direct non-essential personnel be evacuated?
C."" IMMEDIATELY transition to EOP-15.0.
A.     Shift Supervisor; Evacuate to their personal residence.
D. The transition to EOP-15.0 is NOT required since EOP 16.0 provides actions for adjusting EFW.
B.%
: 98. W/E09EA2.2 001 VC Summer Nuclear Plant 2005-301 SRO Inital Exam A Reactor Trip with a loss of Off-site power has occurred.
B ..... Shift Supervisor; Evacuate to the Southern Offsite Holding Area.
Power will not be restored for at least eight hours, and a cooldown is desired. -RCS temperature is currently 557 of -Only one CRDM fan is operable.
C. Manager, Operations; Evacuate to their personal residence.
Which ONE of the following correctly describes the actions to be taken in accordance with EOP-1.3 "Natural Circulation Cooldown"?
D. Manager, Operations: Evacuate to the Southern Offsite Holding Area.
A. Reduce RCS pressure to below 1925 psig, maintain RCS subcooing greater than 80 of, cooldown shall not exceed 50 of/hr. B ..... Maintain RCS pressure above 1925 psig, maintain RCS subcooling greater than 130 of and cooldown shall not exceed 50 of/hr. C. Reduce RCS pressure to below 1925 psig, maintain RCS subcooing greater than 130 of, cooldown shall not exceed 25 of/hr. D. Maintain RCS pressure above 1925 psig, maintain RCS subcooling greater than 80 of and cooldown shall not exceed 25 of/hr.
 
: 99. W/E12EG2.4.4 002 Plant conditions are as follows: VC Summer Nuclear Plant 2005-301 SRO Inital Exam -The Unit experienced a Steam Generator Tube Rupture (SGTR) on the "8" Steam Generator (SG). -The crew is currently performing EOP-4.0, Steam Generator Tube Rupture, Step 3, Isolate flow from each RUPTURED SG. When the crew transitioned from EOP-1.0 to EOP-4.0, FOUR (4) minutes ago, plant parameters were as listed below: Loop A Loop 8 Loop C SG Pressure 800 psig 1200 psig 800 psig SG NR Level 40% 80% 45% SG PORV SHUT OPEN SHUT RCS Temperature 557 of 556 of 557 of RCS Pressure:
VC Summer Nuclear Nuclear Plant Plant 2005-301 SRO Inital Exam
1350 psig NOTE: ALL plant parameters were stable, with the exception of 8 SG NR Level, which was going UP. CURRENT plant parameters are as follows: SG Pressure SG NR Level SG PORV RCS Temperature RCS Pressure:
: 96. W/E02EG2.4.6 W/EO2EG2.4.6 001 001 Plant conditions are as follows:
1000 psig Loop A 500 psig 20% SHUT 520 of Loop 8 1050 psig 85% SHUT 550 of Loop C 750 psig 45% SHUT 550 of ALL above parameters are all decreasing (going DOWN), with Loop A parameters decreasing faster than Loops 8 and C. Which ONE of the following correctly describes the NEXT action the crew should take in accordance with Emergency Operating Procedures?
    - A reactor trip and SI have occurred due to a steam break.
A. IMMEDIATELY go to EOP-2.0, Loss of Reactor or Secondary Coolant. B ...... IMMEDIATELY go to EOP-3.0, Faulted Steam Generator Isolation.
    - ALL Main Steam Isolation Valves initially failed to close.
C. RETURN to EOP-4.0, Steam Generator Tube Rupture, Step 1. D. COMPLETE EOP-4.0, Step 3 and THEN go to EOP-3.0, Faulted Steam Generator Isolation.
    -   EOP-3. 1, Uncontrolled Depressurization of All Steam Generators, is in progress at Step 17,
100. W/E13EG2.2.2S 001 ------" --------------------VC Summer Nuclear Plant 2005-301 SRO Inital Exam Which ONE of the following describes the basis for reducing the Power Range Neutron Flux High Trip Setpoint, in accordance with Summer Technical Specification Table 3.7-1, if one or more main steam line code safety valves are inoperable for more than 4 hours? A.>oI To ensure that sufficient relieving capacity is available to limit secondary system pressure to within 110% of design pressure.
    - EOP-3.1,                                                                                    1 7, Establish Normal Charging.
    - PZR level is 58%.
    - EFW flowrate is 50 gpm to each Steam Generator due to required operator action.
    - All Steam Generator Narrow Range levels are 4%.
    - Reactor Building pressure has remained below 11 psig.
    - RCS pressure is 1750 psig and going UP.
    - Core Exit TCs are 435 of
    -                          &deg;F and going DOWN.
The "C" C Main Steam Isolation Valve closed 30 seconds ago and "C" C Steam Generator pressure has changed from 80 to 130 psig.
Which ONE of the following correctly describes the actions the crew should take?
A.     Must remain in EOP-3.1 until the Critical Safety Function Status Trees direct entering an orange or red path Emergency Operating Procedure.
B. IMMEDIATELY transition to EOP-3.0, Faulted Steam Generator Isolation, Step 1.
C..... Complete EOP-3.1 through Step 20, verify SI Flow is NOT required, and then transition to C
EOP-3.0, Faulted Steam Generator Isolation, Step 1.
D. Complete ALL steps of EOP-3.1 and then transition to EOP-1.2, Safety Injection Termination, Step 1.
 
VC Summer Summer Nuclear Nuclear Plant Plant 2005-301 SRO 2005-301    SRO Inital Inital Exam Exam
: 97. W/EOSEA2.1 W/EO5EA2.1 001 001 The Crew The  Crew has has entered EOP-16.0 "Response entered EOP-16.0  Response to Pressurized Pressurized Thermal Thermal Shock" Shock duedue to to an an Orange path on the integrity CSF status tree. The Crew is at the step for Checking RCS Tcold   I Stable or Increasing.
While checking EFW flow it is determined that a Red path condition exists on the Heat Sink CSF status tree.
Which ONE of the following correctly describes the action that should be taken by the crew?
A. Remain in EOP-16.0 until it is completed, then transition to EOP-15.0, Response to Loss of I Secondary Heat Sink.
B. Remain in EOP-16.0 until the Orange path is cleared, then tranistion to EOP-15.0.
EOP-1 5.0.
C9 IMMEDIATELY transition to EOP-15.0.
C.""
D. The transition to EOP-15.0 EOP-1 5.0 is NOT required since EOP 16.0 provides actions for adjusting EFW.
 
VC Summer Nuclear Plant 2005-301 SRO Inital lnital Exam
: 98. W/E09EA2.2 W/EO9EA2.2 001 A Reactor Trip with a loss of Off-site power has occurred. Power will not be restored for at least eight hours, and a cooldown is desired.
            - RCS temperature is currently 557 of
            -                                   &deg;F
            - Only one CRDM fan is operable.
Which ONE of the following correctly describes the actions to be taken in accordance with FOP-i .3 "Natural EOP-1.3       Natural Circulation Cooldown"?
Cooldown?
A.     Reduce RCS pressure to below 1925 psig, maintain RCS subcooing greater than 80   of, 80&deg;F, F/hr.
0 cooldown shall not exceed 50 of/hr.
By B ..... Maintain RCS pressure above 1925 psig, maintain RCS subcooling greater than 130 130&deg;Fof F/hr.
0 and cooldown shall not exceed 50 of/hr.
C. Reduce RCS pressure to below 1925 psig, maintain RCS subcooing greater than 130 &deg;F,    of, F!hr.
0 cooldown shall not exceed 25 of/hr.
D. Maintain RCS pressure above 1925 psig, maintain RCS subcooling greater than 80       of and 80&deg;F cooldown shall not exceed 25 of/hr.
                                          &deg;F/hr.
 
VC Summer Summer Nuclear Nuclear Plant Plant 2005-301 SROSRO Inital Inital Exam Exam
: 99. W/E12EG2.4.4 W/E12EG2.4.4 002  002 Plant conditions Plant    conditions are as as follows:
            - The Unit experienced a Steam Generator Tube Rupture (SGTR) on the "8" B Steam Generator (SG).
            - The crew is currently performing EOP-4.0, Steam Generator Tube Rupture, Step 3, Isolate flow from each RUPTURED SG.
When the crew transitioned from EOP-1.0 EOP-1 .0 to EOP-4.0, FOUR (4) minutes ago, plant parameters were as listed below:
Loop A           Loop 8B        Loop C SG Pressure                   800 psig       1200 psig     800 psig SG NR Level                     40%               80%         45%
SGPORV SG PORV                     SHUT             OPEN         SHUT RCS Temperature               557 of
                                              &deg;F          556 of
                                                                &deg;F      557 of
                                                                              &deg;F RCS Pressure: 1350 psig NOTE: ALL plant parameters were stable, with the exception of 8     B SG NR Level, which was going UP.
CURRENT plant parameters are as follows:
Loop A          Loop 8 B      Loop C SG Pressure                   500 psig        1050 psig    750 psig SG NR Level                     20%              85%          45%
SGPORV SG   PORV                     SHUT            SHUT        SHUT RCS Temperature               520 of
                                              &deg;F          550 of
                                                                &deg;F      550 of
                                                                              &deg;F RCS Pressure: 10001000 psig ALL above parameters are all decreasing (going DOWN), with Loop A parameters decreasing faster than Loops B8 and C.
Which ONE of the following correctly describes the NEXT action the crew should take in accordance with Emergency Operating Procedures?
A. IMMEDIATELY IMMEDIATELY go    go to EOP-2.0, EOP-2.0, Loss of Reactor or Secondary Secondary Coolant.
B.v B. . . IMMEDIATELY go    go to EOP-3.O, EOP-3.0, Faulted Steam Steam Generator Isolation.
Isolation.
C. RETURN to EOP-4.0, Steam      Steam Generator Tube Rupture, Rupture, Step Step 1.
1.
D. COMPLETE D.      COMPLETE EOP-4.0, EOP-4.0, Step Step 33 and and THEN go go to EOP-3.0, EOP-3.0, Faulted Faulted Steam Steam Generator Isolation.
Isolation.
 
VC SummerSummer NuclearNuclear Plant Plant 2005-301 SRO      SRO Inital Inital Exam Exam 100. W/E13EG2.2.2S 100.
W/E13EG2.2.25 001 001 Which ONE        ONE of      of the following following describes describes the basis                basis for reducing reducing the Power    Power Range Range Neutron Neutron Flux    Flux High Trip Setpoint, in accordance with Summer Technical Specification Table 3.7-1, if one or more main steam line code safety valves are inoperable for more than 4 hours?
A. To ensure that sufficient relieving capacity is available to limit secondary system pressure A.>oI to within 110% of design pressure.
B. To minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown of the INOPERABLE safety valve(s).
B. To minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown of the INOPERABLE safety valve(s).
C. To limit the pressure rise within the reactor building to within the values assumed in the accident analysis in the event of a steam line rupture within the reactor building.
C. To limit the pressure rise within the reactor building to within the values assumed in the accident analysis in the event of a steam line rupture within the reactor building.
D. To ensure that pressure induced stresses in the steam generator with the INOPERABLE safety valve(s) do not exceed the maximum allowable fracture toughness stress limits. -----------------------------------------------
D. To ensure that pressure induced stresses in the steam generator with the INOPERABLE safety valve(s) do not exceed the maximum allowable fracture toughness stress limits.
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Latest revision as of 23:15, 11 March 2020

301 Final SRO Written Exam (Section 9)
ML101620366
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 03/28/2010
From:
NRC/RGN-II
To:
References
50-395/05-301
Download: ML101620366 (61)
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Text

76. 002A2.04

76. 002A2.04 OO1l212/RCS/C/A 00 l/2/2/RCS/C/A (4.3/4.6)lN/SM05301lSIRFAlSDR (4.3/4. 6)/N/SM0530 l/S/RFAJSDR AA large large LOCA LOCA has has occurred.

occurred. Which Which ONE ONE of of the the following following actions actions are are corrrect corrrect given given the the following conditions:

following conditions:

17% andand continues continues to to decrease.

decrease.

  • RHR sump level RHR sump level isis 410 410 feet feet and and increasing.

increasing.

  • All RCPs All RCPs werewere tripped tripped (by (by procedure) procedure) when when RCS RCS pressure pressure dropped dropped below below 1400 1400 psig psig
  • The crew The crew isis currently currently performing performing the the actions actions ofof EOP-2.0, EOP-2.0, LOSS LOSS OF REACTOR OR OF REACTOR OR SECONDARY COOLANT SECONDARY COOLANT The following The following EOPs EOPs areare being being considered:

considered:

  • EOP-2.2, TRANSFER EOP-2.2, TRANSFER TO TO COLD COLD LEG LEG RECIRCULATION RECIRCULATION
    • EOP-2.4, LOSS OF EMERGENC EOP-2.4, LOSS OF EMERGENCY COOLANT RECIRCULATIONY COOLANT RECIRCULATION Transition to:

EOP-2.4 from A. EOP-2.4 from EOP-2.0.

EOP-2.0. When When RHRRHR sumpsump level level reaches reaches the the required required level, level, transition transition to to EOP-2.2.

B. EOP-2.4 from EOP-2.0. When RHR sump level reaches the required required level, return to EOP-2.0 and transition to EOP-2.2.

C. EOP-2.2 from EOP-2.0 then transition to EOP-2.4. When RHR sump level reaches the required level, return to EOP-2.0 and transition to EOP-2.2.

D EOP-2.2 from EOP-2.0 then transition to EOP-2.4. When RHR sump level reaches the Dyo required level, transition back to EOP-2.2.

Feedback Feedback Distractor analysis:

A and B. Incorrect: The transition is not made directly to EOP-2.4 from EOP-2.0 unless coolant recirculation was established and subsequently lost, this is not the case.

C. Incorrect:

Incorrect: The transition from EOP-2.4 is made back to the procedure step in in affect which would have been in EOP-2.2 not EOP-2.0.

D.

D. Correct.

Reference:

Reference:

EOP EOP 2, 2, page page 44 of of 32 32 EOP EOP 2.2, 2.2, page page 33 of of 13 13 EOP 2.4, page EOP 2.4, page 4 of 4 29 of 29 KIA CATALOGU K/A CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Reactor Reactor Coolant Coolant System System (RCS);(RCS); Ability to (a)

Ability to (a) predict predict the the impacts impacts of the following of the following malfunctions malfunctions or or operations operations on on the the RCS; RCS; and (b) based and (b) based on those predictions, on those predictions, use use procedures procedures to to correct, correct, control, control, or or mitigate mitigate thethe consequence consequences s of of those those malfunctions malfunctions or or operations:

operations: Loss Loss ofof heat heat sinks.

sinks.

Categories Categories Tier:

Tier: 22 Group:

Group: 22 Key Word:

KeyWord: RCS RCS Cog Level:

Cog Level: C/A CIA (4.3/4.6)

(4.3/4.6)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Reviewer:

Author/Reviewer: RFAJSDR RFAlSDR

77. 003A2.03
77. 003A2.03 002/211IRCPS/CIA 002/2/1/RCPS/C/A(2.7!3. 1 )/N/SM0530 1/S/RFAJSDR 2.7/3.1INISM0530IlSIRFAlSDR This Question This Question DELETED DELETED The following The following conditions conditions exist:

exist:

Reactor Power

- Reactor

- Power isis 9%.9%.

- AA Total

- Loss of Total Loss of All All Service Service WaterWater has has occurred.

occurred.

AOP-1 17.1, Total Loss of Service

- AOP-117.1, "Total Loss of Service Water," has

- Water, has been been entered.

entered.

RCP temperatures are

- RCP temperatures are beginning to

- beginning to rise.

rise.

Service Water

- Service

- Water can can not not be be restored.

restored.

Which ONE Which ONE of of the the following following describes describes the the action(s) action(s) the the operators operators must must take and .the take and the sequence sequence of those actions (in accordance of those actions (in accordance with AOP-117.1)?with AOP-1 17.1)?

A.v Initiate aa reactor A Initiate reactor plant plant shutdown shutdown per per GOP-4B, GOP-4B, POWERPOWER OPERATION OPERATION (MODE(MODE 11 - -

DESCENDING). Stop DESCENDING). Stop upup to TWO RCPs.

to TWO RCPs. Isolate Isolate unnecessary unnecessary CCW COW loads, loads, and and ensure ensure FS FS

  • is is aligned to the DIGs. D/Gs. When an an RCP RCP motor motor bearing bearing temperatures or lower seal water or lower bearing temperature exceeds the specified limit, bearing limit, stop the affected RCP.

RCP.

B. Initiate a reactor B. Initiate reactor plant plant shutdown per per GOP-4B, GOP-4B, POWERPOWER OPERATION OPERATION (MODE(MODE 11 - -

DESCEN DING).

DESCENDING). Isolate unnecessary CCW loads, and ensure FS is aligned to the DIGs.

Secure an RCP only if motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit.

C. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 11 - -

DESCENDING). Stop at least TWO RCPs. Isolate unnecessary CCW loads, and ensure DESCENDING).

ES is aligned to the DIGs.

FS D/Gs. When the running RCP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, increase monitoring and continue pump operation until the unit is shutdown then stop the affected pump.

D. Stop ONE RCP. Initiate aa reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 11 - DESCENDING).

- DESCENDING). When an RCP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, trip the reactor and stop the affected RCP.

Feedback Feedback Distractor Analysis:

Distractor Analysis:

A. Correct:

A. Correct: lAW AOP-1 17.1, the lAW AOP-117.1, the reactor reactor should should be be shutdown shutdown (not (not tripped).

tripped). Secure Secure upup to to TWO TWO RCPs (Step RCPs (Step 12).

12). TheThe affected affected RCPRCP should should bebe shutdown shutdown ifif RCP RCP motor motor bearing temperatures bearing temperatures exceeds 195 exceeds 195 of°F oror lower lower seal seal water water bearing bearing temperature temperature exceeds exceeds 2250F 225°F (Step (Step 13).

13).

B. Incorrect:

B. Incorrect: Do Do not not wait wait until until temperature temperature are are exceeded exceeded to secure RCPs to secure RCPs C. Incorrect:

C. Incorrect: Step Step 12 12 allows allows two two RCPs RCPs to to be be stopped stopped ifif plant plant conditions conditions permit.

permit. Prudent Prudent action action is to is shutdown with to shutdown with 22 RCPs RCPs running running and secure one and secure one ifif necessary necessary for for temperature.

temperature.

D. Incorrect:

D. Incorrect: Shutdown Shutdown isis initiated initiated inin step step 33 and and Step Step 12 12 secures secures the the RCP.

RCP. Reactor Reactor isis not not tripped unless unless above above P-7.P-7.

References:

GOP-4B

References:

GOP-4B AOP-117.1, page 8 AOP-118.1, page page 55 K/A CATALOGUE KIA CATALOGUE QUESTION DESCRIPTION: DESCRIPTION:

- Reactor Coolant Pump System (RCPS); Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures consequences of those malfunctions or operations: Problems to correct, control, or mitigate the consequences associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems.

Facility POST EXAM comment resulted in this question being DELETED from the exam. The correct sequence is not contained in any of the distractors, so there is no correct answer.

The question was originally constructed and proposed by the NRC to contain only a list of the actions taken in the AOP without regard to sequence. The NRC agreed to the addition of the sequence "sequence" requirement and the inclusion of more of the sequence at the request of V. C.

Summer.

Categories Categories Tier:

Tier: 22 Group: 1I Key Word:

KeyWord: RCPS Cog Level:

Level: C/A(2.7/3.l)

C/A(2.7/3.1)

Source:

Source: N Exam: SM05301 SM05301 Test: SS Author/Revi ewer: RFAISDR Author/Reviewer: RFAlSDR

78. 005G2.1.27
78. 005G2. 1.27 OOII2/l/RHRIM 001/2/1 /RHRJM (2.812.9)/N/SM05301/SIRFAlSDR (2.8/2.9)/N/SM0530 1/S/RFA/SDR Which ONE Which ONE of the following of the following correctly correctly describes describes the the purpose purpose andand or or function function (not (not all all inclusive) inclusive) of the of the RHR RHR system system and and one one ofof its its Mode Mode 44 Technical Technical Specification Specification requirements?

requirements?

A.A. Hot Leg Recirculation, Hot Leg Recirculation, Refueling Refueling Cavity Cavity Cooling, Cooling, Alternate Alternate Water Water supply supply to to Reactor Reactor Building Building Coolers, Pressurizer Relief Tank Cooling.

Coolers, Pressurizer Relief Tank Cooling. RHR can RHR can bebe deenergized deenergized for for up up to to 22 hour2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> hour provided that provided that core core outlet outlet temperature temperature isis maintained maintained at at least least 50°F 50°F below below saturation saturation temperature.

temperature.

B. Cold B. Cold Leg Leg Recirculation, Recirculation, Hot Hot Leg Leg Recirculation, Recirculation, Simultaneous Simultaneous Cold Cold Leg Leg - Hot

- Hot Leg Leg Recirculation, Alternate Recirculation, Alternate Water Water supply supply to Reactor Building to Reactor Building Coolers.

Coolers. RHR RHR can can be be deenergized for deenergized for up up to hour provided to 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> provided that that core core outlet outlet temperature temperature isis maintained maintained at at least least 10°F below saturation temperature.

100F below saturation temperature.

C. Refueling Cavity C. Refueling Cavity Draining, Draining, Cold Cold Overpressure Overpressure Protection, Protection, Simultaneous Simultaneous Cold Cold Leg Leg - Hot

- Hot Leg Leg Recirculation, Pressurizer Recirculation, Pressurizer Relief Relief Tank Tank Cooling.

Cooling. RHRRHR can be be deenergized for up up to 22 hour2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> hour provided that provided that core outlet temperature core outlet temperature is maintained at is maintained least 50°F at least 50°F below below saturation saturation temperature.

D Cold Leg Recirculation, D)/ Recirculation, Refueling Cavity Draining, Cold Overpressure Protection, Cold Leg Injection. RHR can be deenergized for up to 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> provided that core outlet temperature is maintained at least 10°F below saturation temperature.

Feedback Feedback Distractor Analysis:

A. Incorrect: Hot Leg Recirculation, Recirculation, Alternate Water supply to Reactor Building Coolers, Pressurizer Relief Tank Cooling are all incorrect functions. RHR can be deenergized for up to 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> provided that core outlet temperature is maintained at least 10°F 100 F below saturation temperature.

B.

B. Incorrect: Hot Leg Recirculation Recirculation,, Alternate Water supply to Reactor Building Coolers Coolers are incorrect functions.

C. Pressurizer Pressurizer Relief Tank Cooling Cooling is is an an incorrect incorrect function.

D. Correct D. Correct answer answer

References:

References:

AB-7,AB-7, RHR RHR system, system, pagepage 99 AB-2, AB-2, RCS,RCS, page page 99 lB-i, IB-1, SW SW System, System, pagepage 1717 TS 3.4.1.3, page 237 TS 3.4.1.3, page 237 and 241 and 241 K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Residual Residual Heat Heat Removal Removal System; System; Knowledge Knowledge of of system system purpose purpose andand oror function.

function.

Categories Categories Tier:

Tier: 22 Group:

Group: 11 Key Word:

KeyWord: RHR RHR Cog Level:

Cog Level: M (2.8/2.9)

M (2.8/2.9)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revie AuthorlReviewer:

wer: RFAlSDR RFA/SDR

79.007A2.03

79. 002/2/1 /PRT PRESSURE/C/A 007A2.03 0021211IPRT PRESSURE/C/A(3 .6/3 .9)/N/SM0530 I /S/FJE/SDR 3.6/3.9)/N/SM0530IlS/FJE/SDR Plant conditions Plant conditions are are asas follows:

follows:

-- The unit The unit isis in Cold Shutdown.

in Cold Shutdown.

-- The RCS The RCS isis water water solid solid with with one one train train of RHR providing of RHR providing shutdown shutdown cooling.

cooling.

RHR letdown isis in RHR letdown in service service with with PCV-145 PCV-145 controlling controlling RCS RCS pressure pressure in in AUTO.

AUTO.

-- ALL pressurizer ALL pressurizer PORV PORV control control switches switches areare in in AUTO.

AUTO.

RCS temperature is RCS temperature is 140 140 of.

°F.

- PRT level PRT level isis 78%.

78%.

- PRT pressure PRT pressure is is 66 psig.

psig.

PRT temperature is PRT temperature 95 of is 95 °F Assuming no no operator operator action, action, aa _ _ _ _ _ will result in aa pressure result in pressure increase increase in in the PRT PRT and and the crew can can restore PRT PRT parameters parameters by by _ _ _ _ _ __

A. A HIGH HIGH failure of PT-444, pressurizer of PT-444, pressurizer pressure pressure control channel transmitter.

Spraying down the PRT PRT using reactor reactor makeup water per SOP-1 SOP-i 01, Reactor Reactor Coolant System.

B.

B ..... Loss of air to HCV-142, LTDN FROM RHR.

Draining the PRT to the Recycle Holdup Tanks per SOP-1 SOP-i 08, Liquid Waste Processing System.

C. A HIGH failure of PT-444, pressurizer pressure control channel transmitter.

C.

Draining the PRT to the Recycle Holdup Tanks per SOP-1 SOP-i 08, Liquid Waste Processing System.

D. Loss of air to HCV-142, LTDN FROM RHR.

D.

Spraying down the PRT using reactor makeup water per SOP-ioi, SOP-1 01, Reactor Coolant System.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

A Incorrect failure.

A Incorrect failure. AA failure failure of PT-444 of PT high will

-444 high will not not cause cause aa pressurizer pressurizer PORV PORV to to open open because the because the P-11 P-i 1 signal signal (2/3 (2/3 pressurizer pressurizer protection protection channels channels less less than than 1985 psig) will 1985 psig) will prevent automatic operation of the pressurizer prevent automatic operation of the pressurizer PORVs PORVs inin this plant Mode.

this plant Mode.

Plausible because Plausible because thethe discharge discharge of of aa pressurizer pressurizer PORV PORV will will cause cause an an increase increase in in PRT PRT pressure.

pressure.

Incorrect corrective corrective action.

action. ???At

???At 180 o 180°F/6+ psig, the Incorrect F/6+ psig, PRT isis saturated the PRT saturated (no(no vapor vapor bubble).???

bubble).  ???

Spraying the Spraying the PRT PRT would would notnot reduce reduce PRT PRT pressure pressure (but(but would would increase increase PRT PRT pressure pressure as as PRT level PRT level increased increased from from the the addition addition of of reactor reactor makeup makeup water).

water). Plausible Plausible because because thisthis action would action reduce PRT would reduce PRT pressure pressure following following aa relief relief or or safety safety valve valve discharge discharge at at power.

power.

BB Correct Correct failure.

failure. HCV-142 HCV-142 willwill fail fail shut shut onon loss loss of of air.

air. A failure of A failure of HCV-142 HCV-142 in in the the closed closed position isolates the position isolates RHR system the RHR system from from thethe letdown letdown system.

system. With With charging flow in charging flow in manaul, manaul, RCS pressure RCS pressure will increase until the RHR RHR suction relief valve(s) lift, relieving to the PRT. PRT.

corrective, action.

Correct corrective action. Draining the PRT will reduce reduce PRT pressure.

C Incorrect failure. See A. Correct corrective action. See B.

D Correct failure. See B. Incorrect corrective action. See A.

REFERENCES:

REFERENCES:

1. Panel XCP-616, Annunciator Point 4-4
2. AB-2, Reactor Coolant System, Pressurizer Relief Tank
3. AB-7, Residual Heat Removal System SOP-i 01, Reactor Coolant System
4. SOP-1 K/A CATALOGU KJA CATALOGUE E QUESTION DESCRIPTION:

DESCRIPTION:

- Ability to (a) predict the impacts of the following malfunctions or operations on the P S 5

(Pressurizer Relief Tank 1 / Quench Tank System); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequence consequences s of those malfunctions or operations: Overpressuri zation of the PZR (3.6/3.9)

Overpressurization Categories Tier: 22 Group: 11 Key Word:

KeyWord: PRT PRESSURE Cog Level: C/A(3.6/3.9)

C/A(3.6!3.9)

Source:

Source: N Exam: 5M05301 SM05301 Test: SS Author/Revi Author/Reviewer:

ewer: FJE!SDR FJE/SDR

80. 007EA2.01
80. 007EA2.0 1 002/1/1IREACTOR 002/1/1/REACTORTRIPICIA(4.1/4.3)/M/SM05301lSIMC/SDR TRJP/C/A(4. 1/4.3)/M/SM0530 1/S/MC/SDR At50%

At 50% power, power, the the plant plant experienced experienced aa loss loss ofofBOTH BOTH running running Main Main Feedwater Feedwater Pumps Pumpswith with aa concurrent failure of the concurrent failure of the Reactor trip Reactor trip breaker breakerAA toto open.

open. TheThe crew crew isis performing performing the the immediate immediate actions of actions of EOP-1.0, EOP-1 .0, "Reactor ReactorTrip/Safety Trip/Safety Injection Injection Actuation."

Actuation.

Current plant Current plant conditions conditions are are asas follows:

follows:

-- The Integrated The Integrated Plant Plant Computer Computer SystemSystem has has failed.

failed.

-- SG LO-LO Level annunciators SG LO-LO Level annunciators are are lit.

lit.

-- Reactor Power Reactor Power isis 7% 7% and and slowly slowly decreasing.

decreasing.

-- All EFW All EFW Pumps Pumps failedfailed toto start.

start.

Which ONE Which ONE of the following of the following describes describes the the procedure procedure path path based based onon the the above above information?

information?

A. Remain A. Remain in EOP-1 .0, until in EOP-1.0, until directed directed to monitor Critical to monitor Critical Safety Safety Functions Functions then then transition transition toto EOP-1 EOP-15.0, Response To 5.0, "Response To Loss Loss ofof Secondary Secondary Heat Heat Sink."

Sink.

B. Directly B. Directly enter enter EOP-15.0, EOP-1 5.0, "Response Response To To Loss Loss ofof Secondary Secondary Heat Heat Sink."

Sink.

C Remain Cy Remain in in EOP-1.0, EOP-1 .0, until directed to monitor Critical Critical Safety Safety Functions Functions then transition transition toto EOP-13.0, Response To EOP-13.0, "Response To Abnormal Nuclear Nuclear Power Power Generation."

Generation.

DDt Transition from EOP-1.0

..... Transition EOP-1.0 to EOP-13.0, EOP-13.0, "Response Response To Abnormal Nuclear Nuclear PowerPower Generation.

Generation."

Feedback Feedback D ISTRACTORS:

DISTRACTORS:

A INCORRECT A INCORRECT Should transition directly to EOP-13.0. EOP-1 3.0.

B B INCORREC INCORRECT T Should transition directly to EOP-13.0.

C C INCORREC INCORRECT T Should transition directly to EOP-13.0.

DD CORRECT CORRECT Should transition transition directly directly to to EOP-13.0.

EOP-13.0. SinceSince there there areare nono given given conditions conditions that would would warrant an SI, an SI, the CRS shouldshould follow the the Alternative Alternative Action for for Step Step 55 of of EOP-1.0 EOP-1.0 and and transition transition to to EOP-1.1.

EOP-1.1. Upon Upon transition transition from from EOP-1 EOP-1.0, .0, the the STA STA begins begins monitoring monitoring of of CSFs, CSFs, and and should should infrom infrom CRS CRS of of Red Red path path toto EOP-13.0 EOP-13.0 based based on on power power >5%.

>5%.

REFERENC

REFERENCES:

ES:

1.

1.

KIA KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTIDESCRIPTION: ON:

- Reactor Reactor Trip; Trip; Ability Ability toto determine determine or or interpret interpret the the following following as as they they apply apply toto aa reactor reactor trip:

trip:

. Decreasing Decreasing power power level, level, from from available available indications.

indications.

Facility Facility POST POST EXAM EXAM comment comment resulted resulted inin accepting accepting twotwo answers answers for for this this question.

question. With With aa decreasing decreasing power power level level the the applicant applicant may may not not transition transition immediately immediately based based on on the the indications indications present present and and wait wait until until directed directed by by the the status status trees.

trees.

Categories Categories Tier:

Tier: I Group:

Group: 11 Key Word:

KeyWord: REACTOR TRIP REACTOR TRIP Cog Level:

Cog Level: C/A(4.1I4.3)

C/A(4.1/4.3)

Source:

Source: MM Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Reviewer:

AuthorlReviewer: MC/SDR MC/SDR

81. 008A2.04
81. 008A2.04002/2111CCW/CIA 002/2/1/CCW/C/A(3.3/3.5)/M/SM0530IlSIRFAlSDR (3.3/3.5)/M/SM05301/S/RFA/SDR The Unit The Unit isis operating operating atat 100%

100% power powerwith all systems with all systems inin normal normal lineups lineups when when thethe following following annunciators annunciators actuate: actuate:

- LLTDN/SL TDN/SL WTR WTR HX FLO LO HX FLO LO TEMP TEMP HI HI

--CC LOOP AA RM-L2A CC LOOP RM-L2A HI HI RAD RAD

- CC

- SRG TK CC SRG TK VENT VENT 70967096 CLSD CLSD HI HI RAD RAD CCW SRG TK LVL

- CCW SRG TK LVL HI/LO/LO-LO HI/LO/LO-L O NO other NO other annunciators annunciators are are litlit and and all all associated associated automatic automatic functions functions have have occurred.

occurred.

Which ONE Which ONE of of the following isis the the following the correct correct cause cause andand action?

action?

A. AA leak A. leak exists exists inin the the Letdown Letdown HX; HX; verify verify closure closure ofof PVT-8152, PVT-8152, LTDNLTDN LINE LINE ISOL, ISOL, perper SOP-i 02, CHEMICAL SOP-102, CHEMICAL AND VOLUME AND VOLUME CONTROL CONTROL SYSTEM, SYSTEM, and and manually manually shut shut PW-7096, PW-7096, CCSURGET CC SURGE TK KVLVVL V B B.

..... A leak exists A leak exists inin the the Letdown Letdown HX; HX; manually manually close close PVT-8152, PVT-8152, LTDNLTDN LINELINE ISOL, ISOL, perper SOP-i 02, CHEMICAL SOP-102, CHEMICAL AND AND VOLUME VOLUME CONTROL CONTROL SYSTEM, SYSTEM, and and verify closure of verify closure of PW-7096, CC SURGE TK VLV PW-7096, C. RCP C. RCP "A" A thermal barrier has been breached. Conduct a normal shutdown per GOP-4B, POWER OPERATION POWER OPERATION (MODE 11 - DESCENDING), - DESCENDING), Stop RCP A within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per SOP-lOl, SOP-1 01, REACTOR COOLANT SYSTEM.

D. A D. A Phase Phase "B" B Containment Isolation has actuated due to RM-L2A&B (Component Cooling) alarming.

alarming. Immediately trip the reactor and trip ALL RCPs and enter EOP 1.0.

Feedback Feedback Distractor Distractor Analysis:Analysis:

A.

A. Incorrect.

Incorrect. PVT-81 PVT-8152 52 must be manually shut and PVV-7096 PW-7096 should close automatically and and be be verified verified closed.

B.

B. Correct:

Correct:

C.

C. Incorrect:

Incorrect: RCP RCP seals seals have have not not failed failed nor nor has has the the thermal thermal barrier barrier been been breached.

breached. Therefore, Therefore, Stopping Stopping RCP RCP A A within within 88 hours0.00102 days <br />0.0244 hours <br />1.455026e-4 weeks <br />3.3484e-5 months <br /> hours per per SOP-i SOP-1 01,01, REACTOR REACTOR COOLANTCOOLANT SYSTE, SYSTE, does does notnot apply.

apply.

D.

D. Incorrect:

Incorrect: RM-L2A&B RM-L2A&B 99 will will not not cause cause aa Phase Phase BB Containment Containment Isolation.

Isolation.

References:

References:

AOP AOP 101, 101, Reactor Reactor Coolant Coolant Pump Pump Seal Seal Failure, Failure, page page 88 SOP SOP 102.2, 102.2, CHEMICAL CHEMICAL AND AND VOLUME VOLUME CONTROLCONTROL SYSTEM,SYSTEM, page page 70,70, ARP-001-XC ARP-001-XCP-601, page 16 P-601, page 16 KIA CATALOGU K/A CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Component

- Component Cooling WaterCooling Water SystemSystem (CCWS);

(CCWS); Ability Ability to (a) predict to (a) predict the the impacts impacts ofofthe the following following malfunctions malfunctions or or operations operations onon the the CCWS, CCWS, and and (b)

(b) based based on on those those predictions, predictions, use use procedures procedures toto correct, correct, control, control, or or mitigate mitigate the the consequence consequences s of ofthose those malufunction malufunctions or operations:

s or operations: PRMS PRMS alarm.

alarm.

Categories Categories Tier:

Tier: 22 Group:

Group: 11 Key Word:

KeyWord: CCW CCW Cog Level:

Cog Level: CIA C/A (3.3/3.5)

(3.3/3.5)

Source:

Source: MM Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Reviewer:

Author/Reviewer: RFAJSDR RFAlSDR

82. 009EG2.4.30
82. 009EG2.4.30 002/1/I1REPORTABILITYIM(2.2/3.6)/N/SM0530IlSIRFAlSDR 002/1/1/REPORTABILITY/M(2.2/3 .6)/N/SM0530 1/SIRFAJSDR Which ONE Which ONE of of the the following following identifies identifies an an event event that that isis required required to to be be reported reported to to the the NRC NRC withinwithin hour per 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> per EPP-002, EPP-002, COMMUNICATION COMMUNICATION AND AND NOTIFICATION.

NOTIFICATION.

A. An A. unplanned ECCS An unplanned ECCS initiation initiation that that does does not not discharge discharge to to the the RCS RCS during during an an SISI surveillance surveillance test.

test.

BB.v An ECCS

..... An ECCS discharge discharge to to the the RCS RCS inin response response to to aa small small break break LOCA.

LOCA.

C. An C. An airborne airborne release release ofof>

> 2X2X Appendix Appendix BB limits.

limits.

D. liquid release D. AA liquid release of> of> 2X 2X Appendix Appendix BB limits.

limits.

Feedback Feedback Distractor Analysis:

Distractor Analysis:

A. Incorrect:

A. Incorrect: This This is is aa non-emergency non-emergency event event that that does does notnot discharge discharge to to the the RCS RCS this this is is aa 44 hour5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> notification hour notification requirement.

requirement.

B. Correct: A LOCA is an emergency event B. Correct: event which requires notification.

C. Incorrect: This is a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification requirement D. Incorrect: This is a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification requirement D.

Reference:

EPP-002,

Reference:

EPP-002, page 27 K/A CATALOGUE KIA CATALOGUE QUESTION DESCRIPTION: DESCRIPTION:

Small

- Small

- Break LOCA; Knowledge of which events related to system operations/status operations/status should be be reported reported to outside agencies.

Categories Categories Tier:

Tier: I Group: 1 Key KeyWord: Word: REPORTAB REPORTABILITYILITY Cog Level: M(2.2/3.6)

Source:

Source: N Exam: SM05301 Test:

Test: SS Author/Revi Author/Reviewer:

ewer: RFAJSDR RFAlSDR

83. 022AG2.4.49 OOl/1/l1RCS
83. 022AG2.4.49 00 1/1/1/RCS MAKEUP/CIA MAKEUP/C/A(4.0/4.0)/N/SM05301lSIRFAlSDR (4.0/4.O)/N/SM05301/S/RFAJSDR The plant The plant was was operating operating at at 80%

80% power power when when the following annunciators the following annunciators (not (not all all inclusive) inclusive) came came in:

in:

- REGEN HX REGEN HX LLTDN TDN OUTOUT TEMPTEMP HI HI

- VCT LVL VCT LVL HIILO HI/LO

- CHG LINE CHG LINE FLO FLO HIILO HI/LO

- PZR LCS PZR LCS DEV HIILO DEV HI/LO Charging pump Charging pump amps amps are are fluctuating fluctuating between between 25 25 andand 3030 amps amps Charging flow Charging flow isis fluctuating fluctuating between between 25 25 and and 30 gpm 30 gpm Charging pressure Charging pressure isis oscillating oscillating between between 25002500 andand 2600 2600 psig psig Which ONE Which ONE of of the the following following set of actions set of actions should should thethe supervisor supervisor direct direct his his board board operators operators toto perform (These actions perform (These actions are not are all inclusive)?

not all inclusive)?

A.% Secure A.II Secure the the operating operating charging charging pump, pump, close close allall letdown letdown isolation isolation valves, valves, andand close close FCV-122, charging FCV-122, charging flow flow control control valve.

valve.

B. Verify at least one one charging charging pump pump is operating, verify FCV-122 is open, and verify CCW COW flow to the RCP Thermal Barriers is GREATER THAN 90 gpm on FI-7273A(B), FI-7273A(B), THERM BARR FLOW GPM.

C. Secure the operating charging pump, realign charging pump suction, and close both LCV-1 15B(D), RWST TO CHG PP SUCT.

LCV-115B(D),

D. Verify at least one charging pump is operating, verify FCV-122 is open, and open both D.

LCV-115C(E), VCT OUTLET ISOL.

LCV-115C(E),

Feedback Feedback Distractor Analysis:

A.

A. Correct answer per AOP-1 02.2, page 4-6 AOP-102.2, B,C, and D. Charging flow is abnormal - must go to the RNO column. Closing

- ClOSing both LCV-1 1 5B(D), RWST TO CHG PP SUCT, LCV-115B(D), SUCT, is is an an action action ifif charging charging was initially initially aligned aligned toto the the RWST.

Reference:

Reference:

AOP-1 02.2, page AOP-102.2, page 4-6 4-6 K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIP11 DESCRIPTION: ON:

- Loss of

- Loss of Reactor Reactor Coolant Coolant Makeup; Makeup; Ability to perform Ability to perform without without reference reference to to procedures procedures those those actons actons thatthat require require immediate immediate operation operation of of system system components components and and controls.

controls.

Categories Categories Tier:

Tier: 1 Group:

Group: 1 Key Word:

KeyWord: RCS MAKEUP RCSMAKEUP Cog Cog Level:

Level: CIA (4.0/4.0)

C/A (4.0/4.0)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revie AuthorlReviewer: RFAlSDR wer: RFAJSDR

84. 032AA2.08
84. 032AA2.08 003/l/2/SRNIIM(2.2/3.1 003/112/SRNI/M(2.2/3. 1)IN/SM053

)/N/SM053001/S/MCIRF AISDR l/SIMCIRF AlSDR Refueling operations Refueling operations are are inin progress, progress, with with SR monitor N33 SR monitor N33 out of service, out of service, when when power power isis suddenly lost to source range neutron suddenly lost to source range neutron flux monitor N31 flux monitor N31 andand subsequently subsequently regained regained 30 30 minutes minutes later.

later.

Which ONE Which ONE of of the the following following describes describes the the action action to be taken to be taken forfor this this situation situation when when powerpower isis lost?

lost?

A."A. Suspend Suspend all all core core alterations alterations andand perform perform an an analog analog channel channel operational operational testtest ofof source source range neutron flux range neutron flux monitor N31monitor within 88 hours0.00102 days <br />0.0244 hours <br />1.455026e-4 weeks <br />3.3484e-5 months <br /> N31 within hours prior prior toto the the initial initial start.of startof core core alterations.

alterations.

B.B. Suspend Suspend all all core core alterations alterations andand perform perform aa neutron neutron fluxflux response response time time test test AND AND operational operational test of test source range of source range neutron neutron flux flux detector detector N31N31 within within 88 hours0.00102 days <br />0.0244 hours <br />1.455026e-4 weeks <br />3.3484e-5 months <br /> hours prior prior to to the the initial initial start start of of core core alterations.

alterations.

C. Determine boron C. Determine boron concentration concentration and perform aa channel and perform channel checkcheck of of source source range range neutron neutron flux flux monitor monitor N31 N31 withinwithin 1212 hours0.014 days <br />0.337 hours <br />0.002 weeks <br />4.61166e-4 months <br />.

hours.

D.D. Determine Determine boron concentration and perform a neutron neutron flux response response time test of source source range neutron range neutron flux detector detector N31N31 within 12 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

hours.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

A CORRECT T.S. 3.9.2 requires immediate suspension of CORE ALTERATIONS ALTERATIONS when one of the two SR monitors are lost INCORRECT B INCORRECT (*

B Per T.S. Table 3.3-2 (* and Note 1), neutron detectors (not the channel) are exempt from response time testing.

C INCORREC INCORRECT T Boron concentration measuremen measurements ts are only required when both monitors are down.

D INCORREC D INCORRECT T Boron concentration measuriment measuriments s are only required when both monitors are down. Neutron Neutron detectors are exempt from response time time testing.

REFERENC

REFERENCES:

ES:

1. TS 3.9.2,
1. TS 3.9.2, Instrumenta "Instrumentation." tion.
2. TS
2. TS 3.9.1, 3.9.1, Boron "Boron Concentratio Concentration." n.
3. TS
3. TS Table Table 3.3-2, 3.3-2, Reactor "Reactor TripTrip System System Instrumentat Instrumentationion Response Response Times.

Times."

4.

4. IC-8, IC-8, Nuclear "Nuclear Instrumentat Instrumentation,"ion, pages pages 24, 48, && 50.

24,48, 50.

K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTIDESCRIPTION: ON:

- Loss of Source

- Loss of Source Range Range Nuclear Nuclear Instrumentat Instrumentation;ion; Ability Ability toto determine determine and and interpret interpret thethe following following as as they they apply apply to the Loss to the Loss ofof Source Source Range Range Nuclear Nuclear Instrumentat Instrumentation: Testing required ion: Testing required ifif power power isis lost, lost, then then restored.

restored.

Categories Categories Tier:

Tier: 1 Group:

Group: 22 Key KeyWord:Word: SRNI SRNI Cog Level:

Cog Level: M(2.2/3.1)

M(2.2/3.1)

Source:

Source: N N Exam:

Exam: SM05301 SM0530 1 Test:

Test: SS Author/Revie wer:

AuthorlReviewer: MC/RFAlSDR MC/RFAJSD R

85. 035G2.4.20
85. 035G2.4.20 002/2/2/SGIC/A 002/2/2/SG/C/A (3.3/3.4)/N/SM05301lSIRFAlSDR (3.3/3.4)/N/SM0530 1/SIRFAJSDR The crew The crew hashas just just entered entered EOP-15.0, EOP-15.O, "Response Response to to Loss Loss ofof Secondary Secondary Heat Heat Sink" Sink from from EOP-12.O, Monitoring of Critical EOP-12.0, Monitoring of Critical Safety Safety Functions.

Functions.

The following The following conditions conditions exist:exist:

-- WR SG WR SG "A"A level level isis 25%

25%

-- WR SG WR SG "B" B level level isis 12%

12%

- WR SG "c" level is 11%

WR SG C level is 11%

-- Total Feed Total Feed Flow isFlow is 290 290 gpm gpm Which ONE Which ONE of the following of the following sets sets of actions (not of actions (not all all inclusive) inclusiye) should should be be taken taken as as directed directed byby EOP-1 5.0, "Response EOP-15.0, Response to to Loss Loss of of Secondary Secondary Heat Heat Sink"?

Sink?

A. Ensure A. Ensure allall EFW EFW valves valves are are open open and and establish establish EFWEFW flow flow to at least to at least one one SG.

SG.

B. Reset B. Reset SI and establish SI and establish MFW MFW flow to either either the "B" or "c" B or C Steam Steam Generators.

Generators.

Reset SI, dump steam to the condenser and feed using a condensate pump.

C. Reset C.

D D~ Trip ALL RCPs, actuate SI, establish an RCS bleed path:

Feedback Feedback NOTE: No NOTE: No other initial conditions are needed. The caution prior to step 4 of EOP-15 EOP-1 5 isis a stand stand alone alone statement. If the SRO has entered this procedure and these conditions exist, there is is no no other option.

other Distractor Analysis:

Distractor A, B, C. Incorrect:

Incorrect: Not allowed due to caution prior to step 4. These steps are bypassed when when the CAUTION the CAUTION prior to Step 4 is implemented implemented..

D D Correct:

Correct:

Reference:

Reference:

EOP-12, EOP-12, page page 99 EOP-15, EOP-15, page page 33 caution prior to step step 44 K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Steam Steam Generator; Generator; Knowledge Knowledge of of operational operational implications implications of of EOP EOP warnings, warnings, cautions, cautions, and and notes.

notes.

Categories Categories Tier:

Tier: 22 Group:

Group: 22 Key Word:

KeyWord: SG SG Cog Cog Level:

Level: CIA (3.3/3.4)

C/A (3.3/3.4)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revi Author/Reviewer:

ewer: RFAlSDR RFAJSDR

86. 054AA2.03
86. 054AA2.03 0021111/MFW/C/A 002/1/1/MFW/C/A (4.1I4.2)/N/SM05301lSIRFAlSDR (4. 1/4.2)/N/SM0530 1!SIRFA!SDR The following The following conditions conditions exist:

exist:

- AA plant

- plant startup startup was was inin progress.

progress.

Power level

- Power

- level was was at 38%

at 38%

The reactor

- The

- reactor tripped tripped SG blowdown isolation valves

- SG blowdown isolation

- valves (PVG-503A(B)(C),

(PVG-503A(B)(C), A(B)(C) A(B)(C) ISOL)

ISOL) closed closed Current SG narrow range

- Current SG narrow range levels

- levels inin "A",

A, "B", and "c" B, and C SGs SGs are are 8%,10%,

8%, 10%, and and 10%, respectively, 10%, respectively, and and decreasing decreasing Which ONE Which ONE of of the the following following correctly correctly states states the initiating event the initiating event that that caused caused thethe trip trip and and the the expected automatic expected automatic actions actions based based on on these these conditions?

conditions?

A. The A. The operating operating MFPMFP tripped tripped and ONLY the and ONLY the motor motor driven driven EFW EFW pumps pumps havehave aa current current start start signal.

signal.

BB.v The operating

..... The operating MFPMFP tripped and BOTH the turbine driven and BOTH driven AND AND motor motor driven driven EFW EFW pumps pumps have aa current have current start start signal.

signal.

C. All SG flow control valves drifted closed and AMSAC should should have actuated.

D. All D. All SG flow control valves drifted closed and ONLY the turbine driven EFW pump has aa current start signal.

current Feedback Unless the applicant keys on the fact that SG blowdown isolation valves (PVG-503A(B)(C),

Unless (PVG-503A(B)(C),

A(B)(C)

A(B)(C) ISOL) closed, he may consider C or D.

Distractor Analysis:

A. Incorrect:

A. Incorrect: LO LO level both MDEFP AND TDEFP will start B. Correct:

C.

C. Incorrect:

Incorrect: All SG SG flow control control valves drifting drifting closed couldcould cause cause this.

this. ????Howeve

????However, SG r, SG blowdown blowdown isolationisolation valves valves (PVG-503A(

(PVG-503A(B)(C),B)(C), A(B)(C) ISOL) ISOL) closed which dont don't according according to ARP XCP-624.???

XCP-624. ????  ? Additionally Additionally,, AMSAC AMSAC will not not actuate since initial initial power power was <40%< 40%

D. Incorrect:

D. Incorrect: All SG flow control All SG control valves valves drifting drifting closed closed could could cause cause this.

this. ????Howeve

????However, SG r, SG blowdown isolation blowdown isolation valves valves (PVG-503A(

(PVG-503A(B)(C),B)(C), A(B)(C)

A(B)(C) ISOL)

ISOL) closed closed which which dont don't according according to to ARP ARP XCP-624.

XCP-624. ???? ???? Additionally Additionally,, both both MDEFP MDEFP AND AND TDEFP TDEFP will will start.

start.

Reference:

Reference:

ARP-001-XC ARP-001-XCP-624, P-624, page page 22 22 and and 26 26 KIA CATALOGU K/A CATALOGUE E QUESTION QUESTION DESCRIPTIDESCRIPTION: ON:

- Loss of Main Feedwater (MEW);

- Loss of Main Feedwater (MFW); Ability to Ability to determine determine and and interpret interpret the the following following asas they they apply apply to the Loss of Main Feedwater to the Loss of Main Feedwater (MFW): (MFW): Conditions Conditions and and reasons reasons for for AFW AFW pump pump startup.

startup.

Categories Categories Tier:

Tier: 1 Group:

Group: 11 Key Word:

KeyWord: MFW MFW Cog Level:

Cog Level: CIA C/A (4.114.2)

(4.1/4.2)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Reviewer:

AuthorlReviewer: RFA/SDR RFAISDR

87. 068G2.1.20 B7. 068G2. 1.20002/2/2/U 002/2/2/LIQU DIDiDRADWASTE/C/A(4.3/4.2 RADWASTE/C/A(4.3/4.2/N/SM05301/SIRFAlSDR

)/N/SM05301/S/RFA/SDR Liquid Radwaste AA Liquid Radwaste Release Release isis been been inin progress:

progress:

-- XCP-646 2-5, XCP-646 2-5, MON MON TK TK DISCH DISCH RM-L5RM-L5 HI HI RAD, RAD, hashasjust just actuated actuated for forthe the second second time.

time.

-- RCV0001 8-WL, Liquid RCV0001B-WL, Liquid Radioactive Radioactive Waste Waste Control Control Valve, Valve, indicates indicates shut.

shut.

-- Within 30 Within 30 seconds seconds of ofthe the alarm, alarm RM-L5's

, RM-L5s reading reading returns returns toto below below thethe setpoint.

setpoint.

Which ONE Which ONE of of the the following following correctly correctly states states the the next next procedure procedure steps steps toto be be taken.

taken.

A. The A." The tank tank must must be be sampled sampled and and activity activity levels levels verified, verified, then then open open RCV0001B-WL RCV00018-WL and and resume the resume release per the release per SOP-10B.

SOP-108.

B. Verify that B. Verify that the the RM-L5's RM-L5s reading reading isis below below thethe setpoint, setpoint, then then open open RCV0001B-WL RCV00018-WL and and resume the release per resume the release per SOP-1 OB.SOP-i 08.

C. Verify that C. Verify that the the RM-L5's RM-L5s reading reading is is below below thethe setpoint, setpoint, then then open open RCV0001B-WL RCV00018-WL and and resume the resume release per the release per SOP-1 SOP-108. Direct Heath OB. Direct Heath Physics Physics to to continue continue to to monitor monitor thethe release release and reduce and reduce the release rate.

the release rate.

Dv Notify Dy Notify Health Health Physics Physics andand request request aa radiological radiological survey.

survey. TheThe release release cancan not not be be reinitiated reinitiated under the current release under release permit.

permit.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

A CORRECT As per XCP-646-2-5, XCP-646-2-5, this is the first step of the supplemental supplemental actions.

B INCORRECT B INCORRECT This is the action if this is the first time the release has been automatically terminated.

INCORRECT C INCORRECT This is the action if this is the first time the release has been automatically terminated, ????coupled with the actions for a malfunctioni malfunctioning RM-L5. ????

ng RM-L5.????

D INCORREC D INCORRECT T This would be plausible if itit is believed that the release can not be continued.

continued.

REFERENC

REFERENCES:

ES:

1.

1. XCP-646 XCP-646 2-5 2-5 && 2-6, 2-6, pages pages 12 12 && 13.

13.

2. XCP-644 2-5,
2. XCP-644 2-5, page 15. page 15.
3. XCP-643
3. XCP-643 4-i, 4-1, page page 22.

22.

K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Liquid Liquid Radwaste Radwaste System; System; Ability to execute Ability to execute procedure procedure steps.

steps.

Facility Facility POST POST EXAMEXAM comment comment resulted accepting two resulted inin accepting two answers answers for for this this question.

question. The The additional information provided additional information provided by by the the facility facility inin HPP-710 HPP-710 supports supports distractor distractor DD as as an an additional additional correct correct answer.

answer. Additionally Additionally,, this this additional additional answer answer was was not not identified identified by by the the facility facility during during the the examination examination review review andand validation validation activities.

activities. HPP-710 HPP-710 indicates indicates that that the the current current release release permit permit must must be be closed.

closed.

Categories Categories Tier:

Tier: 22 Group:

Group: 22 Key Word:

KeyWord: LIQUID RADW LIQUID RADWASTE ASTE Cog Level:

Cog Level: C/A(4.3/4.2)

C/A(4.3/4.2)

Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Reviewer:

AuthorlReviewer: RFA/SDR RF AlSDR

88. I03G2.1.30
88. 1 03G2. 1.30 002/2/I/CONTAINMENT 002/211 /CONTAfNMENT AlRLOCKIM AIRLOCKJM (3.9/3.4)/N/SM05301/SIFJEIRFNSDR (3.9/3 .4)/N1SM0530 1 /SIFJE/RFAISDR Plant conditions Plant conditions are are asas follows:

follows:

The unit

- The

- unit isis currently currently inin MODE MODE 4,4, with with temperature temperature and and pressure pressure increasing.

increasing.

- All major work

- All major work inside inside containment containment was was completed completed two two hours hours agoago and and there there are are NO NO personnel inside personnel inside thethe Reactor Reactor Building.

Building.

- An

- auxiliary operator An auxiliary operator has has just just called called toto report report that that the the red red indicating indicating light light above above the the Personnel Escape Airlock is LIT and Personnel Escape Airlock is LIT and that he was unablethat he was unable to to operate operate the the Fuel Fuel Handling Handling Building door Building door usingusing the the handwheel.

handwhee!.

Which ONE Which ONE of of the the following following isis correct correct regarding regarding the the status status of of the the Personnel Personnel Escape Escape Airlock Airlock AND Containment AND Containment Integrity?

Integrity?

A The A.v The Reactor Reactor Building Building door door isis OPEN.

OPEN.

The Personnel Escape The Personnel Escape Airlock is Airlock is INOPERABLE.

INOPERABLE.

B. The Reactor B. The Reactor Building Building door door is CLOSED.

is CLOSED.

The Personnel The Personnel Escape Escape Airlock Airlock isis INOPERABLE.

INOPERABLE.

C. Only the Reactor C. Reactor Building Building door position position indicator indicator has has malfunctioned.

malfunctioned.

The Personnel Escape Airlock is is OPERABLE.

OPERABLE.

D. The Personnel Escape Airlock is OPERABLE.

D. OPERABLE.

The Personnel The Personnel Escape Airlock door interlock is INOPERABLE. INOPERABLE.

Feedback Feedback Distractor Analysis Distractor A Correct.

A Correct. The red bulkhead light and the inability to operate door operating handle NO.4 No. 4 (after unlocking (after unlocking it) indicate that the remote (containment side) door is open. Per Tech Spec 3.6.1.3, Containment Air Locks, both airlock doors are required to be CLOSED in Mode 4 unless the air lock is being used for normal transit entry and exit. With NO personnel personnel in containment for two hours, the air lock is NOT being used for normal transit entry and exit.

BB Incorrect.

Incorrect. Incorrect equipment status, correct Tech Spec application. See A.

C.C. The The indicator indicator is is aa positive positive indication indication of of the status of of the the door.

door. The The door door isis open.

open. The The Personnel Personnel Escape Escape AirlockAirlock isis INOPERAB INOPERABLE. LE.

D.D. The The indicator indicator is is aa positive positive indication indication of of the the status status ofof the the door.

door. The The door door isis open.

open. The The Personnel Escape Airlock Personnel Escape Airlock is INOPERABLE.is INOPERABL E.

Reference:

Reference:

Technical Technical Specification Specification 3.6.1.3, 3.6.1.3, Containment Containment Air Air Locks Locks KJA KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTIDESCRIPTION: ON:

- 103 Containment

- 103 Containment System System

- G2.1 .30 Ability G2.1.30 Ability toto locate locate and and operate operate components, components, including including controls controls (3.9/3.4)

(3.9/3.4)

Categories Categories Tier:

Tier: 22 Group:

Group: 1 Key Word:

KeyWord: CONTAINMENTAIRLOCK CONTAINMENT AIRLOCK Cog Level:

CogLevel: MM(3.9/3.4)

(3.9/3.4)

Source:

Source: NN Exam:

Exam: SM05301 5M05301 Test:

Test: SS Author/Reviewer:

AuthorlReviewer: FJEIRF AlSDRR FJE/RFAJSD

89. G2.I.l3
89. G2.1.13002/3//ADMINIM 002/3//ADMINIM(2.0/2.9)/N/SM05301lSIRFAlSDR (2 .O/2.9)IN/SM0530 1 !S/RFAISDR Which ONE Which ONE of ofthe the following following (as (as stated stated inin SAP-200, SAP-200, Conduct Conductof ofOperations)

Operations) has has the the final final authority, per Management Directive 11, authority, per Management Directive 11, for aa case where for case where anan individual's individuals condition condition for forwork work inside the inside the protected protected areaarea isis inin question?

question?

A.A. General General Manager, Manager, Nuclear Nuclear Plant Plant Operations Operations BB.v Shift Supervisor

..... Shift Supervisor Management Duty c.C. Management Duty Supervisor Supervisor D. Security Manager D. Security Manager Feedback Feedback Distractor Analysis:

Distractor Analysis:

A. Incorrect:

A. Incorrect: per per SAPSAP 200, 200, Paragraph Paragraph 6.5.26.5.2 H, H, page page 1010 B. Correct: per B. Correct: per SAP SAP 200,200, Paragraph Paragraph 6.5.2 6.5.2 H, H, page page 1010 C. Incorrect: per C. Incorrect: per SAPSAP 200, 200, Paragraph Paragraph 6.5.26.5.2 H, H, page page 1010 D. Incorrect:

D. Incorrect: per per SAPSAP 200, Paragraph Paragraph 6.5.2 H, H, page page 1010

Reference:

Reference:

SAP 200, SAP 200, Conduct of Operations, Paragraph 6.5.2 H, page 10 KIA CATALOGUE QUESTION DESCRIPTION:

K/A CATALOGUE DESCRIPTION:

Knowledge of facility requirements for controlling vital/controlled

- Knowledge vital I controlled access.

Categories Categories Tier:

Tier: 33 Group:

Key KeyWord: Word: ADMN ADMIN Cog Level: M (2.0/2.9)

M Source:

Source: N N Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revi Author/Reviewer: RFAlSDR ewer: RFA/SDR

90. G2.1.34
90. G2.1.34 002/311CONDUCT 002/3//CONDUCT OF OF OPS/CIA(2.3/2.9)/B/SM0530l/SIMC/SDR OPS/C/A(2.3/2.9)/B/SM0530 1/S/MC/SDR The unit The unit isis undergoing undergoing aa normal normal heatup.

heatup. Plant Plant conditions conditions areare asas follows:

follows:

Hydrazine was

- Hydrazine was added added whenwhen RCSRCS temperature temperature was was 185°F.

185°F.

RCS temperature

- RCS temperature isis 200°F.

- 200° F.

- AA reactor

- reactor coolant coolant sample sample shows shows dissolved dissolved oxygen oxygen concentrations concentrations of of 1.1 1.1 ppm.

ppm.

Given the Given the above above conditions conditions and and inin accordance accordance with with GOP-2,"Plant GOP-2,Plant Startup Startup andand Heatup,"

Heatup, and and Tech Spec Tech 3.4.7, "Chemistry,"

Spec 3.4.7, Chemistry, which which ONEONE ofof the the following following isis correct?

correct?

A.A. Secure Secure the the Heatup, Heatup, plantplant chemistry chemistry isis NOT NOT inin compliance compliance with with GOP-2; GOP-2; an an LCO LCO HASHAS been been entered.

entered.

BB. Secure the

...... Secure the Heatup Heatup to to prevent prevent plant plant chemistry chemistry from NOT being from NOT being inin compliance compliance with with GOP-2; GOP-2; an LCO an LCO has has NOT NOT beenbeen entered.

entered.

C. The C. The heatup heatup cancan continue, continue, plant plant chemistry chemistry IS IS in in compliance compliance withwith GOP-2; GOP-2; an an LCO LCO HASHAS been been entered.

entered.

D. The heatup D. heatup can continue, plant plant chemistry IS IS in in compliance with GOP-2;GOP-2; an LCO LCO hashas NOT NOT been entered.

been Feedback Feedback DISTRACTORS:

DISTRACTORS:

INCORRECT A INCORRECT Per GOP-2, RCS temperature should not be permitted to exceed 200°F until oxygen scavenging of the primary is complete and chemistry is within specification specification..

B CORRECT Per GOP-2, RCS temperature should not be permitted to exceed 200°F until oxygen scavenging of the primary is complete and chemistry is within specification specification.. Although the Steady State Limit for Oxygen is 0.lppm 0.1 ppm in Modes 11 - 4, it is not applicable with Tavg ~

- 250°F

< 250°F (per

  • note below Table 3.4-2).

CC INCORREC INCORRECT T Plant Plant temperature has has exceeded the GOP-2 GOP-2 limit limit of 200°F 200°F but but not not the TS TS limit limit ofof 250°F.

250°F.

DD INCORREC INCORRECT T Plant Plant temperature has has exceeded exceeded the the GOP-2 GOP-2 limit limit of of 200°F.

200°F.

REFERENC

REFERENCES:

ES:

1. Tech
1. Tech SpecSpec Table Table 1.1,1.1, Operational "Operational Modes.

Modes."

2.

2. Tech Tech SpecSpec 3.4.7, 3.4.7, Chemistry, "Chemistry," and and Table Table 3.4-2, 3.4-2, Chemistry "Chemistry Limits.

Limits."

2:

2. GOP-2,Plan GOP-2,"Plantt StartupStartup and and Heatup Heatup (Mode (Mode 55 to to Mode Mode 3), Step 2.la 3)," Step 2.1a page page 2, 2, Step Step 3.1 3.1 page page 5, 5,

&& the Reference the Reference Page. Page.

KIA CATALOGU K/A CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Ability Ability to to maintain maintain primary primary and and secondary secondary plant plant chemistry chemistry within within allowable allowable limits.

limits.

Categories Categories Tier:

Tier: 33 Group:

Group:

Key KeyWord: Word: CONDUCT CONDUCT OF OF OPS OPS Cog Cog Level:

Level: CIA(2.3/2.9)

C/A(2.3/2.9)

Source:

Source: BB Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Reviewer: MC/SDR AuthorlReviewer: MC/SDR

91. G2.2.20 OO1l31ITROUBLESHOOTINGIM2.2/3.3IMISM05301lSIFJE/SDR
91. G2.2.20 001 /3//TROTJBLESHOOTING/M2.2/3 .3/M/SM0530 I /S/FJE/SDR Which ONE Which ONE of of the the following following isis aa VIOLATION VIOLATION of administrative procedures of administrative procedures whenwhen troubleshooti ng an INOPERABL E system troubleshooting an INOPERABLE system or component, or component, the condition of the condition of which which isis specified specified by by aa Technical Technical Specification Specification Action Action Statement.

Statement.

A AA Temporary A:" Temporary Restoration Restoration to Service isis used to Service used even even though though an alternative method an alternative method of of completing the completing the work work that that will will meet meet the the action action statement statement requirement requirement waswas identified.

identified.

B.B. The The troubleshooting troubleshooting requires requires posting posting aa plant plant operator operator to immediately restore to immediately restore an an affected affected component.

component.

C. The Temporary C. The Temporary Inoperable Inoperable Status Status Change Change required required toto perform perform the the troubleshooting troubleshooting was was approved by approved by thethe Duty Duty Shift Shift Supervisor.

Supervisor.

D. The D. The Work Work Document Document also also includes includes an an approved approved Bypass Bypass Authorization Authorization Request Request to to install install electrical electrical jumpers.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

A Correct per SAP-205, 6.7.2.B B Incorrect. Acceptable per 6.7.3.A.1. and 6.7.3.A.2. Plausible if applicant believes that immediately restore" the need to "immediately restore would prevent a troubleshooting troubleshooting activity.

C Incorrect. SAP-205, Attachment V, Temporary Inoperable Status Change, requires approval by the Duty Shift Supervisor. Plausible because the Manager, Operations, approves some plant activities (e.g. extending the time an invalid nuisance annunciator may be removed from service).

D Incorrect. Allowed per SAP-0148 section 2.2. Plausible if applicant believes a Bypass Authorizatio Authorization n Request is not used to authorize installation of electrical jumpers or that administrativ administrative e procedures prohibit the use of electrical jumers during troubleshoot troubleshooting.ing.

REFERENC

REFERENCES:

ES:

1.

1. SAP-0205, Status Control and Removal and Restoration
2. SAP-0148, Temporary Bypass, Jumper, and Lifted Lead Control KIA CATALOGU K/A CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- Knowledge of the process for managing managing troubleshoot troubleshootinging activities (2.2/3.3)

Categories Tier:

Tier: 33 Group:

Group:

Key Word:

KeyWord: TROUBLES HOOTfNG TROUBLESHOOTING Cog Cog Level:

Level: M2.2/3.3 M2.2/3.3 Source:

Source: MM Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revi AuthorlReviewer: FJE/SDR ewer: FJE/SDR

92. G2 .2.7 001l311EQUIPMENT
92. G2.2.7 001/3//EQUIPMENT CONTROLlM(2.0/3.2)/B/SM05301/S/MC/SDR CONTROL/M(2.0/3 .2)/B/SM0530 1/S/MC/SDR AA bypass bypass authorization authorization request, request, prepared prepared per per SAP-148, SAP-i 48, "Temporary Temporary Bypass, Bypass, Jumper, Jumper, and and Lifted Lead Control,"

Lifted Lead Control, requires requires prior prior PSRC PSRC and and NSRC NSRC review review for which ONE for which ONE ofof the the following following conditions?

conditions?

A. AA review A. review indicates indicates that that system system operability operability will will be be affected.

affected.

B. AA review B. review indicates indicates that that 10 10 CFR CFR 50 50 Appendix Appendix RR fire fire protection protection criteria criteria are are impacted.

impacted.

C. review indicates C. AA review indicates that Seismic or that Seismic or blowout blowout provisions provisions areare being being diminished.

diminished.

Dy review indicates Dy AA review indicates that that aa full safety evaluation full safety evaluation isis required required per 10 CFR per 10 CFR 50.59.

50.59.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

INCORRECT A INCORRECT B INCORRECT INCORRECT C INCORRECT C INCORRECT D CORRECT D CORRECT

REFERENCES:

REFERENCES:

1. SAP-148,
1. SAP-i 48, "Temporary Temporary Bypass, Jumper, and Lifted Lead Control." Control. Attachment 1, page 14 of 20.

KIA CATALOGUE QUESTION DESCRIPTION:

K/A CATALOGUE DESCRIPTION:

- Knowledge of the process for conducting tests or experiments not described in the safety analysis report.

analysis report.

Categories Tier:

Tier: 33 Group:

Key Word:

KeyWord: EQUIPMEN EQUIPMENT T CONTROL Cog Level: M(2.0/3.2)

Source:

Source: BB Exam: SM05301 Test:

Test: SS Author/Revi ewer: MC/SDR AuthorlReviewer:

93. G2.3.2
93. G2.3 .2 002/3///M(2.5/2.9 002/3///M(2.5/2.9)/N/SM 0530 1/SIRFA!SDR

/N/SM0530l/S/RFAlSDR Which ONE Which ONE of of the the following following isis correct correct per per HPP-HPP- 709, 709, Sampling Sampling and and Release Release ofof Radioactive Radioactive Gaseous Effluents:

Gaseous Effluents:

A. Discharges Aol Discharges from from the Waste Gas the Waste Gas Decay Decay Tank Tank or or other other high high activity activity gaseous gaseous releases releases should should be avoided when the wind is from the East-Southea be avoided when the wind is from the East-Southeast. st. This will prevent This will prevent the the released released activity activity from being from being drawn drawn into into the Auxiliary Building the Auxiliary Building ventilation.

ventilation.

B.B. Discharges Discharges from from the the Waste Waste Gas Gas Decay Decay Tank Tank or or other other high high activity activity gaseous gaseous releases releases should should be avoided when be avoided when thethe wind wind isis from from the the West-Southwest.

West-Southwest. This This will will prevent prevent the the released released activity from activity from being being drawn drawn into into the the Auxiliary Auxiliary Building Building ventilation.

ventilation.

C. Discharges C. Discharges from the the Waste Gas Gas Decay Decay Tank Tank or or other other high high activity activity gaseous gaseous releases releases should should be avoided be avoided when when thethe wind wind isis from from the the East-Southeast.

East-Southeast. This This will will prevent prevent the the released released activity activity from being from being drawn drawn intointo the the Control Control Building Building ventilation.

ventilation.

D. Discharges D. Discharges from from the Waste Gas Gas Decay Decay Tank or other high high activity gaseous releases releases should be avoided when the wind is is from the West-Southwest.

West-Southwest. This This will prevent prevent the released the released activity from being drawn into activity into the Control Control Building Building ventilation.

Feedback Distractor Analysis:

Correct: Discharges A: Correct: Discharges from the Waste Gas Decay Tank or other high activity gaseous releases gaseous releases should be avoided when the wind is from the East-Southeast. This will prevent the released activity from being East-Southeast.

drawn into drawn into the Auxiliary Building ventilation. Per HPP-709 NOTE 5.1.H B, C, B, C, D Incorrect D Incorrect

Reference:

Reference:

HPP-HPP- 709, Sampling Sampling and Release of Radioactive Gaseous Effluents, page 10 10 KIA CATALOGU K/A CATALOGUE E QUESTION DESCRIPTIDESCRIPTION: ON:

- Knowledge of of facility ALARA ALARA program.

program.

Categories Tier:

Tier: 33 Group:

Group:

Key Word:

KeyWord: Cog Cog Level:

Level: M(2.5/2.9)

M(2.5/2.9)

Source:

Source: N N Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revie wer: RFAJSDR AuthorlReviewer: RFAlSDR

94. G2.4.33
94. G2 .4.33 002/311INOPERABLE 002/3//iNOPERABLEALARMIM2.4/2.8/B/SM05301lSIFJE/SDR ALARM/M2.4/2 8/B/SM0530 I /S/FJE/SDR Which ONE Which ONE of of the the following following individual's individuals approval approval isis required required to to extend extend the the time time that that an an invalid invalid nuisance annunciator isis removed nuisance annunciator removed from from service service past past 96 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />?

hours?

A. Duty A. Duty Shift Shift Engineeer Engineeer B. Duty Shift

8. Duty Shift Supervisor Supervisor Manager, Operations C Manager, Cy Operations D. General Manager, D. General Manager, Nuclear Nuclear Plant Plant Operations Operations Feedback Feedback DISTRACTORS:

DISTRACTORS:

A A

B B

C Correct per C Correct per OAP-100.5, CAP-i 00.5, Section Section 14.0 14.0 D

D

REFERENCES:

REFERENCES:

1.

1.

K/A CATALOGUE KIA CATALOGUE QUESTION DESCRIPTION: DESCRIPTION:

Knowledge of the process used to track inoperable alarms.

- Knowledge Categories Categories Tier:

Tier: 33 Group:

Key Word:

KeyWord: INOPERAB INOPERABLE LE ALARM Cog Level: M2.4/2.8 Source:

Source: B Exam: SM05301 Test:

Test: SS Author/Revi AuthorlReviewer:

ewer: FJE/SDR

95. G2.4.38
95. G2.4.38 002/311EMERGENCY 002/3//EMERGENCY PROCEDURESIM(2.2/4.0)IMISM05301lSIMC/SDR PROCEDURESJM(2 .2/4.0)/M/SM0530 1/S/MC/SDR Plant conditions Plant conditions are are as as follows:

follows:

  • An event An event hashas occurred occurred resulting resulting inin substantial substantial core core degradation degradation with with potential potential loss of loss of containment containment integrity.

integrity.

  • AA General General Emergency Emergency has has been been declared.

declared.

  • The prevailing wind is blowing The prevailing wind is blowing from the from the south.

south.

Which ONE Which ONE of of the following must the following must assume assume thethe duties duties of of Interim Interim Emergency Emergency Director, Director, and and to to which area which area should should he direct non-essential he direct non-essential personnel personnel be be evacuated?

evacuated?

A. Shift A. Shift Supervisor; Supervisor; Evacuate Evacuate to to their their personal personal residence.

residence.

BB.% Shift Supervisor;

..... Shift Supervisor; Evacuate Evacuate to to the the Southern Southern Offsite Offsite Holding Holding Area.

Area.

C. Manager, Operations; C. Manager, Operations; Evacuate Evacuate to to their personal personal residence.

residence.

D. Manager, Operations:

D. Manager, Operations: Evacuate Evacuate to to the the Southern Southern Offsite Offsite Holding Holding Area.

Area.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

A INCORRECT A INCORRECT Correct individual; however, if there is a potential for personnel or vheicle contamination, the evacuation would NOT be to peronal residence.

contamination, B CORRECT B CORRECT C INCORRECT C INCORRECT If there is a potential for personnel or vheicle contaminatio contamination, n, the evacuation would NOT be to peronal residence.

D D INCORREC INCORRECT T REFERENC

REFERENCES:

ES:

1.

1. SAP-109, Managemen "Managementt Duty Supervisor.

Supervisor."

2. EPP-012, Onsite Personnel
2. EPP-012, "Onsite Personnel Accountability Accountabili ty and and Evacuation, Evacuation," pages pages 55 and and 9.

9.

KIA CATALOGU K/A CATALOGUE E QUESTION QUESTION DESCRIPTIDESCRIPTION: ON:

- Ability Ability to to take take actions actions called called forfor in in the the facility facility emergency emergency plan, plan, including including (if (if required) required) supporting supporting or or acting acting asas emergcy emergency coordinator.

coordinator.

Categories Categories Tier:

Tier: 33 Group:

Group:

Key KeyWord: Word: EMERGENC EMERGENCY Y PROCEDUR PROCEDURES ES Cog Cog Level:

Level: M(2.2/4.0)

M(2.2/4.0)

Source:

Source: MM Exam:

Exam: SM05301 5M05301 Test:

Test: SS Author/Revi AuthorlReviewer:

ewer: MC/SDR MC/SDR

96. W/E02EG2.4.6
96. W/EO2EG2 .4.6 OOl/l/2/SI 001/1/2/SITERMINATION/CIA(3.1/4.0)INISM05301/S/FJE/SDR TERMINATION/C/A(3.1 /4.0)/N/SM0530 I /S/FJE/SDR Plant conditions Plant conditions areare as as follows:

follows:

- AA reactor

- reactor trip and SI trip and SI have occurred due have occurred due toto aa steam steam break.

break.

- ALL

- ALL Main Main Steam Steam Isolation Isolation Valves Valves initially initially failed failed to to close.

close.

EOP-3.1, Uncontrolled

- EOP-3.1,

- Uncontrolled Depressurization Depressurization of of All All Steam Steam Generators, Generators, isis inin progress progress at at Step Step 17, 17, Establish Normal Establish Normal Charging.

Charging.

- PZR

- PZR level level isis 58%.

58%.

- EFW flowrate

- EFW flowrate isis 50 50 gpm gpm to each Steam to each Steam Generator Generator due due to to required required operator operator action.

action.

All Steam Generator Narrow

- All Steam Generator

- Narrow Range Range levels levels areare 4%.

4%.

Reactor Building

- Reactor

- Building pressure pressure has has remained remained belowbelow 11 psig.

psig.

- RCS

- RCS pressure pressure isis 1750 1750 psig and going psig and going UP.

UP.

- Core

- Exit TCs Core Exit TCs areare 435 435 OF °F and going DOWN.

and going DOWN.

The "c" The Main Steam C Main Steam Isolation Isolation Valve Valve closed closed 30 30 seconds seconds ago and "c" ago and C Steam Steam Generator Generator pressure pressure has changed has changed from 80 80 to 130130 psig.

psig.

Which ONE ONE of the following following correctly correctly describes describes the actions actions the the crew crew should should take?

take?

A. Must remain in EOP-3.1 until the Critical Safety Function A. Function Status Trees direct entering an orange or red path Emergency Operating Procedure.

IMMEDIATELY transition to EOP-3.0, Faulted Steam Generator Isolation, Step 1.

B. IMMEDIATELY Cv C ..... Complete EOP-3.1 thrQugh through Step 20, verify SI Flow is NOT required, and then transition to to EOP-3.0, Faulted Steam Generator Isolation, Step 1.

D. Complete ALL steps of EOP-3.1 and then transition to EOP-1.2, Safety Injection D.

Termination, Step 1.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

AA Incorrect.

Incorrect. The The CC SGSG pressure pressure has has increased.

increased. Per Per EOP-3.1 EOP-3.1 Reference Reference Page Page item item 2,2, Secondary Integrity Secondary Integrity Transition Transition Criteria, Criteria, the the crew crew should should go go to to EOP-3.0, Faulted Steam EOP-3.0, Faulted Steam Generator Isolation, Step 1, after completing Generator Isolation, Step 1, after completing EOP-3.0 SI EOP-3.0 SI Termination Termination steps steps 15 15 through through 20.

20.

Plausible ifif applicant Plausible applicant does does notnot recognize recognize secondary secondary integrity integrity transition transition criteria.

criteria.

Incorrect. Per BB Incorrect. Per EOP-3.1, EOP-3.1, Reference Reference Page Page item item 2,2, the crew should the crew should go go to to EOP-3.0 EOP-3.0 ifif any any SG SG pressure pressure increases increases at any time at any time EXCEPT EXCEPT while while performing performing SI SI Termination Termination inin steps steps 1515 through through 20.20. Plausilbe Plausilbe ifif applicant applicant does does not recognize step not recognize step number number or or step step description description as an as an SI SI Termination Termination stepstep oror does does notnot remember remember an an exception exception to to Secondary Secondary Integrigy Integrigy Transition Critierion.

Transition Critierion.

CC Correct Correct per EOP-3.1, Reference per EOP-3.1, Reference Page, Page, item item 2,2, Secondary Secondary Integrity Integrity Transition Transition Criterion.

Criterion.

D Incorrect. Per D Incorrect. Per EOP-3.1 EOP-3.1 Reference Reference Page, Page, item item 2,2, the crew crew should transition to to EOP-3.0 EOP-3.0 after completing SI Termination in Steps after completing SI Termination in Steps 15 through 15 through 20.20. Plausible Plausible because because the the last last step step of of EOP-3.0, Faulted EOP-3.0, Faulted Steam Steam Generator Generator Isolation, Isolation, directs a transition to EOP-1.2.EOP-1 .2.

REFERENCES:

REFERENCES:

1. EOP-3.1, Uncontrolled Depressurization
1. Depressurization of All Steam Generators
2. EOP-3.1 EOP3. 1 LP, Uncontrolled Depressurization Depressurization of All Steam Generators Lesson Plan K/A CATALOGUE KIA CATALOGUE QUESTION DESCRIPTION: DESCRIPTION:

- W/E02 SI Termination Knowledge symptom based EOP mitigation strategies (3.1/4.0).

- Knowledge Categories Tier: 1 Group: 22 Key KeyWord:Word: SI TERMINAT TERMINATION ION Cog Level: CIA(3 .114.0)

C/A(3.l/4O)

Source:

Source: N Exam: SM05301 Test:

Test: SS Author/Revi AuthorlReviewer:

ewer: FJE/SDR

97. W/EOSEA2.1
97. W/EO5EA2. 00 001/1/1/HEA 1111 1IHEATT SINK/CIA SNKJC/A (3.4/4.4)/B/SMOS30IlS/GWLIRFAlSDR (3 .4/4.4)/B/SM0530 1/S/GWL/RFAJSDR The Crew The Crew has entered EOP-16.0 has entered EOP-16.0 "Response Response to Pressurized Thermal to Pressurized Thermal Shock" Shock duedue to to an an Orange Orange pathpath on the integrity on the integrity CSF CSF status status tree.

tree. The The Crew Crew isis at at the the step step for for Checking Checking RCS RCS Tcold Tcold Stable or Stable or Increasing.

Increasing.

While checking While checking EFW EFW flowflow itit isis determined determined that Red path that aa Red path condition condition exists exists on on the the Heat Heat Sink Sink CSF status tree.

CSF status tree.

Which ONE Which ONE of of the the following following correctly correctly describes describes thethe action action that that should should bebe taken taken byby the the crew?

crew?

A. Remain A. Remain in in EOP-16.0 EOP-16.O untiluntil itit isis completed, completed, then then transition transition toto EOP-1S.0, EOP-15.0, Response Response to to Loss Loss of of Secondary Heat Secondary Heat Sink.

Sink.

B. Remain in B. Remain EOP-16.0 until in EOP-16.0 until the OrangeOrange path path is is cleared, cleared, then then tranistion tranistion to to EOP-1S.0.

EOP-15.O.

CY' IMMEDIATELY transition C IMMEDIATELY transition to EOP-15.0.

to EOP-1S.0.

D. The transition to EOP-1S.0 D. EOP-15.0 is is NOT NOT required required since EOP EOP 16.0 provides actions for adjusting 16.0 provides E FW.

EFW.

Feedback DISTRACTORS:

DISTRACTORS:

A Incorrect, a red path exists for heat sink and it has priorty over integrity, the operator should tranistion immediately.

immediately.

B Incorrect, a red path exists for heat sink and it has priorty over integrity, the operator should immediately.

tranistion immediately.

C Correct, the operator should transition to EOP-1S.0 EOP-15.0 immediately.

immediately.

D D Incorrect, aa red path exists for heat sink and it has priorty over integrity, the operator should tranistion immediately.

immediately. EOP-1S.0 EOP-15.0 has a caution that states:

If total EFW flow is LESS THAN 450 4S0 gpm due to operator action, this procedure should NOT be performed, since these actions are NOT appropriate if 450 4S0 gpm EFW flow is available.

The stem does not support this and EOP-1 EOP-1S.05.0 must be transitioned to for this CAUTION to apply.

REFERENC

REFERENCES:

ES:

1.

1. EOP-EOP- 15.0, 1S.0, 16.0, 16.0, 12.0.

12.0. Summer Summer Exam Exam bank bank question question EOPS EOPS 385. 38S.

K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

WEO5EA2.1 WEOSEA2.1 Ability Ability to to operate operate and and I1oror monitor monitor the the folowing folowing as as they they apply apply toto the the (Loss (Loss ofof Secondary Secondary Heat Heat Sink)

Sink) Facility Facility conditions conditions and and selection selection of of appropriate appropriate procedures procedures during during abnormal abnormal and and emergency emergency operations.

operations. (3.4/4.4) (3.4/4.4)

Categories Categories Tier:

Tier: I Group:

Group: 1I Key Word:

KeyWord: HEAT SINK HEAT SINK Cog Level:

Cog Level: CIA C/A (3.4/4.4)

(3.4/4.4)

Source:

Source: BB Exam:

Exam: SM0530 SM05301 1 Test:

Test: SS Author/Reviewer:

AuthorlReviewer: GWLlRF GWL/RFAJSAlSDRDR

98. W/E09EA2.2
98. W/EO9EA2.2 OOll112!NATURAL 001 / 1 /2/NATURALCIRCIC/A(3.4/3.8)IMISM05301lS/GWLlSDR CIRC/C/A(3 .4/3. 8)/M/SM0530 1/S/GWL/SDR AA Reactor Reactor TripTrip with with aa loss loss of Off-site power of Off-site power hashas occurred.

occurred. Power Power willwill not not be be restored restored for for atat least eight hours, and least eight hours, and aa cooldown cooldown isis desired.

desired.

RCS temperature

- RCS

- temperature isis currently currently 557 557 of°F Only one

- Only

- CRDM fan one CRDM fan isis operable.

operable.

Which ONE Which ONE of the following of the following correctly correctly describes describes the actions to the actions to be be taken taken inin accordance accordance with with EOP-1 .3 Natural Circulation EOP-1.3 "Natural Circulation Cooldown"? Cooldown?

A. Reduce A. Reduce RCSRCS pressure pressure to below 1925 to below 1925 psig, psig, maintain maintain RCS RCS subcooing subcooing greater greater than than 80 80 of,

°F, cooldown shall cooldown shall not not exceed exceed 50 50 of/hr.

°F/hr.

B. Maintain B.",; Maintain RCS RCS pressure pressure aboveabove 1925 1925 psig, psig, maintain maintain RCSRCS subcooling subcooling greater greater than than 130 130°F of and cooldown cooldown shall not not exceed 50 of/hr.F/hr.

0 Reduce RCS C. Reduce RCS pressure to below below 1925 1925 psig, maintain RCS subcooing greater than 130 130 of,°F, cooldown shall not exceed 25 of/hr. °F!hr.

D. Maintain RCS pressure above 1925 psig, maintain RCS subcooling greater than 80 80°Fof and cooldown shall not exceed 25 of/hr. °F/hr.

Feedback DISTRACTORS:

DISTRACTORS:

A Incorrect, RCS pressure should not be reduced, subcooling must be greater than 130 130°F.0 F.

BB Correct, RCS pressure should be maintained above 1925, 1925, subcooling must be greater than 130°F, 0

130 F, and cooldown is limited to 50F 0 0 50/hr.

F/hr.

CC Incorrect, Incorrect, RCS pressure should not be reduced, subcooling must be greater than 130 130 °F,of, and the cooldown and the cooldown is is limited limited toto 50 50 °F/hr.

of/hr.

DD Incorrect, Incorrect, the cooldown is is limited limited to 50 0 to 50 F /hr.

of/hr.

REFERENC

REFERENCES:

ES:

1.

1. EOP-1 EOP-1.3 .3 Natrual Natrual Circulation Circulation Cooldown.

Cooldown.

K/A KIA CATALOGU CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

WEO9EA2.2 WE09EA2.2 Ability Ability to to operate operate and or monitor and // or the following monitor the following as as they they apply apply toto the the (Natural (Natural Circulation Operations)

Circulation Operations) Adherence Adherence to to appropriate appropriate procedures procedures and and operation operation within within the the limits limits inin the the facilityss facilitys's license license and and amendments amendments. . (3.4/3.8)

(3.4/3.8)

Categories Categories Tier:

Tier: 1 Group:

Group: 22 Key Word:

KeyWord: NATURAL NATURAL CIRC CIRC Cog Cog Level:

Level: C/A(3.4/3.8)

C/A(3.4/3.8)

Source:

Source: M M Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revie AuthorlReviewer:

wer: GWLlSDR GWL/SDR

99. W/E12EG2.4.4
99. W/E 1 2EG2.4.4 0021111/STEAM 002/1/1/STEAM LINE LINE RUPTURE/C/A(4.014.3 RUPTURE/C/A(4.0/4.3)/N /SM0530 1/S/FJE/SDR

/N/SM05301lSIFJE/SDR Plant conditions Plant conditions are are as follows:

as follows:

The Unit

- The

- Unit experienced experienced aa Steam Steam Generator Generator Tube Tube Rupture Rupture (SGTR)

(SGTR) on on the the "8" B Steam Steam Generator (SG).

Generator (SG).

The crew

- The

- crew isis currently currently performing performing EOP-4.0, EOP-4.0, Steam Steam Generator Generator Tube Tube Rupture, Rupture, Step Step 3, 3,

Isolate flow from each RUPTURED Isolate flow from each RUPTURED SG. SG.

When the When the crew crew transitioned transitioned from from EOP-1.0 EOP-1 .0 to EOP-4.0, FOUR to EOP-4.0, FOUR (4)(4) minutes minutes ago, ago, plant plant parameters were parameters were asas listed listed below:

below:

Loop AA Loop Loop 8B Loop Loop Loop C C SG Pressure SG Pressure 800 psig 800 psig 1200 psig 1200 psig 800 psig 800 psig SG NR SG NR Level Level 40%

40% 80%

80% 45%

45%

SGPORV SG PORV SHUT SHUT OPEN OPEN SHUT SHUT RCS Temperature RCS Temperature 557 of 557 °F 556 556 of°F 557 557 of°F RCS Pressure: 1350 psig NOTE: ALL plant parameters were stable, with the exception of 8B SG NR Level, which was going UP.

CURRENT plant parameters are as follows:

CURRENT Loop A Loop 8 B Loop C SG Pressure 500 psig 1050 psig 750 psig SG NR Level 20% 85% 45%

SGPORV SG PORV SHUT SHUT SHUT RCS Temperature 520 °Fof 550 °Fof 550 °Fof RCS Pressure: 1000 1000 psig ALL above parameters are are all all decreasing (going (going DOWN),

DOWN), withwith Loop Loop A parameters decreasing faster than Loops Loops B8 and and C.

Which ONE ONE ofof the the following correctly describes describes thethe NEXT NEXT action action the the crew crew should should take take in in accordance accordance with with Emergency Emergency Operating Operating Procedures?

Procedures?

A. IMMEDIAT A. IMMEDIATELY ELY go to EOP-2.0, go to EOP-2.0, Loss Loss of of Reactor Reactor or or Secondary Secondary Coolant.

Coolant.

B B.II IMMEDIAT IMMEDIATELY ELY go go to to EOP-3.0, EOP-3.0, Faulted Faulted Steam Steam Generator Generator Isolation.

Isolation.

C. RETURN C. RETURN to to EOP-4.0, EOP-4.0, Steam Steam Generator Generator Tube Tube Rupture, Rupture, Step Step 1.1.

D. COMPLETE D. COMPLETE EOP-4.0, EOP-4.0, Step Step 33 and and THEN THEN gogo toto EOP-3.0, EOP-3.0, Faulted Faulted Steam Steam Generator Generator Isolation.

Isolation.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

AA Incorrect.

Incorrect. Plausible Plausible ifif applicant applicant believes believes aa LOCALOCA isis now now inin progress.

progress. AA LOCA LOCA would would bebe indicated by indicated by decreasing decreasing RCS RCS pressure pressure and and Loop Loop BB SG SG pressure ONLY, NOT a large pressure ONLY, NOT a large decrease inin Loop decrease Loop AA SG SG pressure, pressure, level, level, and and RCSRCS temperature.

temperature.

BB Correct Correct per EOP-4.0, Reference per EOP-4.0, Reference Page, Page, Secondary Secondary Integrity Integrity Transition Transition Criteria Criteria C Incorrect. Plausible C Incorrect. Plausible because because this this isis item item 44 (Multiple (Multiple Tube Tube Rupture Rupture Criteria)

Criteria) on on the the EOP-4.O reference EOP-4.0 reference page.

page.

DD Incorrect.

Incorrect. EOPEOP rules rules of usage require of usage require immediate immediate transition transition after after performing performing applicable applicable immediate actions. EOP-4.0 immediate actions. EOP-4.0 doesdoes not not contain contain anyany immediate immediate actions. Plausible ifif actions. Plausible applicant believes applicant believes that that completely completely isolating isolating thethe ruptured ruptured SGSG is is aa higher higher priority priority than than isolating the isolating faulted SG.

the faulted SG.

REFERENCES:

REFERENCES:

1. EOP-4.0,
1. EOP-4.0, Steam Generator Generator Tube Tube Rupture, Rupture, Reference Page, Page, item item 2, Secondary Integrity Integrity Transition Criteria.

Emergency Operating Procedures.

2. EO-2, Usage of Emergency Procedures.

KIA CATALOGUE QUESTION DESCRIPTION:

K/A CATALOGUE DESCRIPTION:

- W/E12 Steam Line Rupture -

- Excessive Heat Transfer

- G2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures (4.0/4.3).

entry-level Categories Categories Tier: 1 Group: 11 Key Word:

KeyWord: STEAM LINE RUPTURE Cog Level: CIA(4.0/4.3)

C/A(4.O/4.3)

Source:

Source: N Exam: SM0530 1 SM05301 Test:

Test: SS Author/Revi AuthorlReviewer: FJE/SDR ewer: FJE!SDR

1 00.W/E13EG2.2.25 100. W/E1 3EG2.2.2500ll1l2/S/G 00 1/1/2/S/GOVERPRESSUREIM2.5/3.7/N/SM05301lSIFJE/SDR OVERPRESSURE/M2.5/3.7/N/SM0530 1/SIFJE/SDR Which ONE Which ONEofofthe thefollowing following describes describesthe thebasis basisforforreducing reducingthe thePower PowerRange Range Neutron Neutron FluxFlux High Trip Setpoint, in accordance High Trip Setpoint, in accordance with with Summer SummerTechnical Technical Specification SpecificationTableTable3.7-1, 3.7-1, ififone oneor or more main more main steam steam lineline code codesafety safetyvalves valves are are inoperable inoperablefor formore morethanthan 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br />?

hours?

A.v To A.II To ensure ensure that thatsufficient sufficient relieving relieving capacity capacityisis available availabletoto limit limit secondary secondarysystem system pressure pressure to within 110% of design to within 110% of design pressure. pressure.

B.B. To To minimize minimize the the positive positive reactivity reactivity effects effects ofofthe the Reactor Reactor Coolant Coolant System System cooldown cooldown associated with associated with the the blowdown blowdown of of the the INOPERABLE INOPERABLE safety safety valve(s).

valve(s).

C.C. To To limit limit the pressure rise the pressure rise within within the the reactor reactor building building to to within within thethe values values assumed assumed inin thethe accident analysis in the event of a steam line accident analysis in the event of a steam line rupture within rupture within the the reactor reactor building.

building.

D.D. To To ensure ensure thatthat pressure pressure induced induced stresses stresses inin the the steam steam generator generator with with the the INOPERABLE INOPERABLE safety valve(s) do safety valve(s) do not not exceed exceed the the maximum maximum allowable allowable fracture fracture toughness toughness stress stress limits.

limits.

Feedback Feedback DISTRACTORS:

DISTRACTORS:

A Correct A Correct per per Summer Summer Technical Specification Specification Bases 3/4.7.1.1, 3/4.7.1.1, page page B B 3/4 3/4 7-1, 7-1, paragraph paragraph 2. 2.

BB Incorrect.

Incorrect. Plausible because this is part of the basis for the operability of MSIVs and FWIVs.

FWIVs.

C Incorrect.

C Incorrect. Plausible because this is part of the basis for the operability of the MSIVs and FWIVs.

and FWIVs.

D Incorrect.

D Incorrect. Plausible Plausible because this is the basis for the Steam Generator Pressure I/

Temperature Temperature limitiation (3.7.2). Fracture toughness (brittle fracture) is not a concern at at NOP/NOT.

NOP/NOT.

REFERENC

REFERENCES:

ES:

1. SummerTech
1. Summer Technical nical Specification Bases Bases 3/4.7.1.1, 3/4.7.1.1, 3/4.7.1.5, 3/4.7.1.5, 3/4.7.1.6, 3/4.7.1.6, 3/4.7.2 3/4.7.2 KJA CATALOGU K/A CATALOGUE E QUESTION QUESTION DESCRIPTI DESCRIPTION: ON:

- W/E 13

- W/E 13 Steam Steam Generator Generator Over-pressur Over-pressure. e.

G2.2.25 G2.2.25 Knowledge Knowledge of of bases bases inin technical technical specification specifications s for for limiting limiting conditions conditions for for operations operations and safety limits (2.5/3.7).

and safety limits (2.5/3.7).

Categories Categories Tier:

Tier: 1 Group:

Group: 22 Key Word:

KeyWord: S/G S/G OVERPRES OVERPRESSURE SURE Cog Cog Level:

Level: M2.5/3.7 M2.5/3.7 Source:

Source: NN Exam:

Exam: SM05301 SM05301 Test:

Test: SS Author/Revi AuthorlReviewer:

ewer: FJE/SDR FJE/SDR

Final Submittal (Btue Paper)

(Slue FINAL SRO WRITTEN EXAMINATION 2/9/06

VC Summer Nuclear Plant 2005-301 SRO Inital Exam

76. 002A2.04 001 A large LOCA has occurred. Which ONE of the following actions are corrrect given the following conditions:
  • RWST level is 17% and continues to decrease.
  • RHR sump level is 410 feet and increasing.
  • All RCPs were tripped (by procedure) when RCS pressure dropped below 1400 psig
  • The crew is currently performing the actions of EOP-2.0, LOSS OF REACTOR OR SECONDARY COOLANT The following EOPs are being considered:
  • EOP-2.2, TRANSFER TO COLD LEG RECIRCULATION
  • EOP-2.4, LOSS OF EMERGENCY COOLANT RECIRCULATION Transition to:

A. EOP-2.4 from EOP-2.0. When RHR sump level reaches the required level, transition to EOP-2.2.

B. EOP-2.4 from EOP-2.0. When RHR sump level reaches the required level, return to EOP-2.0 and transition to EOP-2.2.

C. EOP-2.2 from EOP-2.0 then transition to EOP-2.4. When RHR sump level reaches the required level, return to EOP-2.0 and transition to EOP-2.2.

D9 D ..... EOP-2.2 from EOP-2.0 then transition to EOP-2.4. When RHR sump level reaches the required level, transition back to EOP-2.2.

Summer Nuclear VC Summer Nuclear Plant Plant 2005-301 SRO SRO Inital Inital Exam Exam

77. 003A2.03
77. 003A2.03 002002 The following conditions The conditions exist:

exist:

- Reactor Power is 9%.

- A Total Loss of All Service Water has occurred.

Total Loss of Service Water,"

- AOP-117.1, "Total

- Water, has been entered.

- RCP temperatures are beginning to rise.

- Service Water can not be restored.

Which ONE of the following describes the action(s) the operators must take and the sequence of those actions (in accordance with AOP-117.1)?

A. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 11 -

A.>I -

DESCEND ING). Stop up to TWO RCPs. Isolate unnecessary CCW DESCENDING). COW loads, and ensure FS D/Gs. When an RCP motor bearing temperatures or lower seal water is aligned to the DIGs.

bearing temperature exceeds the specified limit, stop the affected RCP.

B. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1 1 -

DESCENDING). Isolate unnecessary CCW COW loads, and ensure FS is aligned to the DIGs.

Secure an RCP only if motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit.

C. Initiate a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1 1 -

DESCENDING). Stop at least TWO RCPs. Isolate unnecessary CCW COW loads, and ensure D/Gs. When the running RCP FS is aligned to the DIGs. ROP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, increase monitoring and continue pump operation until the unit is shutdown then stop the affected pump.

D. Stop ONE RCP. Initiate a a reactor plant shutdown per GOP-4B, POWER OPERATION (MODE 1 1 - DESCENDING). When an RCP motor bearing temperatures or lower seal water bearing temperature exceeds the specified limit, trip the reactor and stop the affected!

affected RCP.

VC Summer VC Summer Nuclear Nuclear Plant Plant 2005-301 SRO Inital 2005-301 SRO Inital Exam Exam

78. 005G2.1.27 005G2.1.27 001 001 Which ONE Which ONE of of the the following correctly correctly describes describes the the purpose purpose and and or or function (not (not all all inclusive) inclusive) of the RHR system and one of its Mode 4 Technical Specification requirements?

A. Hot Leg Recirculation, Refueling Cavity Cooling, Alternate Water supply to Reactor Building' Building Coolers, Pressurizer Relief Tank Cooling. RHR can be deenergized for up to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided that core outlet temperature is maintained at least 50°F below saturation temperature.

B. Cold Leg Recirculation, Hot Leg Recirculation, Simultaneous Cold Leg - Hot Leg Recirculation, Alternate Water supply to Reactor Building Coolers. RHR can be deenergized for up to 11 hour provided that core outlet temperature is maintained at least 10°F below saturation temperature.

100F C. Refueling Cavity Draining, Cold Overpressure Protection, Simultaneous Cold Leg - Hot Leg -

Recirculation, Pressurizer Relief Tank Cooling. RHR can be deenergized for up to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 50°F below saturation provided that core outlet temperature is maintained at least 500F temperature.

D D~ Cold Leg Recirculation, Refueling Cavity Draining, Cold Overpressure Protection, Cold Leg Injection. RHR can be deenergized for up to 1 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided that core outlet temperature 10°F below saturation temperature.

is maintained at least 100F

Summer Nuclear VC Summer Nuclear Plant Plant 2005-301 SRO Inital 2005-301 SRO Inital Exam Exam

79. 007A2.03
79. 007A2.03 002 002 Plant conditions are Plant are as as follows:

- The unit is in Cold Shutdown.

- The RCS is water solid with one train of RHR providing shutdown cooling:

- RHR letdown is in service with PCV-145 controlling RCS pressure in AUTO.

- ALL pressurizer PORV control switches are in AUTO.

- RCS temperature is 140 of.

- °F.

- PRT level is 78%.

- PRT pressure is 6 psig.

- PRT temperature is 95 of

- °F Assuming no operator action, a _____ will result in a pressure increase in the PRT and the crew can restore PRT parameters by _ _ _ _ _ __

A. A HIGH failure of PT-444, pressurizer pressure control channel transmitter.

Spraying down the PRT using reactor makeup water per SOP-1 SOP-i 01, Reactor Coolant System.

B.

B . . . Loss of air to HCV-142, LTDN FROM RHR.

SOP-i 08, Liquid Waste Processing Draining the PRT to the Recycle Holdup Tanks per SOP-108, System.

c.

C. A HIGH failure of PT-444, pressurizer pressure control channel transmitter.

Draining the PRT to the Recycle Holdup Tanks per SOP-108, SOP-i 08, Liquid Waste Processing System.

HCV-i42, LTDN FROM RHR.

D. Loss of air to HCV-142, Spraying down the PRT using reactor makeup water per SOP-1 SOP-i 01, Reactor Coolant System.

VC Summer Summer Nuclear PlantPlant Inital Exam 2005-301 SRO Inital Exam

80. 007EA2.01 002
80. 007EA2.01 At 50% power, the plant experienced a loss of BOTH runningrunning Main Main Feedwater Pumps Pumps with aa concurrent failure of the Reactor trip breaker A to open. The crew is performing the immediate FOP-i .0, "Reactor actions of EOP-1.0, Reactor Trip/Safety Injection Actuation."

Actuation.

Current plant conditions are as follows:

- The Integrated Plant Computer System has failed.

- SG LO-LO Level annunciators are lit.

- Reactor Power is 7% and slowly decreasing.

FFW Pumps failed to start.

- All EFW Which ONE of the following describes the procedure path based on the above information?

A. FOP-i .0, until directed to monitor Critical Safety Functions then transition to Remain in EOP-1.0, EOP-15.0, Response To Loss of Secondary Heat Sink."

FOP-i 5.0, "Response Sink.

FOP-i5.0, "Response B. Directly enter EOP-15.0, Response To Loss of Secondary Heat Sink."

Sink.

FOP-i .0, until directed to monitor Critical Safety Functions then transition to C. Remain in EOP-1.0, EOP-13.0, Response To Abnormal Nuclear Power Generation."

FOP-i 3.0, "Response Generation.

D Transition from EOP-1.0 Dy FOP-i 3.0, "Response FOP-i .0 to EOP-13.0, Response To Abnormal Nuclear Power Generation."

Generation.

VC Summer VC Summer Nuclear Nuclear Plant Plant 2005-301 SRO 2005-301 SRO Inital Inital Exam Exam

81. 008A2.04 81.

c--------'--c--c--

008A2.04 002 002 The Unit Unit is is operating operating at at 100%

100% power power with all all systems in in normal normal lineups lineups when the following annunciators actuate:

- LLTDN/SL

- TDN/SL WTR HX FLO LO [0 TEMP HI

- CC LOOP A RM-L2A HI RAD

- CC SRG TK VENT 7096 CLSD HI RAD

- CCW SRG TK LVL HI/LO/LO-LO NO other annunciators are lit and all associated automatic functions have occurred.

Which ONE of the following is the correct cause and action?

A. A leak exists in the Letdown HX; verify closure of PVT-8152, LLTDN TON LINE ISOL, per SOP-i 02, CHEMICAL AND VOLUME CONTROL SYSTEM, and manually shut PVV-7096, SOP-102, CCSURGETKVLV CC SURGE TK VLV BB.

..... A leak exists in the Letdown HX; manually close PVT-8152, PVT-8i52, LLTDN TON LINE ISOL, per SOP-i 02, CHEMICAL AND VOLUME CONTROL SYSTEM, and verify closure of SOP-102, PVV-7096, CC SURGE TK VLV C. RCP "A" A thermal barrier has been breached. Conduct a normal shutdown per GOP-4B, POWER OPERATION (MODE 1 1 - DESCENDING), Stop RCP A within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per SOP-lOi, SOP-1 01, REACTOR COOLANT SYSTEM.

D. A Phase "B" B Containment Isolation has actuated due to RM-L2A&B (Component Cooling) alarming. Immediately trip the reactor and trip ALL RCPs and enter EOP 1.0.

VC Summer VC Summer Nuclear Nuclear Plant Plant 2005-301 SRO 2005-301 SRO Inital InitaJ Exam Exam

82. 009EG2.4.30
82. 009EG2.4.30 002002 Which ONE ONE of the following identifies identifies an event that is is required required to be be reported reported toto the NRC NRC within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> per EPP-002, COMMUNICATION AND NOTIFICATION.

A. An unplanned ECCS initiation that does not discharge to the RCS during an SI surveillance test.

B.%

B ..... An ECCS discharge to the RCS in response to a small break LOCA.

C. An airborne release of> 2X Appendix B limits.

D. A liquid release of of>> 2X Appendix B limits.

VC Summer Nuclear Plant 2005-301 SRO Inital Exam

83. 022AG2.4.49 001 The plant was operating at 80% power when the following annunciators (not all inclusive) came in:

- REGEN HX L LTDN TDN OUT TEMP HI

- VCT LVL HI/LO

- CHG LINE FLO HIILO Hl!LO

- LOS DEV HI/LO PZR LCS Hl!LO Charging pump amps are fluctuating between 25 and 30 amps Charging flow is fluctuating between 25 and 30 gpm pressure is oscillating between 2500 and 2600 psig Charging pre,ssure Which ONE of the following set of actions should the supervisor direct his board operators to perform (These actions are not all inclusive)?

A.

A.>I Secure the operating charging pump, close all letdown isolation valves, and close FCV-122, charging flow control valve.

B. Verify at least one charging pump is operating, verify FCV-122 is open, and verify CCW COW flow to the RCP Thermal Barriers is GREATER THAN 90 gpm on FI-7273A(B),

Fl-7273A(B), THERM BARR FLOW GPM.

C. Secure the operating charging pump, realign charging pump suction, and close both LCV-115B(D),

LCV-1 1 5B(D), RWST TO CHG PP SUCT.

D. Verify at least one charging pump is operating, verify FCV-122 is open, and open both LCV-1 150(E), VCT OUTLET ISOL.

LCV-115C(E),

VC Summer VC Summer Nuclear Nuclear Plant Plant 2005-301 2005-301 SRO SRO Inital Inital Exam Exam

84. 032AA2.08
84. 032AA2.08 003003 Refueling operations Refueling are in operations are in progress, progress, with SR SR monitor monitor N33 N33 out out of of service, service, when power power is is suddenly lost to source range neutron flux monitor N31 and subsequently regained 30 minutes j later.

Which ONE of the following describes the action to be taken for this situation when power is lost?

A. Suspend all core alterations and perform an analog channel operational test of source A>o/

range neutron flux monitor N31 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of core alterations.

B. Suspend all core alterations and perform a neutron flux response time test AND operational test of source range neutron flux detector N31 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start of core alterations.

C. Determine boron concentration and perform a channel check of source range neutron flux monitor N31 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D. Determine boron concentration and perform a neutron flux response time test of source range neutron flux detector N31 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

VC Summer Nuclear Plant 2005-301 SRO Inital Exam

85. 035G2.4.20 002 The crew has just entered EOP-15.0, "Response Response to Loss of Secondary Heat Sink" Sink from EOP-12.0, Monitoring of Critical Safety Functions.

The following conditions exist:

- WR SG "A"

- A level is 25%

- WR SG "8"

- B level is 12%

- WR SG "c"

- C level is 11%

- Total Feed Flow is 290 gpm Which ONE of the following sets of actions (not all inclusive) should be taken as directed by EOP-1 5.0, "Response EOP-15.0, Response to Loss of Secondary Heat Sink"?

Sink?

A. Ensure all EFW valves are open and establish EFW flow to at least one SG.

B. Reset SI and establish MFW flow to either the "8" B or "c" C Steam Generators.

C. Reset SI, dump steam to the condenser and feed using a condensate pump.

D..... Trip ALL RCPs, actuate SI, establish an RCS bleed path:

D

VC Summer Summer Nuclear Nuclear Plant Plant 2005-301 2005-301 SRO SRO Inital Inital Exam Exam

86. 054AA2.03 002 following conditions The following conditions exist:

- A plant startup was in progress.

- Power level was at 38%

- The reactor tripped

- SG blowdown isolation valves (PVG-503A(B)(C), A(B)(C) ISOL)

- SQL) closed A, "B",

- Current SG narrow range levels in "A",

- B, and "C" C SGs are 8%, 10%, and 10%, respectively, and decreasing Which ONE of the following correctly states the initiating event that caused the trip and the expected automatic actions based on these conditions?

A. The operating MFP tripped and ONLY the motor driven EFW pumps have a current start signal.

B.v B ..... The operating MFP tripped and BOTH the turbine driven AND motor driven EFW pumps have a current start signal.

C. All SG flow control valves drifted closed and AMSAC should have actuated.

D. All SG flow control valves drifted closed and ONLY the turbine driven EFW pump has a a current start signal.

VC Summer Nuclear Plant 2005-301 SRO Inital Inital Exam

87. 068G2.1.20 002002 A Liquid Radwaste Release is been in progress:

- XCP-646 2-5, MON TK DISCH RM-L5 HI RAD, has just actuated for the second time.

RCV00018-WL, Liquid Radioactive Waste Control Valve, indicates shut.

- Within 30 seconds of the alarm, alarm RM-L5's

, RM-L5s reading returns to below the setpoint.

Which ONE of the following correctly states the next procedure steps to be taken.

A.

A..... The tank must be sampled and activity levels verified, then open RCV00018-WL and resume the release per SOP-1 SOP-i 08.

RM-L5s reading is below the setpoint, then open RCV00018-WL B. Verify that the RM-L5's RCV000i8-WL and SOP-i 08.

resume the release per SOP-1

c. RM-L5s reading is below the setpoint, then open RCV00018-WL and C. Verify that the RM-L5's SOP-i08.

resume the release per SOP-1 08. Direct Heath Physics to continue to monitor the release and reduce the release rate.

D. Notify Health Physics and request a radiological survey. The release can not be reinitiated under the current release permit.

VC Summer Nuclear Plant 2005-301 SRO Inital Exam

88. 103G2.1.30 002 Plant conditions are as follows:

- The unit is currently in MODE 4, with temperature and pressure increasing.

- All major work inside containment was completed two hours ago and there are NO personnel inside the Reactor Building.

- An auxiliary operator has just called to report that the red indicating light above the Personnel Escape Airlock is LIT and that he was unable to operate the Fuel Handling Building door using the handwheel.

Which ONE of the following is correct regarding the status of the Personnel Escape Airlock AND Containment Integrity?

A.oI be avoided when the wind is from the East-Southeast. This will prevent the released activity from being drawn into the Auxiliary Building ventilation.

B. Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should: should be avoided when the wind is from the West-Southwest. This will prevent the released activity from being drawn into the Auxiliary Building ventilation.

C. Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should be avoided when the wind is from the East-Southeast. This will prevent the released activity from being drawn into the Control Building ventilation.

D. Discharges from the Waste Gas Decay Tank or other high activity gaseous releases should be avoided when the wind is from the West-Southwest. This will prevent the released activity from being drawn into the Control Building ventilation.

VC Summer Summer Nuclear Nuclear Plant Plant 2005-301 SROSRO Inital Inital Exam Exam

94. G2.4.33
94. G2.4 33 002 002 ONE of Which ONE of the following individual's individuals approval is is required required to extend the the time that an an invalid invalid nuisance annunciator is removed from service past 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />?

A. Duty Shift Engineeer B. Duty Shift Supervisor C Manager, Operations Cy D. General Manager, Nuclear Plant Operations

VC Summer Nuclear Plant 2005-301 SRO Inital Exam

95. G2.4.38 002 Plant conditions are as follows:
  • An event has occurred resulting in substantial core degradation with potential loss of containment integrity.
  • A General Emergency has been declared.
  • The prevailing wind is blowing from the south.

Which ONE of the following must assume the duties of Interim Emergency Director, and to which area should he direct non-essential personnel be evacuated?

A. Shift Supervisor; Evacuate to their personal residence.

B.%

B ..... Shift Supervisor; Evacuate to the Southern Offsite Holding Area.

C. Manager, Operations; Evacuate to their personal residence.

D. Manager, Operations: Evacuate to the Southern Offsite Holding Area.

VC Summer Nuclear Nuclear Plant Plant 2005-301 SRO Inital Exam

96. W/E02EG2.4.6 W/EO2EG2.4.6 001 001 Plant conditions are as follows:

- A reactor trip and SI have occurred due to a steam break.

- ALL Main Steam Isolation Valves initially failed to close.

- EOP-3. 1, Uncontrolled Depressurization of All Steam Generators, is in progress at Step 17,

- EOP-3.1, 1 7, Establish Normal Charging.

- PZR level is 58%.

- EFW flowrate is 50 gpm to each Steam Generator due to required operator action.

- All Steam Generator Narrow Range levels are 4%.

- Reactor Building pressure has remained below 11 psig.

- RCS pressure is 1750 psig and going UP.

- Core Exit TCs are 435 of

- °F and going DOWN.

The "C" C Main Steam Isolation Valve closed 30 seconds ago and "C" C Steam Generator pressure has changed from 80 to 130 psig.

Which ONE of the following correctly describes the actions the crew should take?

A. Must remain in EOP-3.1 until the Critical Safety Function Status Trees direct entering an orange or red path Emergency Operating Procedure.

B. IMMEDIATELY transition to EOP-3.0, Faulted Steam Generator Isolation, Step 1.

C..... Complete EOP-3.1 through Step 20, verify SI Flow is NOT required, and then transition to C

EOP-3.0, Faulted Steam Generator Isolation, Step 1.

D. Complete ALL steps of EOP-3.1 and then transition to EOP-1.2, Safety Injection Termination, Step 1.

VC Summer Summer Nuclear Nuclear Plant Plant 2005-301 SRO 2005-301 SRO Inital Inital Exam Exam

97. W/EOSEA2.1 W/EO5EA2.1 001 001 The Crew The Crew has has entered EOP-16.0 "Response entered EOP-16.0 Response to Pressurized Pressurized Thermal Thermal Shock" Shock duedue to to an an Orange path on the integrity CSF status tree. The Crew is at the step for Checking RCS Tcold I Stable or Increasing.

While checking EFW flow it is determined that a Red path condition exists on the Heat Sink CSF status tree.

Which ONE of the following correctly describes the action that should be taken by the crew?

A. Remain in EOP-16.0 until it is completed, then transition to EOP-15.0, Response to Loss of I Secondary Heat Sink.

B. Remain in EOP-16.0 until the Orange path is cleared, then tranistion to EOP-15.0.

EOP-1 5.0.

C9 IMMEDIATELY transition to EOP-15.0.

C.""

D. The transition to EOP-15.0 EOP-1 5.0 is NOT required since EOP 16.0 provides actions for adjusting EFW.

VC Summer Nuclear Plant 2005-301 SRO Inital lnital Exam

98. W/E09EA2.2 W/EO9EA2.2 001 A Reactor Trip with a loss of Off-site power has occurred. Power will not be restored for at least eight hours, and a cooldown is desired.

- RCS temperature is currently 557 of

- °F

- Only one CRDM fan is operable.

Which ONE of the following correctly describes the actions to be taken in accordance with FOP-i .3 "Natural EOP-1.3 Natural Circulation Cooldown"?

Cooldown?

A. Reduce RCS pressure to below 1925 psig, maintain RCS subcooing greater than 80 of, 80°F, F/hr.

0 cooldown shall not exceed 50 of/hr.

By B ..... Maintain RCS pressure above 1925 psig, maintain RCS subcooling greater than 130 130°Fof F/hr.

0 and cooldown shall not exceed 50 of/hr.

C. Reduce RCS pressure to below 1925 psig, maintain RCS subcooing greater than 130 °F, of, F!hr.

0 cooldown shall not exceed 25 of/hr.

D. Maintain RCS pressure above 1925 psig, maintain RCS subcooling greater than 80 of and 80°F cooldown shall not exceed 25 of/hr.

°F/hr.

VC Summer Summer Nuclear Nuclear Plant Plant 2005-301 SROSRO Inital Inital Exam Exam

99. W/E12EG2.4.4 W/E12EG2.4.4 002 002 Plant conditions Plant conditions are as as follows:

- The Unit experienced a Steam Generator Tube Rupture (SGTR) on the "8" B Steam Generator (SG).

- The crew is currently performing EOP-4.0, Steam Generator Tube Rupture, Step 3, Isolate flow from each RUPTURED SG.

When the crew transitioned from EOP-1.0 EOP-1 .0 to EOP-4.0, FOUR (4) minutes ago, plant parameters were as listed below:

Loop A Loop 8B Loop C SG Pressure 800 psig 1200 psig 800 psig SG NR Level 40% 80% 45%

SGPORV SG PORV SHUT OPEN SHUT RCS Temperature 557 of

°F 556 of

°F 557 of

°F RCS Pressure: 1350 psig NOTE: ALL plant parameters were stable, with the exception of 8 B SG NR Level, which was going UP.

CURRENT plant parameters are as follows:

Loop A Loop 8 B Loop C SG Pressure 500 psig 1050 psig 750 psig SG NR Level 20% 85% 45%

SGPORV SG PORV SHUT SHUT SHUT RCS Temperature 520 of

°F 550 of

°F 550 of

°F RCS Pressure: 10001000 psig ALL above parameters are all decreasing (going DOWN), with Loop A parameters decreasing faster than Loops B8 and C.

Which ONE of the following correctly describes the NEXT action the crew should take in accordance with Emergency Operating Procedures?

A. IMMEDIATELY IMMEDIATELY go go to EOP-2.0, EOP-2.0, Loss of Reactor or Secondary Secondary Coolant.

B.v B. . . IMMEDIATELY go go to EOP-3.O, EOP-3.0, Faulted Steam Steam Generator Isolation.

Isolation.

C. RETURN to EOP-4.0, Steam Steam Generator Tube Rupture, Rupture, Step Step 1.

1.

D. COMPLETE D. COMPLETE EOP-4.0, EOP-4.0, Step Step 33 and and THEN go go to EOP-3.0, EOP-3.0, Faulted Faulted Steam Steam Generator Isolation.

Isolation.

VC SummerSummer NuclearNuclear Plant Plant 2005-301 SRO SRO Inital Inital Exam Exam 100. W/E13EG2.2.2S 100.

W/E13EG2.2.25 001 001 Which ONE ONE of of the following following describes describes the basis basis for reducing reducing the Power Power Range Range Neutron Neutron Flux Flux High Trip Setpoint, in accordance with Summer Technical Specification Table 3.7-1, if one or more main steam line code safety valves are inoperable for more than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />?

A. To ensure that sufficient relieving capacity is available to limit secondary system pressure A.>oI to within 110% of design pressure.

B. To minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown of the INOPERABLE safety valve(s).

C. To limit the pressure rise within the reactor building to within the values assumed in the accident analysis in the event of a steam line rupture within the reactor building.

D. To ensure that pressure induced stresses in the steam generator with the INOPERABLE safety valve(s) do not exceed the maximum allowable fracture toughness stress limits.

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