ML17031A302
| ML17031A302 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/12/2016 |
| From: | Public Service Enterprise Group |
| To: | D'Antonio J Operations Branch I |
| Shared Package | |
| ML16076A441 | List: |
| References | |
| U01930 | |
| Download: ML17031A302 (124) | |
Text
U.S. Nuclear Regulatory Commission S ite-S pecifi c Written Examination Applicant Information Name: I Region:
Date: 12/19/2016 rFacility: Salem 1 & 2 License Level: RO Reactor Type: W Start Time: Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. The passing grade requires a final grade of at least 80.00 percent. Examination papers will be collected SIX hours after the examination starts.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results Examination Value - - - - - - Points Applicant's Score - - - - - - Points Applicant's Grade - - - - - - Percent
Reactor Operator Answer Key
- 1. c 26. c
- 2. b 27. a
- 3. a 28. a
- 4. b 29. a
- 5. d 30. a
- 6. d 31. c
- 7. b 32. a
- 8. d 33. c
- 9. c 34. a
- 10. a 35. a 11 . a 36. d
- 12. d 37. d
- 13. c 38. c
- 14. d 39. d
- 15. b 40. b
- 16. b 41. d
- 17. b 42. c
- 18. c 43. b
- 19. d 44. c
- 20. b 45. b
- 21. d 46. d
- 22. c 47. a
- 23. d 48. b
- 24. d 49. a
- 25. a 50. b Page 1
Reactor Operator Answer Key 51 . b
- 52. d
- 53. a
- 54. d
- 55. d
- 56. d
- 57. d
- 58. a
- 59. b
- 60. a 61 . a
- 62. b
- 63. c
- 64. a
- 65. d
- 66. c
- 67. c
- 68. c
- 69. b
- 70. d 71 . d
- 72. d
- 73. a
- 74. c
- 75. c Page 2
RO SkyScraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes pue.stionTopi~J I Ro 1 Given the following conditions:
- Unit 1 was operating at 80% power, steady state.
- RCS Cb is 1100 ppm.
- Control rods begin withdrawing at 8 spm.
Of the following, which could be causing this rod withdrawal?
~ 1PT-505, Turbine Steam line Inlet Pressure transmitter, has failed low.
ibl 1PT-505, Turbine Steam line Inlet Pressure transmitter, has failed high.
L:_
I
!c~ A VCT auto makeup occurred, and the 1CV175 Rapid Borate Stop Valve was open.
~I I
~.: A VCT auto makeup occurred, and the boron addition rate was set to 1 gpm instead of 11 gpm.
I
!Answer 1 c 1
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1 001 as the appl to Continuous Rod Withdrawal:
- Explanation of I 55.41.(b)5 - The system characteristics of the emergency borate line are such that no flow will occur with a BAT pump running in Answers
- , slow speed, which is the normal alignment of the CVCS makeup system. When an auto makeup occurs, the BAT pump running (in
~-*** ~~~**
- auto) swaps to fast speed, and would provide flow through an open CV75 to borate the RCS. The boration would cause RCS temperature to lower, causing SG pressure to lower, causing MT governor valve to open, causing temperature to further lower, and l------....U:ons...111roulCLl1efur*LIALl!I.nm:aw:u:*!Cl...l:O...r..e.e *
- o
- Iis incorrect because PT-505 failing low would ca.use rod insertion, not withdrawal. B is incorrect because the rod withdrawal would Ibe at maximum rate 72 spm . Dis incorrect because it would cause a dilution, not a boration.
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~IJesti~n Topic i RO 2 IWith Unit 2 at power, which of the following failures would cause a SINGLE control rod to drop fully into the core? I fa~ Blown fuse for a Lift coil during demand for rod movement.
c-* 1 lb.
Blown fuse for a Stationary Gripper coil with no demand for rod movement.
!c. Loss of Power to a single Power Cabinet during demand for rod movement.
I
'.dJ Loss of Power to a single Logic Cabinet with no demand for rod movement.
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system/Evotution L_____-=..__- ** - - - - .. ~---*__J Titl~
il<A State_111!!nT:1 Knowled e of the interrelations between Oro ped Control Rod and the followin :
Control rod drive power sup lies and lo ic circuits 1
,Expianation of 55.41.(b)6- Rod movement loss of lift coil still has Moveable Gripper holding rod, rod just wouldn't move. Stationary gripper coil Answe_rs_:__ J holds rod while not moving. Loss of power to Power Cabinet would affect multiple rods stationary gripper coils. Loss of Logic cabinet with a demand for rod movement could cause rods to drop during the movement cycle, as it would lose power to movable gripper and lift coils, and rods would stop when cycle timed out and stationary gripper coils re-engaged.
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~uestionTopicl *~--------------------------------------------~
Given the following conditions:
- Unit 1 was operating at 100% power when a reactor trip signal was generated by the RPS, but the Reactor Trip Breakers did NOT open.
- The reactor was tripped from the control room when the RDMG sets power supply breakers were opened from 1CC3.
Because RPS did not successfully trip the reactor, which of the following actions is required to be directly performed by the control room crew?
Open the Main Generator Output Breakers.
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-rKA Statementl Breakers, rela s and disconnects l
1 Explanation of l 55.41(b)7 - With the reactor trip breakers failing to open, the Main Turbine will not receive a trip signal (from the output of the
_______ I' RTBs). A manual turbine trip will be performed. The main turbine trip will cause the main generator output breakers to Answers:
automatically open, so the crew will not directly open the output breakers. The group buses will transfer automatically on low voltage. The AFW pumps will automatically start on lo-lo level when the SGs shrink after the main turbine is tripped.
Reference Title Reference Number -NOl !Revision
__J I~~~~=II Objectives TRP001 E021 I
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RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes L<Juestion T.9pic .. IR04 I What does EOP-LOCA-1, Loss of Reactor Coolant, check for OTHER than a LOCA as the reason for being in LOCA-1, and why?
iaJ SGTR. If the ECCS injection flow is due to a SGTR, the tube rupture must be addressed before returning to LOCA-1 to terminate ECCS flow.
fb.
Steam break. If the ECCS injection flow is due to a Loss of Secondary Coolant, the event could be terminated by isolating the faulted SG.
!~ SGTR. If the ECCS injection flow is due to a SGTR, an unnecessary transition to LOCA-3, Transfer to Cold Leg Reci ,, ....
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,d. Steam break. If the ECCS injection flow is due to a Loss of Secondary Coolant, an unnecessary transition to FRHS-1, Loss of Secondary Heat Sink could be required. I IAnswe_i:J b I I 'exam LeveO IR I 'c;(ignlt!ve Levei_j IMemory I !facility:~ jSalem 1 & 2 I ~xamDate: I 12/19/20161 1 1 2.~a_.Ji~~~@~~!J§Jl~~~l~r~~~LJ~~<3~~LJ ~;~; D I - ' o/;J, "_'~i
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~stem/EvolutionTitle j L009 Knowled e of the specific bases for EOPs.
Explanation ofl 55.41.b(1 O)The Major Action Categories for LOCA-1 are : 1. Check for Subsequent Failure, 2. Monitor Plant Equipment for Optimal iAnswer!i: __ .J Mode of Operation, and 3. Determine optimal Method of Long-Term Plant Recovery. The first item checks that a faulted or ruptured SG is not the reason for ECCS injection, and either fixes it on the spot (faulted) or transitions to another more appropriate procedure With a faulted SG being the cause of the ECCS flow, LOCA-1 has a "do loop" which will wait until the SG has blown performed to do actions which will terminate the primary to secondary leakage, which is not performed in LOCA-1. Additionally, there is no transition from SGTR-1 to LOCA-1. The unnecessary transition to FRHS-1 is plausible because it happens on other procedures FRCE,LOSC-2) when minimizin AFW flow to SGs when all are faulted.
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Reference Title
!~~b~*-=--**-~ Objectives I LOCA01 E009
! M~terial_ Required for Examination J I
'Question Source: 11 Facility Exam Bank I ~estionModification Method: _J Direct From Source col"nmen-t-i I
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RO SkyScraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes f§uestion Topicj I Ro 5 I Given the following conditions:
- Due to a LBLOCA, Operators have entered 2-EOP-LOCA-3, Transfer to Cold Leg Recirculation.
- NO CCW pumps are running.
Which of the following describes the procedure flowpath?
fa.I Continue in LOCA-3 to align BOTH RHR pumps, one SI pump, and one charging pump for recirc until RWST lo-lo level is reached.
~ *** J
'c!>.:1 Transition to LOCA-5, Loss of Emergency Coolant Recirculation, while attempting to restore CCW.
r~ Transition to APPX-1, CCW Restoration, then establish cold leg recirculation.
I id. -
I Continue in LOCA-3 and align for single train recirculation without CCW.
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[El<planation ofl 55.41.b(10) At LOCA-3 step 11.2, with no CCW pumps running, operators are directed to go to step 124 and align for single train
'~swers.:____ ~ operation. There is no provision to transition to APPX-1 or LOCA-5.
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fQu~tionTop~ * - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - '
Which of the following indications would be unexpected following a total failure of a RCP #1 seal?
Affected RCP .....
~~1000015K210 j 1~i_1_0_-~~~§~~~!J:Ifil1hCf~~1~~~~D~~~~LJ ~ D
'.~ystem/Evolution TitleJ IReactor Coolant Pump Malfunctions I _q_1 s __ _J 1
~ Statemef!!:J Knowled e of the interrelations between Reactor Coolant Pump Malfunctions and the followin RCP indicators and controls Explanation of I 55.41.b(3)Number 1 seal failure means minimum resistance I maximum seal flow, so seal flow will rise. More seal flow will be felt at 1
An~wers:_ ---' the #2 seal, which will cause higher #2 seal D/P and higher leakoff going to the standpipe. The seal leakoff D/P alarm will come in because the failure of the seal results in no D/P across the seal.
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Material Required for Examination j I 11
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RO SkyScraper SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List I Outline Changes I 1Question Topic IRO 7 Given the following conditions:
- Unit 2 was operating at 90% power with 21 charging pump in service when the controlling PZR Level Channel I failed low.
- The Charging Master Flow Controller was placed in Manual when directed by S2.0P-AB.CVC-0001, Loss of Charging.
- The alternate PZR level channel has been selected as the controlling channel.
- Letdown has been restored.
Which of the following identifies a consequence of returning the Master Flow Controller to auto PRIOR to returning PZR level to program as directed in S2.0P-AB.CVC-0001 ?
Charging flow will ...
' rise, and VCT auto makeup may initiate.
~
I
~ lower, and flashing in the Letdown line could occur.
- I
- c. rise, and RCP seal injection flow could exceed Tech Spec limit total seal injection flow.
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lower, and 2CC71 LTDWN HX CC CONT VALVE will not respond quickly enough to prevent Mixed Bed Dem in isolation on high inlet 1 ** -"""'1 I
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'system/Evolution
Title:
ILoss of Reactor Coolant Makeup I 022 __
ed e of the operational implications of the followin concepts as the apply to Loss of Reactor Coolant Makeup:
nship between char in flow and PZR level Explanation of' 55.41.b(?) With a CCP in service, the failure LOW of the controlling PZR level channel will cause charging flow to RISE. The stem
- Answers
- . stated that MFC was taken to manual when directed IAW AB, so there was sufficient time for actual charging flow to rise
!I substantially. With actual level higher than programmed level, if the MFC were placed in auto it would force charging flow to lower.
If charging flow lowered to <-60 gpm, inadequate cooling of letdown flow would occur in the regenerative heat exchanger, and i--------;-<l=et~d~oiM:J...JinP~.e CC71 is normallv ooh1 -10% onen and...b.a.5"-1.JJ""'-Ll.'¥-!.llJ;JClW!.ll...ll.J,J;.L"-""'.L*u....u.=.J.W<"--"'"'-'!'.!...lN"""'UJ.J.-+i
!rise downstream ofthe letdown HX, and temps would not reach demi~ isolation lev~ls. .. . .
Iflow wouldn't rise, but the actions associated with hi her flow are correct.
Reference Title Facility Reference Number
- !Reference Section _J *Page No.* ---- 'Revision
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RO SkyScraper I SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes Question Topic] *-------------------------------------------~
When responding to multiple stuck rods during the performance of EOP-TRIP-2, Reactor Trip Response, why are there two different borationtimes I associated with borating the RCS for those stuck rods?
s the number of stuck out rods increases, the amount of boration required to be added per rod also increases.
n is in progress a higher boration total is required vs if the plant is stable in Hot Standby.
OL vs EOL) require different specific boration times to be used.
c9_._ The different available borated water sources contain different ppm boron.
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- t>s.43 D System/Evolution Title !----"'---'---------------------------' 1024 ---1 KA Statement: I ~owledge of the reasons for the following responses as they apply to Emerqency Boration: I Actions contained in EOP for emerqency boration I
[Explanation of I 55.41.b(10) Step 7 of TRIP-2 requires boration for 2 or more control rods not fully inserted. It first attempts rapid boration from the Answers: I Boric Acid Storage Tanks via a Boric Acid Transfer pump in high speed, for 35 minutes per rod. If this is unsuccessful, then boration from the Refueling Water Storage Tank via a charging pump running at greater than 87 gpm is performed for 120 minutes per rod. The BAST minimum Cb is 6550 ppm per Tech Specs, while the RWST minimum Cb is 2300 ppm.
J:Reference Section ] iF>a9e-No.]
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!Revisio~
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Reference Title I Facility Referenc;_~ Number I Reactor Trip Response 112-EOP-TRI P-2 II Step 7 II I I30 I I Bo ration Times for Multiple Stuck-out Control Ro II S-C-CVC-MDC-1314 11 1115 111 I I II 11 11 11 I
!L.O. Number I
.. 1 Objectives I
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RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes l.:;iuestio~ Topi~l 1RO g Given the following conditions:
- Unit 2 is in MODE 4 with RHR system providing the shutdown cooling.
- 2RH25 RHR Hot Leg Recirc discharge relief starts to discharge (lift).
With NO operator action, which of the following indications would occur if the valve continues to pass flow?
[it: OHA-41 AUX ALM SYS PRINTER, for point 758, 24 RHR SUMP PUMP START.
OHA-41 AUX ALM SYS PRINTER, for point 710, RCDT PUMP START.
- b.J I
~-i OHA C-2, CNTMT SUMP PUMP START.
I ldj PRT LEVEL HI-LO Console Alarm.
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[KA:11000025G446 lsystem/Evoiution:Title I ILoss of Residual Heat Removal System I r~25_
[~ St<!tement:
Abilit to veri that the alarms are consistent with the Ian! conditions.
IEXplanation of
- 55.41.b(5,7,8) The 2RH25 is located upstream of normally shut 2RH26 which supplies Hot Leg Recirc during accident conditions. It
!Jl.~wer,s: is located in containment, and as such, discharges to the containment trench, which flows into the containment pocket sump. C-2 will annunciate when the containment sump pump starts. All the other choices are radioactive waste paths which do not receive the discharge. RCDT and PRT are also located in containment and are plausible relief path collection points. RHR sump pump run
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~~~stion~our~e Comm~nts' 142333 changed from levels changing to alarms which would occur.
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--*---*-*~ ' I Given the following conditions:
- Unit 2 initiates a Safety Injection from 100% power due to a LOCA.
- 15 minutes after the SI is initiated, containment pressure peaks at 5 psig.
Which of the following identifies an automatic response which has occurred for Component Cooling Water System components, and why?
la. 1 2CC215 and 2CC113, Excess Letdown Heat Exchanger CCW isolation valves, received a close signal to ensure this non-essential containment flow path is isolated.
I
'b.I 21 and 22CC16, RHR HX CCW isolation valves, received an open signal to ensure that long term cooling of the RCS is in service when the swap to Cold Leg Recirc is required. I
~*J 2CC215 and 2CC113, Excess Letdown Heat Exchanger CCW isolation valves, received a close signal to ensure ALL CCW supply and return from the containment is isolated.
I
' 21 and 22CC16, RHR HX CCW isolation valves, received an open signal to ensure that RHR pumps do not overheat if the RCS remains I
id.
-- I above the shutoff head of the RHR pumps.
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[Syste~yo1uti0n-Titlej ILoss of Component Cooling Water I '.CJ.26_ -_
1 IKA Statement:
~-*--* - --* --~
Knowledge of the reasons for the following responses as they apply to Loss of Component Cooling Water: I The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS I Explanation of i 55.41.b(?,8) The SI signal sends a close signal to the CC215 and CC113, Excess Letdown HX isolation valves, as they are
~swe_i:_s:_ _ J Containment Phase A isolation valves. The purpose of closing Phase A isolation valves is to ensure all non-essential containment penetrations are isolated on a SI. B is incorrect because CC16s do not receive an open signal until the ARM PB is depressed and the RWST level is 15.2' and manual alignment is required to place ECCS in CLR. C is incorrect because ALL CCW supply and I--", 1rn "'!ro - - " =--1-6. ... .J nr"I,.. ~I -:---.I 6.1... ... Df"'O r'f'\11.I ic- c-+ill 1... ... '1r.rt e1 * - .... li.o~ ..... .&.:1 .... oi... ......... C .... :-....... ;if 1 i:::. ....... :-in. ........... " n ic- '
because the CC16s do not recei~e an open signal until the ARM PB. is depressed and the RWST level 'is 15.2', and the RHR pumps are cooled by either flow through the pump from RWST (LBLOCA) or recirc flow (SBLOCA until DD is SID).
r-*---*- --------------- [------------~*------ *-*---,~---1 L_ _ Ref~ence Title _ _ _- - J _- Facility ReferencEi__NlJ!11ber _ j ~eference Section_ *-
~ l Page No. 1 ~evisio~
I Component Cooling Lesson Plan 11 NOS05CCW000-11 11 1142 1111 I II ii - II !I I 1: II II q JI I
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RO Skyscraper I SRO Skyscraper I RO System/Evolution List SRO System/Evolution List I Outline Changes I louestion Topic_] I RO 11 l IWhen responding to lowering PZR pressure IAW S2.0P-AB.PZR-0001, Pressurizer Pressure Malfunction, why are BOTH PZR PORV Stop valves closed when attempting to determine if the PORVs are the source of the pressure reduction? I
~ Because the PORV tailpipe temperature sensor is on the combined PORV discharge line .
1 b.I To prevent pressurizing the PRT past the point where venting will be unavailable due to the high pressure interlock.
- ________j
~
~J Because the PZR PORV and PZR Safety Valves discharge into a single line, and isolation of both PORVs is necessary to determine whether the leak is from the PORV's or Safeties. I
~] Because the PZR PORV and Rx Head Vent Valves discharge into a single line, and isolation of both PORVs will give indication of whether the leak is from the PORV's or Rx Head Vents.
I
]Answer l a I I Exam Level I j R I :cognitive Level 'I Memory I 1Fa~ility:
- 1Salem 1 & 2 I [E~amDate: I 12/19/20161 4.1l\Section:jl~
~w' <;*;-~<<~
I AK3.03
,----; I IKA:il 000027K303 IRoValue:,j 3.7jSROValue:Jl ROGroup:il 1jSROGroup:!I 11 55;!3 D 1
System/Evolution Title j Pressurizer Pressure Control Malfunction ! 027~
KA Statement:* ! Knowledqe of the reasons for the followinq responses as they apply to Pressurizer Pressure Control Malfunction:
IActions contained in EOP for PZR PCS malfunction
- Explanation of "I 55.41.b(7) As shown on dwg 203301, both the PZR PORVs and Safeties discharges combine into a single line going to the PRT.
!Answers: 1 The Safeties each have their own individual temperature sensor, while the PORVs have one sensor on a common line. Since there I is no way to distinguish which valve is leaking, both PORV Stop valves are closed. If temperature does not lower, the user is II~~=~'.~~:=~~~ ::~p~t~~~:l~~:\~~T:n%~~~~ t~ ~8h~~~~~ ;~~~e0t~;l~~9e ;~~~~~~t~:~~~' ~~eei~e:!:~at~~_!:~ l~h:~rt~~;
stop valve is closed and the other opened. Then the procedure is exited." B is incorrect but plausible because discharge is directed I to the PRT, and PRT vent valve is prevented from opening >10 psig. C is incorrect but plausible because the all the discharges do combine into a single line, however all 3 safeties have their own sensors. C is incorrect but plausible because the all the discharges do combine into a single line, however, Rx Head Vent leakage is not addressed in AB. PZR-1, as the vents would be seen as a RCS leak.
~~~* Reference Title i Facility Reference Number : _Refererice Section _] ' Page No. i ~vision' IPressurizer Pressure Malfunction I II ,l I, I 11 S2.0P-AB.PZR-0001 18 I -, I 11 I
'I ll I II lI I L.O. Number I ABPZR1 E002 Objectives
\Material Required for Examination 'I I Ij lauestio~ Source: i l_N_e_w______~l f Ouestion Modification Method: l, ________~I [Used During Training Program ID
~~~~s~~~m~~1----------------------------------------~I
,coriunent I
I I
RO SkyScraper ( SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List I Outline Changes I
- Question Topic I IRO 12 I I Analyze the following vv* ,..;;UV*
- Unit 2 is operating at 100% power.
- l&C is performing Solid State Protection System testing.
- Reactor Trip Breaker (RTB) A is open.
- Reactor Trip Bypass Breaker A is racked in and closed.
- A valid reactor trip signal is generated in the Reactor Protection System, but the RPS system does not provide any output signal to trip the Rx.
Assuming that the RPS system WOULD generate the appropriate signal when MANUAL actions are performed during TRIP-1 immediate actions, which of the following contains both the operator action and the DIRECT method which will trip the Rx?
- a. Depressing the OPEN PB for Reactor Trip Breaker B to deenergize the UV coil.
I lb.~ Deenergizing the RDMG sets by opening the PZR heater bus supply breakers on 2CC3.
I
"~
~~
Depressing the OPEN PB for Reactor Trip Bypass Breaker A to energize the shunt coil.
I 1.dJ Turning either of the Reactor Trip pistol grip handles to the TRIP position to deenergize the UV coil for Reactor Trip Breaker B.
I
- Answer 11 d I tExam Level* IR I 1Cognitive Level 1 IApplication I I Facility~-* Salem 1 & 2 I IExamDate: i I 12/19/20161
- ,_,,c~~~>>'?,
'KA:ll 000029K206 I AK2.06 I'
- Ro Value
- 112.9*1 SRO Value: 13.1*jSection: l_~_J IRO Group:ll 11 SRO GroupJI 11 ;;t~:!2. D System/Evolution Title : IAnticipated Transient Without Scram 11029 KA Statement:* I Knowledqe of the interrelations between Anticipated Transient Without Scram and the following:
I Breakers, relays, and disconnects Explanation of I155.41.B(?)he failure of the RPS output signal from the automatic trip will initially prevent the reactor from tripping. A is incorrect
!Answers:
_, l
! because PB energizes the shunt coil. B is incorrect because the Rx would already have tripped by another means prior to having to perform this step .. C is incorrect because the RT Bypass Breakers do not have an OPERATE function from the control console.
I Tier/Group 2/1 1OCER55...4 1 -"'
Cognitive Level 3 - Analysis I
References:
NOS05RODSOO EL0-19, Logic drawing 221051 Schematic drawinQ 240111 1
! Reference Title I Facility Reference Number . !Reference Section *I Page No. I !Revision:
IRPS Trip Signals 11221051 I ii 1113 I I II I ll 11 I I ii I 11 ii I LO. Number Objectiv I RXPROTE027
- Material Required for Examination**. 11 Ques~i!;>n Source:.: I
\ Facility Exam Bank l l?uestiori Modification M~tt{od:* *'I Direct From Source l \Usecl During Training Program 1D
.--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~!
lauestiCin Source Comnientsj 150753
- ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~---'
l
!Comment .*.* '. I I
I I
RO SkyScraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
[(luestion ioeis IRo 13 Given the following conditions:
- Unit 1 is operating at 100% power when Intermediate Range Nuclear Instrument 1N35 fails high.
- Operators are responding IAW S1 .OP-AB.NIS-0001, Nuclear Instrumentation System Malfunction, and are removing the channel from service IAW S1 .OP-SO.RPS-0001, Nuclear Instrumentation Channel Trip I Restoration.
- With the PO in the rack area, OHA E-29, SR & IR TRIP BYP, annunciates.
Which of the following identifies the cause of this alarm?
~*.I 1N35 Control Power fuses have been removed .
~ 1 N35 Instrument Power fuses have been removed.
[S 1 N35 LEVEL TRIP switch has been placed in the bypass position.
lcLl POWER MISMATCH BYPASS switch has been placed in BYPASS 1N35.
A~~wer ! Ic I ~~m Levei1 IR I ,Cognitive Level j IMemory I racility: I ISalem 1 & 2 1 iExamoa~ I 12/19/20161
[~I 000033A 102
[SystelTl/Evolutioor-i!&J j Loss of Intermediate Range Nuclear Instrumentation I ~_33
.KA Statement: I bilit to operate and I or monitor the followin as the appl to Loss of Intermediate Ran e Nuclear Instrumentation:
Explanation of 55.41.b(7) A is incorrect but plausible since control power fuses are removed when removing a PR NI from service using the same l~nsw~rs: . __ _J procedure. B is incorrect but plausible as it is the next action to be performed after placing the Level Trip Bypass switch in Bypass. C is correct because when placing the level trip bypass switch the BYPASS position, the IR FLUX HI reactor trip and IR HI FLUX ROD WDRWL STOP are blocked, and OHA E-29 annunciates. Dis incorrect because the IR does not have a power Refe~e_n_c_e se*ct-ion -- ~R~oll~
1
- ================-====.i==
- =="-'=========~~========~r~==::j5
,~=::::::
l':-_:_()*~~- Objectives 1ABNIS1 E001 I
,I____,
'Material Required for Examination
- . 11 l~~-e_st_i~n_._so_u_rce_:_l l_N_e_w_ _ _ _ _ _ ___.l jauest_io_n_M_~~-if_ic_a_ti~_rl_M_et_ho_d_:...-'l, ________~I i!J.!'led During T~aining Progra111_ 1 D
~~e_s_u_on.s_o_-u_rce_-c_o_*m-~~~~ I I
- ~-----------------------------------------'
- --~-. - * - - *--1 I
I I
RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
- Question Topic 1 I RO 15 I Given the following conditions:
- Unit 2 has experienced a tube rupture on 22 SG.
- After the reactor was tripped, the Main Turbine failed to automatically trip, and was manually tripped using the Turbine Trip handle on the control console.
- All feedwater flow was isolated to 22 SG during performance of EOP-TRIP-1, Reactor Trip or Safety Injection.
- 21, 23, and 24 SG NR levels are off-scale low.
- 22 SG NR level is 1% and rising slowly.
- Operators are currently performing actions in EOP-SGTR-1, Steam Generator Tube Rupture.
- Prior to performing the RCS cooldown to Target Temperature, operators are assessing AFW flow status.
Which of the following describes how AFW flow to 22 SG should be controlled?
~ Leave AFW flow isolated to 22 SG for the remainder of the event regardless of 22 SG NR level.
I
~ Establish AFW flow to 22 SG until its NR level is > 9%, then isolate AFW flow to 22 SG. Maintain 22 SG NR level >9%.
I C.' Establish AFW flow to 22 SG until its NR level is >19%, then isolate AFW flow to 22 SG. Maintain 22 SG NR level >19%.
I
'd* jf};:e~se~~:~~w isolated to 22 SG until the--cooldo;;;ntoTargetTe;;:;perat~relsco;T;pJete,thenestabiishAFWfio;;;a~required to keep the sG I
)Answer! ff.:} Exam Level ~ I
- cognitive Level ' Application j ,Facility: i ISalem 1 & 2 ! 1ExamDate:
- j___1_2_11_9_12_0_1_,6I
~I ooo038A144 I EA1 .44 I !RO Value: §!SRO Value: f}:+/-j e_e~I~ ~~[J}:sRo Group: LJ :Ss-.43 &:; k D
!System/Evolution Title KA Statement: i ~to operate and I or monitor the following as they apply to Steam Generator Tube Rupture: I Level operatinq limits for S/Gs Explanation of *I 55.41.b(4, 10) Step 6 of SGTR-1 directs AFW flow be established to the ruptured SG if its NR level is <9%. A is incorrect but
'Answers: plausible if it is thought that you never feed a ruptured SG if intact SG's are available. C is incorrect but plausible since it is the correct action, but the incorrect level. Note: 19% is the new (REV. 30 of EOPs) SG NR level above which intact SGs are directed to be maintained at. D is incorrect but plausible if it is thought that the purpose of leaving ruptured SG isolated during cooldown is to mjoimjze spread of contamination IF jot.act S~ble for cooldo\A/O (~AJbich is asked for jo ste~ "If\ 1 f,...,,. ;,....;.1.:-l.~ .... : t""n +,..., T .... -=-
!Temp).
Reference Title *[ Facility Reference Number I 'Reference Section ii Page No., 1Revision:
ISteam Generator Tube rupture 112-EOP-SGTR-1 F !I Sheet 2 II 1130 I I II II 11 I[ I I *1 ii 11 lI !
I LO. Number SGTR01 E006 Objectives I
- Material Requfredfor Examination II I
,Qu~stie>,n Soulce: J INew I[Question Modification Metho~: :l ________~l fusecl During Training Program lD
!Question source comments! I j
!~~----~-~----~--~-~~---------~-~-~~-~~-----'
- cominent.
I I
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RO System/Evolution List SRO System/Evolution List Outline Changes r=-*-~-*** ---***--: .----------------------------------------------~
lQues~ionTopic !~-----------------------------------------------'
Given the following conditions:
- Unit 2 has experienced a rupture of the 24 main steamline in the mechanical penetration area upstream of 24MS167.
- The Rx is tripped and a MSLI performed.
- Feed flow is isolated to 24 SG.
- Operators are preparing to transition out of EOP-TRIP-1.
Which of the following describes how the RCS cooldown rate will be affected over the next 30 minutes?
The RCS cooldown rate will. ..
Ic.' remain constant until AFW flow is re-initiated to 24 SG, at which time it will increase.
1-:11
- cl._i lower until at least one intact SG NR level rises above 9%, then remain constant as AFW flow is lowered.
~s~ ~ ~Leve_~' IR I Icognitive Le~el j IApplication I ~acility:~ ISalem 1 & 2 I ~arnDate: ' I 12/19/20161 S)lstem/Evolution Titl~
1 KA Statement:' e of the operational implications of the followin concepts as the appl to Steam Line Rupture:
i-----~----'-----'---------""----'----'--'-'--"--------'---------------""
Leak rate versus pressure chan e 55.41.b(4,5, 14) As the faulted SG pressure lowers due to the steam break, break flow will lower, and the rate at which the RCS is being cooled due to break will lower as a result. A is incorrect but plausible if it is thought that a static break will pass the same lbm of steam flow during the entire event. C is incorrect but plausible if it is thought that feed flow is initiated to keep the SG tubes wet, which only would be performed in LOSC-2 if ALL SGs were faulted. D is incorrect but plausible if it is thought that the lowering of Objectives I MSTEAME016 j_ ___,
!Material Re9uired for Examination lj
'Question ~.°urce~ -~ l_N_e_w_ _ _ _ _ _ __.I rQUe_.s_t_io_nM_o_d_ific_a_ti_o_n__M_*e_t_h_od:~"I,._ _ _ _ _ _ _ ___.! ~ed Duril_lg !!~l'ling P_l"~rarnJ D
[(l~esti-on so~rc_e co~_ments 1
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-. --**-**--**--**-I
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j I I I I
- RO Skyscraper
!Question Topic SRO Skyscraper 11 RO 17 RO System/Evolution List SRO System/Evolution List Outline Changes I
Given the following conditions:
.. Unit 2 is operating at 100% power, MOL .
.. 21 SGFP trips .
.. NO operator action is taken in response to the SGFP trip, and the Rx does NOT trip .
Which of the following is an UNEXPECTED alarm if it is locked in 2 minutes after 21 SGFP trips, and what procedure would be used to address the condition associated with that unexpected alarm?
-:a.
- I
~ OHA G-3, EHC SYS TRBL. S2.0P-AB.TRB-0001, Turbine Trip Below P-9.
-i;:-1 Console Alarm RC PRESS DEVIATION HI. S2.0P-AB.PZR-0001, Pressurizer Pressure Malfunction.
~-
c.l OHA G-44, COND POL TRBL. S2.0P-AB.CN-0001 Main Feedwater/Condensate System Abnormality.
I "d:l Console Alarm RC LOOPS TAVG-TREF DEVIATION. S2.0P-AB.ROD-0001, Immovable/Misaligned Control Rods.
I Answer db I !Exam Level I j R I Cognitive Level I IApplication ! ,!Facility: ' ISalem 1 & 2 I iExamDat:: I J 12/19/2016j I,2.4.45 _ _ 1Ro Value: !I 4.1 I/SRO Value. !j4.3 I Section.'!~ RO Group: I 1i:SRO Group: I 1I 5r.43 D
' ~*,,*',"';><
,/ i .11 I
,KA::I 000054G445
- system/Evolution Title
- j_L_o_ss_o_fM_a_in_F_e_e_d_w_a_te_r_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___,! 'o54 H '
- KA Statement
- 1 Ability to prioritize and interpret the significance of each annunciator or alarm.
1 Explanation of] 55.41.b(7, 10) The condensate polisher trouble alarm will be in alarm due to the CN108s AND the CN109 being open at the same 1
Answers: time. Dis incorrect because RC loops Tavg-Tref deviation will be expected as rods are driving in due to the turbine runback to 65%.
~
The ARP has operators place rods in manual, and if not successful at restoring conditions, going to AB.ROD-01. Bis correct because the RC pressure deviation would not be expected, since the setpoint (+75 psig deviation)equates to when the spray valves
--- '* *" MM Tho c----* ""1ves...sbo11ld be sb11! after tbe ins11rne d11e to tbe load reiec:lioo aod lheo tbe larna.arorn int of icu&.a.uL.mrl.-..
I motion. The alarm response directs entry into AB.PZR-0001.-A is incorrect becau~e G-3 will be in alarm since it receives input from I the EHC Control and Status computer, which has a Loss of Feed pump Runback alarm in, and the ARP directs performance of
[ SO.TRB-2 to reduce power if a steam valve has shut. This question meets the K/A because the operator must be able to distinguish I between expected and unexpected alarms for the loss of feedwater, and prioritize them in order to know which would require action in an abnormal Response Procedure.
I Reference Title
., Facility Reference Number !Reference Section l I i Page No. [Revisi;;-~
i I Main Condensate Feedwater Abnormality "S2.0P-AB.CN-0001 II II 112a I I II H If ii I I II II 11 11 i
!LO. Number Objectives I CN&FDWE016
!Material Requiredfor examination.* 11 fQue~tionSoun:e: ** j jFacility Exam Bank I!Question Modification Method: lDirect From Source l iused puring Training ProgramJ D
/aue~tion source Comments;
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11 3267
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I lcorriment
- I I I I
RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
!Question Topic l IRO 18 Given the following conditions:
- Unit 2 was operating at 100% power when a loss of all AC power occurred.
- 15 minutes after the power loss, operators have locally started 2B EOG.
Which of the following is an action that is REQUIRED to have been performed PRIOR to energizing 2B 4KV Vital bus, and why?
,---c
~ Shed non-essential DC loads to extend the time the Vital Instrument Inverters can power their AC loads.
b.1 Initiate and reset SI to prevent the auto start of a centrifugal charging pump and possible thermal shock to the RCP seals. I
.c. I Deenergize ALL SECs and depress stop PBs for SEC actuated components to prevent overloading the 2B 4KV vital bus .
~
d._: Start the Station Blackout Compressor to provide air for operation of 21-24AF11, AUX FEED-SIG LEVEL CONTROL VLVS, to prevent over feeding the SGs when 22 AFW pp starts.
I IAnswe_r:J ~ :Exam~ ~ 1Cognitive Level J 1Memory I ~: 11 Salem 1 & 2 I E_x~lll_?~ j 12/19/201611 BI 000055A203 I EA2.03 I RO Value: I[Ifil" [SRO Valu=J@!Section: II~ .RO Grou~ LJ !SRO Group:' LJ ~s:43 L*-- ,,,..,.,
D
'System/Evolution Title ;
KA Statement:* I Ability to determine and interpret the followinq as they applv to Station Blackout:
IActions necessary to restore power Ij 55.41.b(10)
Explanation of Answers: I The Continuous Action Step for energizing a deenergized vital bus with an EOG comes AFTER the step to deenergize all SEC's. The Bases Document states on page 15 that the reason to deenergize the SECs and depress the Stop PB for all SEC controlled safety related loads is to prevent the bus from overloading. It additionally states that a further reason is to prevent l C-I charging pump automatic start and possible thermal shock to the RCP seals. SI is initiated at Step 21 NOT to prevent a charging 011mo from ri moino._bj1i.J::ath.ec to oreveot the SI actL~alli:mrnentJ.hat..IAlilL.a.ccu~ -- ;~ I I ~estored. Non essential DC loads are shed at Step 35 to extend th~ batteries power capability. The- SBO is started as part of I
I Blackout Coping Actions in Attachment 2 Part A of AB.LOOP-1. All the distracters are actions which will be taken during an extended loss of all AC power, but the correct answer is the only one that is required to be performed AND has the correct reason for doing it prior to power restoration. D will be performed, but it is NOT the correct reason, and is required within 60 minutes of Blackout. A and B will be performed, but are not required to be performed prior to power restoration.
Reference Title ..
Facility Reference Number !:Reference Section I *Page No. ! iRevision I Loss of All AC Power 112-EOP-LOPA-1 11 1117 1130 I I II ll 11 11 I I II II 11 IL L.O. Number Objectives OPAOOE007
!Materfal Required for Exaininatior( !j I
\Question' Source: .. : Facility Exam Bank I'Question Modification Me!hod:
- f Direct From Source !!Used During Training Program I D i~~~~~~~~:l _________________________________________I iComment I I I I I I I
RO Skyscraper I SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
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l~uestionTopic 1 *~-----------------------------------------------'
Given the following conditions:
- Unit 1 is operating at 100% power.
- The crew is performing S1 .OP-ST.SJ-0001, lnservice Testing - 11 Safety Injection Pump.
- 11 SI pump is running.
- A loss of all off-site power occurs.
- 1B 4KV vital bus locks out on Bus Differential.
Which of the following describes Safety 1n*ection pump status 2 minutes after the loss of off-site power?
ld-:-1 NEITHER SI pump is running.
~~[I::} ~~v~ ~ ~~L~J !Application I !~acttitY:l lsalem 1 &2 Ir-~~~ j 12/19/20161 lajloooo56A203 1~-:-~j~~Q]"~e:J@'.!~~l~~~LJ~~~OJ ~511 D
- systE!lnlEvo1uu~hl ~6__
IKA Statelll~nt: Abilit to determine and interpret the followin Operational status of safet in"ection pump ie)(planation of 1 55.51.b(8) neither SI pump will be running after a loss of off-site power with NO SI required. A is incorrect but plausible if it is
~swe_rs:___ " thought that the 11 SI pump breaker would remain shut during the response, and the pump would restart. Bis incorrect but plausible if it is thought that only 12 SI pump would start because 11 SI pump was originally is an abnormal configuration. C is incorrect but plausible if it is thought the SECs would load both SI pumps, which it would only do if there was an accident signal
- ' ' I ' * * '
No. 8.~n
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1============1=========-;=====::::::::::.:::::==:::::. =::::::'.
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~L~u~r __ J Objectives I ABLOP1 E001 I I
1Material R~9uire~ for Examina_tion .i I 11
'auE!stionsourc~:j j_N_e_w_ _ _ _ _ _~I [QU~stionModiflcatio~ Method:- :_1, _________.I ~sE!ci ou_ring Training Program' o
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!Question s_~_r-ceCommentsl I I
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Comment I I I I I I
RO Skyscraper I SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List r Outline Changes I
~uestie>n Topic 1 IRO 20 I Given the following conditions:
- Unit 2 is at 100% power
- A loss of 2A 115 VAC Vital Instrument Bus occurs.
Which of the following describes the impact of the loss on the AFW system if a reactor trip with no SI occurs before the bus is recovered?
l;J
- a. 21 AFW Pump will have to be started manually.
hl Operators must dispatch an NEO to locally throttle 23AF21 and 24AF21.
,b.
~
6 21 AFW Pump may trip during the automatic start because 23AF21 and 24AF21 are failed open.
I Id. I Operators must press the PRESSURE OVERRIDE DEFEAT pushbutton for 21 AFW Pump before gaining control of 23AF21 and 24AF21.
~s~ lb I ~xamle~ IR I ~gnitiveLevell IApplication I facility] !salem 1 &2 I ~ExamDate:j I 12119120161
.. -.. ,,,..~
~1000057A106 1~1*~-~~a~@~~~~~~~~!~~~e>~O~~r~~o ~'?~1 o
-~
~temi~volution Title1 (Loss of Vital AC Instrument Bus I 057 __- I 1*--"----.
J'_(A Statement:" as the appl to Loss of Vital AC Instrument Bus:
ents for which automatic control is lost
- Explanation of I 55.41.b(?) Bis correct because 23AF21 and 24AF21 fail closed due pressure override as power is lost to the pressure transmitter.
1Answers: . An operator is dispatched at Step 13 of AB. Power is also lost to the valve controllers. A is incorrect because 21 AFW Pump would
~. * - - ..._. - only have to be started if an SEC actuation occurred, and the stem states no SI has occurred. C is incorrect because the valves fail closed, Dis incorrect because power is not available to the valve controllers.
-- -*-**--.. --* - -... - . . - - * * - ,..__ , .... _ ..._ ..- .. _ .. _ .....- . , - - * - - * - - - - i r - * - - - ---.. -*-~
L._._____ -~e~~. *--_.. ___ _J '_ ~i~e!!':!n~u~r_J ~~e~e~__J *. ~. N~ l~io~
ILoss of 2A 115 VAC Vital Instrument Bus l!s2.0P-AB.115-0001 14 I !20 I I f I I 1
i.o.-*N-um-be-r---*-~
~--.-.*---*--*--' Objectives IAB1151E003 1_ __..
!Material Required for Examination j I jQuestion I Source~ Facility Exam Bank I [Question Modification Me-thod: _J Direct From Source
.. .--.*----**--1 ..----------------------------------------.,.!
l~uesti(.)n Source ?C>mments 1 IC.:. ...... -*n.
I I
l
RO System/Evolution List SRO SystemJEvolution List Outline Changes Given the following condition:
- Operators are performing actions in 2-EOP-FRCC-1 , Response to Inadequate Core Cooling.
Which of the following identifies how the PZR PORVs will be operated after starting ALL available RCPs with CET temperatures above 1200°F?
rc:1 IOpen ONL y ONE PORV.
- ~.JI Open BOTH PZR PORVs.
l~~~l@=J ~~~.~'~~]I Memory I ~~i m 1 &2 --c>ate: I 12119120161
[{A:J!oooo74K202 1 1 ~~ j 1~~Q]},~a§j~~~j~~~OJ~G-~]~ ~5::~ D
~ystem/~volutio~Title] !_1n_a_d_eq~u_a_te_c_o_re_c_o_o_li_n~g----~---------------------~---'I 074 __J
_KA Statement: Knowledge of the interrelations between lnadeauate Core Cooling and the following:
PORV I
,Explanation of1 55.41.b(10) RCPs will be started at step 25 if CETs are still >1200°F, to clear the water in the RCS intermediate leg and permit the circulation of hot gases from the overheated core to circulate through the steam generators. If RCP(s) restart is not effective in
!Answers: .
decreasing CET temperature <1200°F (it is not per stem), the PZR PORVs (BOTH) will be opened at step 25.3 to help reduce RCS pressure to allow ECCS injection.
~-*-_**----=:_*::::::::R-efi_e~re_-n_c-_e~t_it-l_e-=_-_- . .**_.~----. _ Qaciiity Refe-rence Number- I ~~e~n --=:J [P~- ~0~ 1 I
___1_______...;.___1 Basis Doc
~IR"-e-s-po_n_s-'"e-to-ln_a_d-eq_u_a-te_C_o_r_e_C_o_ol-...in_g_ _..;..__1.~l-2--E-O'-P--F-R_C_C 1138 j 30 I i==================~l~============~I lj I I
- ~~~~~~~~~! I Ii I I c---- *----*-- I 1L O._t-j_u_m_b~r___......~ Objectives I FRCCOOE002 I I
'--~
~!erial R~quired f()r Examination j I 11
~s~ion Sou~ce: 1 j_N_e_w_ _ _ _ _ __.l jQuestion Modificati()n Met_l_lod: :,,! _ _ _ _ _ _ _ _ __,I !used During Training f)_rogrci_rlll D
!~u_e_s~-i~n_s_o_u.-r~~-c-o-~-~entsj I I
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RO SkyScraper I SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List I Outline Changes I
\0.uestion TopiCJ I RO 22 I Given the following conditions:
- Unit 2 has experienced a SBLOCA.
- Operators have transitioned from 2-EOP-TRIP-1 Reactor Trip Response, to 2-EOP-LOCA-6 LOCA Outside Containment.
- The 21SJ49 COLD LEG ISOLATION VALVE has just been closed in an attempt to isolate the leak.
Which choice describes the response which would indicate successful leak isolation, and the next action to be performed IAW 2-EOP-LOCA-6?
11 I
La~ RCS pressure stable, open 21SJ49.
~
[Cl I RCS pressure stable, stop 22 RHR pump.
RCS pressure rising, stop 21 RHR pump.
I
~I I
ld*j RCS pressure rising, close 21RH19 RHR DISCHARGE X-CONN.
I
'Answer! j c I '.Exam l..evel 1jR I 1cognitive Lev~ IMemory l iFacilitY:l ISalem 1 & 2 I rexamDate:j I 12/19/20161 l,~jj D
¥' >>: """""
~!OOWE04A101
~stelll/Evol~t~~~ ILOCA Outside Containment 1 [Eo4- _ 1
]<A Statement;' Abilit to operate and I or monitor the followin as the appl to LOCA Outside Containment:
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
!Explanation of 55.41.b( 10) Dis tractor a is incorrect because after the leak is isolated by closing the 21SJ49, the procedure leaves it closed. Also 1
Answers: . stable RCS pressure is not the required RCS pressure indicating leak is isolated. C is correct because rising RCS pressure
- ' indicates leak isolation, and the next step is to stop 21 RHR pump because the RHR system is split and there is no discharge path.
Dis tractor D is incorrect because the 21RH19 would already have been closed at step 2. Distractor b is incorrect because both
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~C>:~rn~_r ___ 1!
OCA06E002 I
- Material Required for Examination -~ I I
euestion_Source:J Facility Exam Bank jfa_uestion Modlfication Method:
L'-*--**---*---****-**J
'I Direct From Source
!-Que~~n Sou!_<:eCommerrtsl 1 . - - 1 2 - 7 0 - 8 6 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . . . . . _ , . 11 I .. ..
icomment I I
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RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes iauestion I Topi~ RO 23 Given the following conditions:
- A loss of heat sink has occurred.
- The operating crew is establishing RCS Bleed and Feed in accordance with EOP-FRHS-1, Loss Of Secondary Heat Sink.
- The RO opens one PORV. He reports that the second PORV will NOT open.
Which one of the following describes the consequences of the PORV failure?
~*
!a. ALL SGs will require depressurization to inject the alternate source of feedwater.
- b. The RCS will rapidly re-pressurize when the SGs empty, resulting in a violation of a RCS Safety Limit.
~
IC.
l___.
Bleed and Feed cooling of the RCS must be terminated and secondary depressurization to inject condensate pump fl initiated.
id.
L~
The RCS may not depressurize quickly enough to ensure sufficient SI flow to provide RCS heat removal, and ot, *-*
~~~
... ~
h<wa to be established.
Ans;er 11 d I !Exam Level j IR I jcognitive Level JI Memory I :Facility: j ISalem 1 & 2 I iExamDate: ; I 12/19/20161
[KA:,I OOWE05K301 Syst~llll_~!'_olution Title I E05 rt<A-Stcit;.;entj Knowled e of the reasons for the followin responses as the appl to Loss of Seconda Heat Sink:
Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivit chan es and o eratin limitations and reasons for these operatin characteristics.
IExplanation of i 55.41.b(S, 10) Distractor c is incorrect because Bleed and Feed is not terminated if only one PORV is open. Distractor b is incorrect Answers: I because the RCS Safety limit is 2735 psig and will not occur with the PORV open. Distractor a is incorrect because action to align condensate pumps is already taken, and not as a contingency to Bleed and Feed. D is correct because FRHS Basis document describes the consequences of not having both PORV's open, and it is D.
r** -
~.Number .
0 FRHSOOE009
_J I
'Material Required for Exaf!lill_ation II
!ouestion Source:
I Facility Exam Bank I 10uestion Modificatio-n Method: .. IDirect From Source
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~ue_stio.'1 Source Comr11_~~ I I
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RO Skyscraper I SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List I Outline Changes I
~~est~o~ToPICl IRO 24 Given the following conditions:
- Unit 2 has experienced a steam line break inside containment.
- Operators have entered FRTS-1, Response to Imminent Pressurized Thermal Shock.
Why will the operators be instructed to terminate SI and start RCP(s) if possible?
~ --.-** _ by FRTS-1 requires SI to be secured. RCPs are started to provide the ability to use spray to depressurize the primary.
- b. The soak required by FRTS-1 requires SI to be secured. RCPs are started to provide mixing of cold SI and warm reactor coolant water.
- c. Safety Injection flow is a significant contributor to any cold leg temperature decrease or overpressure condition and must be terminated.
RCPs are started to minimize temperature gradient across SIG tube sheets. I id., Safety Injection flow is a significant contributor to any cold leg temperature decrease or overpressure condition and must be terminated.
L ___ J RCPs are started to provide mixing of cold SI and warm reactor coolant water. I jAnswer' Id I ~xam l.eve1i IR I cog11_itiveieve1] IMemory I Facility: lsalem 1 & 2 I Exam Date: I 12/19/20161 c
~:!! OOWE08K101
- -'~_yaiue: @"~ah.1~~~1J]"~:_Jj~ ROGroup:ILJ~~~LJ ~--~3 D
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ls}tste.n/EvOMion TitlE!_] ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~---'
E08 L.
[l<A Statement: ~edge of the operational implications of the following concepts as thev apply to Pressurized Thermal Shock:
Components, capacity, and function of emergency systems.
Explanation of I 55.41.b.(10,8)A- incorrect - purpose for RCPs is not priority in FRTS-1, soak is not basis for SI. B - incorrect - soak not basis. C -
Answers:
~~*
[ Facility RefE!_re~_ce Number IReferellce L _ _ ...
Section 1 ** Page N~ [~e\li~~
IResponse to Imminent Pressurized Thermal Sh 112-EOP-FRTS-1 I ii 1130 I I II I II 11 I I II I 11 11 I Objective FRTSOOE007 I
I Material Required for Examination i
- I II Question Source: j I Facility Exam Bank I[Question Modification Method: IDirect From Source 1lused During Training Program D I
Question Source Commellis
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!Question Topiel IRO 25 I Given the following conditions:
- Unit 2 has tripped from 100% power due to a Loss of Off-Site Power.
- Operators are performing a cooldown IAW 2-EOP-TRIP-6 NATURAL CIRCULATION RAPID COOLDOWN WITH RVLIS.
Which choice identifies the MINIMUM RVLIS Full Range level required to be maintained during the cooldown, and its significance?
~ 70% to limit steam entering the RCS hot legs.
1---c
~ 100% to limit steam entering the RCS hot legs.
70% to ensure positive level indication of RCS.
c.
I d.! 100% to ensure positive level indication of RCS.
I
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Answer I Exam Leve_I IR I cogniti~e Level ,IMemory I !Facility] Isa1em 1 & 2 I .ExamDate: 11 12/19/20161
[KA:] IOOWE1 OK303 I ~K3.3 _~_J ~2\fal~~ ~:SRO Value: I[TI}[~~ I~ ~Cl_llP~ LJ SRO Group~ LJ :~s:~~: D
~y~tern/~voiution Title ! INatural Circulation with Steam Void in Vessel with/without RVLIS I ~~~-]
KA Statement: ' Knowledge of the reasons for the following responses as they apply to Natural Circulation with Steam Void in Vessel with/without
~LIS:
nipulation of controls required to obtain desired operating results during abnormal, and emergency situations.
Explanation of 55.41.b(10}74% is minimum allowed at step 10, and get into a do loop until it is satisfied. The Bases Document states that if steam
'Answers:
enters the hot legs, there may be some potential for it to reach the top of the SG U tubes, thereby disrupting the natural circulation flow circuit. By monitoring RVLIS and limiting the void growth to the top of the hot legs, the potential for introducing voids into the SG Utubes is minimized. Setpoint was changed from 74% to 70% current revision of EOPs.
---*--* . - -* -* 1 Reference Title
- -*** -****** I . Fac_i~ity Reference NurJibE!r . . ] :~E!!erence Section I P;;i~~ [Revis101"1:
INatural Circulation Rapid Cooldown with RVLIS 112-EOP-TRIP-6 ii Bases Document 1122 1130 I I I 11 11 11 I I I II 11 11 I 11-.o. Number Objectives I TRP004E004
- 1V1ate.r!al Required for Exa,1nination 1 l I IQuestionSource: , j Previous 2 NRC Exams I'Question Modific~t!on_Method: :j Editorially Modified I [USed. During-- Training Program-~ D I
t__ -
Questio~-Sou~ce Commentsj ~sed on Salem December 2014 NRC exam (2 exams ago.) Setpoint was changed from 74% to 70% current evision of EOPs in Dec 2015).
... ~-"" ...
I icornrnent . ........ I I
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RO SkyScraper I SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
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Que st ion Topic I *---------------------------------------------~
Given the following conditions:
- A LBLOCA occurred on Unit 2.
- 2C 4KV vital bus locked out on Bus Differential.
- Both 22 and 24 CFCUs failed to start in low speed and cannot be started.
- After entering 2-EOP-LOCA-3, Transfer to Cold Leg Recirculation when required, the crew has transitioned to EOP-LOCA-5, Loss of Emergency Recirculation when neither SJ44 valve opened.
- Containment pressure is 18 psig.
- The crew is performing Step 9 to determine the required number of Containment Spray pumps to be operated.
Which of the following identifies the Containment Spray pump(s) which will be in service if Step 9 is completed seven minutes after the RWST Lo Level alarm was received?
- a. BOTH Containment Spray pumps.
R Containment Spray pump.
L~~~ Level ~ Cognitive Level j Application I ~~~ ISalem 1 & 2 ! IExam Date: ' !________,
~!ooWE11K102 !!EK1.2 l~~Vatue::Q]}SROValue:*[DJ*~~!~~-~LJSROGroup:!LJ 55.43. D System/Evolutio_~~ ~-~~ :,
e of the operational implications of the followin concepts as the appl to Loss of Erner enc Coolant Recirculation:
al, abnormal and emergenc operating procedures associated with Loss of Emergenc Coolant Recirculation .
Explanation of
- 55.41.b(10) Table C uses RWST level, Containment pressure, and the number of operating CFCUs in Low speed to determine how Answers: many containmernt spray pumps are required to be run. LOCA-3 was entered with RWST level at 15.2', and with 2C 4KV vital bus deenergized will be depleting at-13,000 gpm, with 2 RHR, 1charging,1 SI, and 1 CS pump running. This will require over 9 more minutes of injection before RWST level would be lower than 1'. With the stem stating that Step 9 is complete 7 minutes after 15.2' in E?\LVSI then Table C will indicate> * * *
- Ideenergized, so 21 will be run. If RWST drain do~n ~lculation is.incorrectly pertormed and it is assu.med RWST level is <1 ',then
'I NO CS pumps would be required. The BOTH distracter is for RWST level between 1-15.2' if either containment presure is >47 psi , or if no CFCUs were runnin .
Reference Title r- Facility Reference Number .Reference Section __ J *Page No. : ~!~~~
ILoss of Emergency Recirculation 112-EOP-LOCA-5 II Basis Doc I!28 ! I30
,~=
- ===::::
'!~------------'*----------' ---~ '~-.......;
LO. Number Objectives
Material Required for Examination
- -- - i !RO 26 2-EOP-LOCA-5 Sheet 1 AND S2.0P-TM.ZZ-0002 TANKS CURVE RWST Ii jouestion Source: : New I I 10uestion ~odification Meth~~: I 1 I rused During Training Progra~
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- auestion Source Comments .
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RO Skyscraper I SRO Skyscraper I RO System/Evolution List f SRO System/Evolution List I Outline Changes I Question Topic'. I RO 27 I Following a SBLOCA inside containment concurrent with a faulted SG inside containment, the following conditions are noted:
- RCS subcooling is indicating 10°F.
- RCS pressure is 1380 psig.
- Containment spray actuation has occurred, but neither Containment Spray pump started.
- The crew is implementing 2-EOP-FRCE-1, Response to High Containment Pressure.
I Which of the following describes why the Reactor Coolant Pumps (RCP) are tripped under these conditions?
~ To prevent RCP motor damage due to lack of cooling.
I b.' To minimize additional loss of reactor coolant from RCP seal leakoff.
-- I
"'C.! To prevent subsequent thermal barrier damage due to backflow of RCS fluid.
__J I
- d. To minimize possible subsequent core damage due to pumping a two-phase mixture.
--~
II 1
Answerl a I I Exam Lev_:IJ IR I !Cognitive Level !Memory I \Facility:*
j Salem 1 & 2 I [Exam_D~te: 1 I 12/19/201611 j _E_K_1.2_ _' RO Value: II i 3.7j ,Section: I~ iRO Group:: I
$"'{~,***<,".._v~*;~c KA::jooWE14K102 3.2j SRO Value:
I 21 1SRO Group: j 21 -05.43 D
'system/Evolution Title ! IHigh Containment Pressure KA Statement:: Knowled e of the operational implications of the followin concepts as they appl to High Containment Pressure:
Normal, abnormal and emergency operating procedures associated with Hi h Containment Pressure).
Explanation of* 55.41.b(10,3) CS actuation occurs at 15 psig in containment, as well as Phase B isolation, which shuts RCP CCW cooling inlet and Answers: outlet valves. Per FRCE-1 basis document page 4, " ... RCPs are tripped since component cooling water to the RCP seals and motors is isolated." Bis incorrect but plausible if RCP seal package operation is not understood (running pump to secured pump).
C is incorrect but based on having no CCW flow to thermal barrier. D is incorrect but plausible if it is thought a two phase
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Reference Section No. i Revision:
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- =======================~!~===============~===========~==:::::=:'.1~3=0===
~==========~=======:!!======:.==:::.::::,I~==
LO. Number I I Objectives FRCEOOE006 I I
I Material Required for Examination 11 p
I
'Question Source: ! Facility Exam Bank I!Question Modification Method: IEditorially Modified j 'used During Training Program I D 1
I Question Source Comments: Replaced _a distracter which used to have containment spray water in it, as new rev of EOPs requires CS pumps
- NOT running to enter FRCE-1. l I
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RO Skyscraper ( SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List I Outline Changes I
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I Question Topic' RO 28 I I
--*--~-----
Given the following conditions:
- Unit 2 is operating at 4% power during a plant startup.
- 22 RCP trips.
Which of the following identifies the Tec_h S12ec re!;Juired action for the RCP trip?
ia* 1 Be in Mode 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
-- ~
ib. ~~" ***---
--- I c.' I Immediately initiate corrective action to return 22 RC loop to operable status as soon as possible.
~~*-.
I
~ Suspend all operations involving a reduction in boron concentration of the reactor coolant system.
I
.Answer~ I~ I Exam Level IR I I Cognitive Level I Memory 1 IF~~iUtyj ISalem 1 & 2 I.ExamDate: !
I 12/19/20161
- ,~** '7
~_:_:I 003000G222 System/Evolution Title : IReactor Coolant Pump System KA Statement* I Knowledge of limitino conditions for operations and safetv limits. I Explanation of I 55.41.b(3, 10) With the reactor in Mode 2, LCO 3.4.1.1 states all reactor coolant loops shall be in operation. The ACTION with less Answers: ______J'
__________ than all loops in operation is to be in HSB within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Bis incorrect but plausible as it has the correct action but wrong time. c and D are incorrect but plausible as they are actions taken for Mode 4 and Mode 3 RCP operation respectively.
Reference Title Facility Reference Number j Reference Section 1: Page No. I Revision ISalem Tech Specs I j Section 3/3 4.1 l 13/4 4-1 1I2s2 I I I II ii 11 I I I II ii 11 I L.o.N~"be-r- i TECHSPE015
_Question Source: I
! Facility Exam Bank I'Question Modification Method:
.--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~!
I Direct From Source I Used During Training Program
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Question Source Comments' Comment
RO System/Evolution List J SRO System/Evolution List Outline Changes
- Unit 1 is operating a 100% power.
- After performing a normal dilution for RCS temperature control, the START pushbutton for CVCS Makeup Mode Select was NOT depressed when returning the CVCS Makeup System to automatic.
Which of the following describes the effect this will have if VCT level were to continuously lower with NO operator action?
1SJ1 and 1SJ2, RWST to Charging Pump Suction valves will open automatically when VCT level reaches the lo-lo level setpoint, and 1CV40 and 1CV41, VCT Outlet Isolation Valves, will shut automatically.
1 and 1SJ2, RWST to Charging Pump Suction valves will open automatically when VCT level reaches the lo-lo level setpoint, and 1CV40 1CV41, VCT Outlet Isolation Valves will remain open.
lution will occur when the Primary Water pumps start at 14% VCT level with no boration flow aligned to the CVCS Blender.
The VCT will empty and the charging pumps will lose suction.
,A~swe;:l ~ ~xam Level . ~ Cognitive Level ~ j Application ! ~acility: 1 ISalem 1 & 2 I i~~m_i:>~~J I 12/19/20161 gj 004000K404 IIK4.04 , .RO Value: IG];sRO Value:lf}TI!Section: 1j~ 'Ro Group: L J SRO Group:;LJ 55.43. D 1System/Evolution Title I j Chemical and Volume Control System 004 KA Statement:. Knowledqe of Chemical and Volume Control System design feature(s) and or inter\ock(s) which provide for the following:
Manual/automatic transfers of control Explanation of I 55.41.b(7) The CVCS START PB must be depressed to align the CVCS M/U system to whichever mode was selected (BORATE,
'Answers: DILUTE, ALT DILUTE, AUTO). Dis incorrect but plausible if it is thought that the SJ1 auto open interlock is based on having the CVCS M/U Mode Selector in AUTO and START. C is incorrect but plausible if it is thought that Primary Water pump operation would occur based on last position of CVCS M/U system (dilute per stem) when the auto makeup setpoint would be reached at 14%
l------......Lllrn~teDJ'nOJ.~i.l.Ll\/r:::IJ.f>~e S 11andS12 ooe.n.,a.uJru:n.a.tka.212JE~Le.Llos.tJ.od.o..\1CI...Lf>..llill and once the>~4,()_;and .J
!CV41 shut to transfer suction of char~ing pumps to RWST. . *
- I Reference Title I! Facility Reference Number i ,Reference Section J Page No. I Revision' 1
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- :l ! I 16 I ==
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_ _ _ _ _ _ _ _ ______,!! 11, _ _ _ _ _,,,q :=I I
'LO. Number CVCSOOE006
_J Objectives Material Required for Examination 11 II
,Question Source: [!New I!Question Modification Method: I I fliSed During Training Program D!
Question S~urce Comments; I 11
- comment I
I I
. RO Skyscraper fouestion_r~PTc]
I SRO Skyscraper RO System/Evolution List
.-R-0_3_0_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __..,
SRO System/Evolution List Outline Changes Given the following conditions:
- Unit 2 is operating at 100% power, steady state.
- The Charging System Master Flow Controller is in MANUAL.
- A malfunction in the H2 pressure regulator supplying cover gas to the VCT occurs, and VCT pressure rises from 25 to 35 psig.
Which of the following describes the effect this will have on CVCS when steady state conditions are established?
~ Charg I
Lb*! Letdown flow will rise.
I I Charging flow will lower.
e:J I
[cf.J ILetdown flow will lower.
[~ ~ 'Exam Lev:_IJ ~ iCognitive Level : Application I ! Facility: . ,Salem 1 & 2 I Exam Oat~ 12/19/20161
~I 004000K526 I. K5.26 :Ro Value: [ITI SRO Value:: [E} Section: i!~I RO Group:j LJ SRO Group: LJ 65.43 D \db*::<,\,,~
lsystem!Evolution Tit~ IChemical and Volume Control System I 004 KA Statement:: concepts as the appl to the Chemical and Volume Control System:
!-----"'-----"-'--'--'-'---"--"-_;_;;_;;,_;._;_..c.__.;.._;;__;__;_-'--'><...;;..;.....;..;..;;..c;~;;_;;_;;;._;;;...:...i.:..J;.;.;<,_;;.;;,...;;_;;_.:....;."""'~'-"'.;.;;;_..;..:c.c:;;..;.;_;;__;:...:...;..:;_;c:.....:c.;...;;..,,;,;;.;.;.;..;__....i.
Explanation of: 55.41.b(5, 7) Raising VCT pressure will cause NPSH available to the charging pumps to rise. With the flow controller in manual, and Answers: more suction head available, pump flow will rise. The letdown pressure control valve will respond in automatic and letdown flow will remain the same. Static pressure at the pump suction: An increase in surge tank level, increase in the pressure above the liquid in the surge tank, increase in booster pump output, or opening of the pump suction valve would Reference Number
- Lo. Number I CVCSOOE004 Material Required for Examination 11 Ii
,Question Source:
- _J 1 I New 1,0uestion Modification Method: i! ! 'Used During Training Program j D Question Source Comments I I l
I I I I I l
"RO SkyScraper I .SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
!Question Top&J ! r R - 0 _ 3 _ 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - : 1 Given the following conditions:
- Unit 2 is in MODE 4.
- 21 RHR loop is in service in SOC mode.
- 22 RHR loop is O/S and aligned for ECCS.
Which of the following would cause the temperature of the water flowing to the RCS from the RHR system to RISE?
~ 21SJ49 RHR DISCH TO COLD LEGS is shut.
I
~ 2RH20 RHR HX Bypass Valve is throttled open.
~ 21RH18 RHR HX FLOW CONT VALVE is throttled open.
I
'.Ans-;:.e.:1 c I Exam Leveil ~ 1cognitive Level 11 Application ! !Facility:, ISalem 1 & 2 ExamDate: 11 12/19/20161 I
KA:. 005000A 102 I!A1.02 ____J RO Value: '@.SRO Value:: [TI" ;section: Ij~ RO Group: LJ ;SRO Group:: LJ iSystem/Evolution Title i IResidual Heat Removal System KA Statement: : Ability to predict and/or monitor changes in parameters associated with operating the Residual Heat Removal System controls includinq:
RHR flow rate Explanation of : 55.41.b(5) A is incorrect because with the RH19s open, the discharge from 21 RHR HX will flow through the normally open 22SJ49.
Answers: 1 Bis incorrect because the valve is normally shut, and with the 22RH12 shut there won't be any flow through 22 CCHX from 21 loop anyways. C is correct because bypassing flow around the in service HX will cause system temp to rise, as more warm RCS water is mixed in with the cooled RHR HX outlet water and returned to the RCS. Dis incorrect because opening the 21 RH18 will increase II
- ~...... +hr'" ..... t... +L-. .... in ~~nlimEHR ~X. ca11sio9 QI rtlet temp to lo'Af.e'"
IRHR Simplified Reference Title Facility Reference Num~ .Reference Section j j 205332-SIMP I
- ; Page No.
11 i
112 Revis.ion I
I Iinitiating RHR 11 S2.0P-SO.RHR-0001 I 11 1129 I I 11 I 11 11 I lLO. Number Objectives I RHROOOE004 Material Required for Examination 11 II Question Source: ;IFacility Exam Bank I[Cluestion Modification Method: IDirect From Source I;Used During Training Program I D
,Question Source Commentsj 113-01 C RO 31 I
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RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
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[Question Topic I RO 32 I Given the following conditions:
- Unit 1 was operating at 100% power when a SBLOCA occurred.
- During the performance of EOP-TRIP-1, RCS pressure has lowered to 1600 psig.
- 11 SI pump failed to start.
- Current TOTAL ECCS injection flow is 400 gpm.
Which of the following approximates TOTAL ECCS injection flow if 11 SI pump is successfully started?
~ 400 gpm.
I
~
I
'c. i
~
~
I
'd.i 1000 gpm 11
- Answer i a I I Exam Level i IR I !Cognitive Level 1 IApplication I 'tacility: 11 Salem 1 & 2 j !ExamDate: 11 12/19/201611 IRO Value: i@ISRO Value:@ ~JI~ RO Group:JLJ!SRO Group:,LJ 5B;~3 0
'KA::I 005000A117 I A1.17 1
,System/Evolution Title; IEmergency Core Cooling System KA Statement: i Ability to predict and/or monitor changes in parameters associated with operating the Emergency Core Cooling System controls including:
ECCS flow rate r
'Explanation of i 55.41.b(8) Shutoff head for an SI pump is 1520 psid. Starting one at 1600 psig in RCS (with suction from 41' of RWST level,)
~swers: ~~* would provide no additional ECCS flow. The 500 gpm distracter if it is thought that shutoff head is slightly higher than 1600 psig.
The 1000 gpm distracter is if-full SI pump flow were added to ECCS flow. The 800 gpm is flow at 1082 psid.
1 Reference Title _Jr Facility Reference Number 1 Reference Section [ [ Page No. [ .Revision IECCS Lesson Plan If NOS05ECCSOO I !127 1I9 I I II ! ll 11 I I ii I II Ii I iL.O. Number I ECCSOOE008 Objectives I
DIII 1Material Required for Examination_J
!Question Source: :IFacility Exam Bank I'Question Modification Method: IConcept Used Iiused During Training Progra.:;;j
[Question Source Comments' 161678 I
'Comment I
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RO SkyScraper ( SRO Skyscraper I RO System/Evolution List
.I SRO System/Evolution List ! Outline Changes I I
!Questio_ri Topic : RO 33 I Given the following conditions:
- Salem Unit 2 has experienced a LBLOCA.
- 21 SJ44 fails to open when demanded and cannot be opened.
Upon completion of EOP-LOCA-3, Transfer to Cold Leg Recirculation, which of the following identifies how the 21SJ44 failure affected the Cold Leg Recirc alignment compared to if the 21SJ44 were open?
-:a. i
~-d Containment spray header flow will be zero because 21 CS36 is interlocked to remain shut. I
-:--1
~ Containment spray header flow will be zero because 21 RHR pump will have been stopped.
iZ!
Containment sump recirc flow will be directed through 22SJ45 and 22CS36 ONLY because 21 RHR pump will have been stopped.
I
- d.11 Containment sump recirc flow will be directed through the 22SJ49 and 22CS36 ONLY because 21 SJ45 is interlocked to remain shut.
I
]Answer 1 Ic I 1Exam Level 1 IR I 1Cognitive Level IApplication I Facility:! ISalem 1 & 2 I fExamDate: I 12/19/20161
[Iii !SRO Value: 1@ Section: II~ RO Group: LJ ls RO Group: LJ
,?~*4.34 D
~~,,
~1006000K301 1!K3.01 I RO Value: i System/Evolution Title' I Emergency Core Cooling System I *_006
.KA Statement: i Knowledqe of the effect that a loss or malfunction of the Emerqency Core Cooling System will have on the following:
RCS 1Explanation of I 55.41.b(S,7) When 21SJ44 fails to open, the procedure will direct stopping 21 RHR pump, and it will remain stopped as long as the Answers: 21SJ44 is shut (step 5.2) The 21SJ45 is interlocked with the 21SJ44 such that it cannot be opened with the 21SJ44 shut. The 21 CS36 interlock is with the RH 1 and RH2 needing to be SHUT before the CS36 can be OPENED. A is incorrect because CS header flow will be provided by opening the 22CS36 since 22 RHR pump is running at step 22. B is incorrect because even though
"' nwc '." *m'."' 1 "" ' haoJ.a.he.e.n...sJapp.ed...thP_nmning RHR pi l!ll!J 1uill he s.u.pply.ir:l.g.J'...S...b.ead..e.r..flo1~L.-OJ.sJ-------* '---- *-- *nr<o.
ALL circumstances if 22 RHR pump is running when the RWST lo-lo level alarm is received, the 22SJ49 isolation to cold legs is shut. The final lineup will be with ALL containment sump recirculation flow going through the 22SJ45 to Charging/SI pump suctions, and through 22CS36 to spray headers.
Reference Title Facility Reference Number
- rReference Section *I Page No. ; ~sion I ECCS Lesson Plan II _jl q 47,52 II I I Transfer to Cold Leg Recirculation lI2-EOP-LOCA-3 II lj _ __J 130 I I ECCS Simplified Drawing 11205350-SIMP II II ii 5 I
[LO. Number Objective~j I ECCSOOE016 I ECCSOOE006 Material Required for Examination 11 !
Question Source: . !New I!Question Modification Method: I I l~sed _During Trainin_§I Program J D Question Source Commen_!:J I I Comment I
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RO Skyscraper I SRO Skyscraper RO System/Evolution List SRO System/Evolution List . I Outline Changes
[<:.i;:;-e~nroi)ic ! ~R=o==3=4=================================================================================='I 1
Which of the following describes the operation of the PRT Vent Vent, 2PR15? 1 The 2PR15 recieves a(n)... ... .
!a I shut signal at 10 psig in PRT.
~~--"J
'dl Iopen signal at 100 psig in PRT.
Answer i a I I Exam Levell ~ ~gnitive Level 11 Appl1cat1on I 1_i='acility: 11 Salem 1 & 2 I ,Exam Date: , I 12/19/20161 I I
- KA: 007000A404 1IA4.04 RO Value: il2.6*I isROValue: q2.6*l lsection: II~ RO Group:!I 11 !SRO Group: I 11 ~~.431 D
!System/Evolution Title , IPressurizer Relief Tank/Quench Tank System KA Statement: ' Ability to manually operate and/or monitor in the control room: l PZR vent valve I Explanation of i 55.41.b(?) PRT vent valve 2PR 15 is interlocked to SHUT on a high PRT pressure of 10 psig. The PRT Rupture Diaphram will
~swers: I actuate at 100 psig in the PRT.
l Reference Title I Facility Reference Number : ,Reference Section i Page No. I ;Revisi~ri, 1
IControl Console CC2 11 S2.0P-AR.ZZ-0012 I ii 51-52 1139 I I I I 11 11 I I I I 11 11 I LO. Number Objectives I PZRPRTE006 Material Required for Examination lI q I
'Question Source: * ! Facility Exam Bank 1 lauestion Modification Method: . :I Concept Used !'Used During Training Program cD
- Ouestion Source Comments I I
!Comment I
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RO Skyscraper I SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List J Outline Changes I
!Question Topic : IRO 35 I Given the following conditions:
- Unit 2 is operating normally at 65%, steady state.
- 22 and 23 CCW pumps are in service.
Subsequently 22 CCW pump trips.
Which of the following describes how the CCW system will respond or be manipulated by the control room crew?
r;I 21 CCW pump will auto start when CCW header pressure lowers to 70 psig.
~
~ 21 CCW pump will auto start immediately since less than 2 CCW pump 4KV breakers are shut.
Ii
'C.
~
The NCO will start 21 CCW pump immediately since the 3rd CCW pump is normally aligned in MANUAL to prevent 3 CCW pumps from operating simultaneously. I
'd.
The control room crew will enter S2.0P-AB.CC-0001, Component Cooling Abnormality, isolate the non-safeguards header, and start 21 CCW pump if CCW header pressure lowers to 80 psig. I
- Answer i a I I 1 Exam Level IR l I Cognitive Level
- I Memory I iFacility: l ISalem 1 & 2 1 IExamDate: 11 12/19/2016!
(m,'~ '"""'*
!KA: 11 oosoooK401 l,[_K_4._01_~ilROValue:ll 3.1l;SROValue:1j 3.3liSection:!l~ 1 ROGroup:j i
11 SROGroup:;I 11 J'i~'.~3 D
!system/Evolution Title , I Component Cooling Water System I !oos -=
KA Statement: Knowledge of Component Cooling Water System design feature(s) and or interlock(s) which provide for the following: I Automatic start of standby pump I
,Explanation oJ 55.41.b(7) Normal CCW system alignment is 2 CCW pumps running in MANUAL, and one CCW pump in AUTO and stopped. A
,Answers: CCW pump selected to AUTO will start when either 21 or 22 CCW header pressure lowers to 70 psig. There is no interlock based
- - - * - - - - on breaker positions, but other system DO have a breaker anticipatory function. AB.CCW could be entered, but no actions will be performed other than ensuring the backup pump started.
Reference Title Facility Reference Number *.Reference Section 1i PageNO:l !'Revision IControl Console CC1 I 1 $2.0P-AR.ZZ-0011 11 ii 92 1160 I I 11 II ii II I I
I I II IIl ii 11 I 1LO. Number Objectives I CCWOOOE006 I!Material Required for Examination j I q
~
Question Source: l IFacility Exam Bank I Question Modification Method: 'I Direct From Source j 'Used During Training _i:>rogra~ D
~stion Source Comments.
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RO SkyScraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
!Question Topic' IRO 36 I Given the following conditions:
- Unit 2 is operating at 4% power holding during a startup.
- 2PS1, PZR Spray Valve, fails open and cannot be shut.
With NO operator action, which of the following protective actions will occur FIRST?
~ Reactor trip on OT/DT.
~
I
~ Reactor trip on High PZR level.
~
I
- C.,
Reactor trip on Low PZR pressure.
I
'dl !Safety Injection on Low PZR pressure.
I
.Answer 11 d I !Exam Level , IR ! !Cognitive Level / j Application I /Facility:* j Salem 1 & 2 I /Exam_Date: _* I 12/19/20161 jA2_._0_2~~I jRO Value: i 3.9\ SRO Value: JI
_,., .... ,.;w I II~ !RO Group:: I 553;~;~ D KA: 010000A202 3.91 ISection: '
1 j ;sRO Group: I 1j System/E~olution Title I IPressurizer Pressure Control System I 01_0_
KA Statement: I Ability to (a) predict the impacts of the following on the Pressurizer Pressure Control System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
Spray valve failures iExplanation of I 55.41.b(?)Low pressure Rx trip is not reinstated until > P-10. D/T is very small at 4% power and would not initiate any protective 11
'Answeffi' 1 *ctioo, '"' it wo"ld be the tic;! pn>teoti'e ootioo to oow1 ' ' 100% powe1. PZR Je,el wHI oot ri*e to the R' !lip *etpoiot T h : J l pressure SI was reinstated during heatup/pressurization when RCS pressure was >1915 psig.
Reference Title
' Facility Reference Number i Reference Section , ' Page No. : Rev~
IFluency List II NOS05FLUNCY-09 ii 119 I
!I II I
I "
11 11 11 1 I I
I Lo. Number l FLUNCYE002 Objectives Material Required for Examination ! I II 1
Question Source: I IFacility Exam Bank l Question Modification Method: I Direct From Source I;used During Training Program lo
!Question Source Comments!______J I I Comment . i I
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RO SkyScraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
-i----~
1 Questi~n Topic 11RO37 I I With normal Letdown in service, all of the following conditions would cause any open Letdown Orifice Isolation Valve 2CV3, 2CV4, or 2CV5 to automaticall~ shut EXCEPT: I Ci Phase A isolation signal occurs.
~I I
~ PZR level lowers to less than 17%.
I
~
C.' 2CV2 OR 2CV277, Letdown Isolation Valve is shut from 2CC2.
I
~ 2CV7, Letdown Line Containment Isolation Valve is shut from 2CC2.
I Answer 11 d I ,Exam Level I j R I 'cognitive Level. i IMemory I IFacility: 11 Salem 1 & 2 1 IExamDate: !j 12/19/20161 r~~43 D I
- c*;,"0'0'"}
KA::I 011000A405 I A4.05 _I ROValue:ij 3.21 SROValue:lj 2.91 Section: ;j~ RO Group:lj 2l!SRO Group: ' 21
- system/Evolution Title j IPressurizer Level Control System I 011 KA Statement: I Ability to manually operate and/or monitor in the control room: !
Letdown flow controller I
,Explanation of I 55.41.b(7) The 2CV7 is NOT interlocked with the Orifice Isolation Valves. All the other conditions will cause letdown flow to be
!A'!swers: i isolated by closing the CV3,4,5.
ij Reference Title ,,i: -i !Reference Section '
'L Facility Reference Number ii Page No .. :Revision ILogic Diagram
!1224431 I q I s I I II l 11 I I I Ii I 11 I I LO. Number __J Objectives CVCSOOE006 I Material Required for Examination 11 q
.Question Source: i INew I Question Modification Method: I I !Used During Training ~rogram i D
'Question Source Comments
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- l..on .... ~ ... I I I I I I I
RO SkyScraper J SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
'Ouestion -Top~ IRO 38 IWhich of the following actions changes the seteoint at which a Rx trip would occur while performing_a power ascension during a plant startup? !
~
~ Placing a PRNI drawer Rate Mode switch to Reset at 4% Rx power.
~
b.I Placing the High Flux at Shutdown Block switches in Block at 4% Rx power.
I c____J
~
8 Depressing the Block Power Range A and B pushbuttons at 12% Rx power.
.~
I
~ Depressing the Reset Source Range A and B pushbuttons at 12% Rx power.
I
!Answer] c I l 'Exam Level ' IR I 'Cognitive Level i IApplication ! !Facility:
- ISalem 1 & 2 I ExamDate: 11 12/19/20161 I~IA_1._01_ _ 1ROValue: *12.9*J SROValue:!l 3.4J Section:*!~ !Ro Group:il 1l 1SRO Group:, I
}N'~1
~.JI 012000A101 11 ;5p.43, D lsystemJEvolution Title I ,_R_e_a_ct_o_r_P_ro_t_e_ct_io_n_S~y~s_te_m_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~! 1012--
l!$A Statement: I ! Ability to predict and/or monitor chanqes in parameters associated with operatinq the Reactor Protection System controls includinq:
I Trip setpoint adjustment
[Explanation of, 55.41.b(?) A is incorrect but plausible if it is thought that resetting a High Flux Rate trip on a PRNI drawer would affect the Rx power Answers: trip setpoint. C is correct because it blocks the low power Rx trip (25%) when above 10% power.Bis incorrect but plausible if it were to be confused with the Source Range Block switches which blocks the Source Range hi power trip. D is correct but plausible as it WOULD change the setpoint if it were performed below 10% power after the SR hi power trip was blocked, but it is prevented
'--- m-aneroizino.Jbe...S.RhlJCsJJAtblciLWCLlldJ.awedbP,....Rx..nruNel'..idp..s-';--;nt tn 1v1nc:<: -;--~ h'. *'-- D 1f1 ..._, __ , I Reference Title __J Facility Reference Number
---*-iOill j iReference Section 1
~-
Pa~e No .. 'Revision I
IRx Protection Nuclear Instr Trip Signals !1221052 L II 117 I I
I ii II I If '[ I I II I! I LO. Number Objectiv I RXPROTE012
- Material Required for Examination iI lj Question Source: ! !New I\Question Modification Method: . I I [Used During Training Progra6J D I
~uestion Source Comments 1 I
- C"'.' .. """;-;! I I I i I I I
RO Skyscraper I SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes UuestlOn Topicl RO 39
- ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-~~~~~~~~~~-'
I Given the following conditions:
- Unit 2 is operating at 100% power.
- 21 and 22 CCW pumps are in service.
23 Charging pump is in service.
- A Safety Injection is initiated.
When performing SEC loading verification in TRIP-1, the PO reports the following equipment is not running:
- 21 Charging pump
- 21 Safety Injection pump
- #2 Emergency Air Compressor Assuming the SEC BLOCK switches on 2RP1 DO NOT WORK, which of the following identifies ONLY the power supplies which must be deenergized
- in order to start the above equipment?
~
.* a .. j2AVIB24, 2BVIB27.
- b. I 2AVIB24, 2CVIB9.
l L~ I2BVIB27, 2CVIB9.
I'1
~ "~I . . c....u.i=,,,__~~~~~~~~~~~~~~~~~~~~___,,,
~we;:' @=] -Exam Level I ~ ~f!nitive Level i IApplication I iFacility: i ISalem 1 & 2 I IExamDate:-1_ _ _1_2_11_9_12_0_1~61 KA:'I 013000K201 !IK2.01 I;Ro Value: J!ill SRO Val~IJ]°lsection: 11~ !ROGfo;;P: LJiSRO Group:t_..!J ;?~:~f' 0 1
!<A Statement:J ! Knowledqe of bus power supplies to the followinq:
I ESFAS/safeguards equipment control Explanation of 155.41.b(7) The A, B, CSE C's are powered from their respective vital instrument buses (VIS), and control the equipment powered !
~ers: .~-1 from the 1eopeoti'e 4KV ood 460 Volt '"'*'* 21 Chocgiog p"m p io powe<ed Imm B 'ital '"'* 21 SI p"m p io powe<ed Imm A 'ital bus. #2 ECAC is powered from C vital bus.
I i Reference Title Facility Reference Number l ,Reference Section i, Page No. i ~Revision IRx Trip or Safety Injection 112-EOP-TRIP-1 I lj 1 l I30 I j 4KV Vital buses one line !1203061 I 11 1135 I
!2c 460V vital bus one line Ii lj 24 LO. Number 601392 I 11 I I
Objectives I SECOOOE011 1
Material Required for Examination 1 I II
[Question Source:* 11 New I!Question Modification Method: I I[Used During Training Program I D
!Question Source Comments! I I Comment . I I
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RO SkyScraper SRO Skyscraper RO System/Evolution List J SRO System/Evolution List Outline Changes
-Question Topic I J RO 40 Given the following conditions:
- Unit 2 was tripped from 100% power about 16 minutes ago.
- IRNI 2N35 indicates 2.0 E-11 Amps.
- IRNI 2N36 indicates 2.0 E-10 Amps.
- Channel I SUR is -0.3 dpm
- Channel II SUR is -0.06.
Which of the following describes the condition present, and any action(s) required to be performed as a result of this condition?
!I
~_:_1 2N35 is over compensated. Manually energize Source Range channels.
~ 2N36 is under compensated. Manually energize Source Range channels.
!c.
~
2N35 is under compensated. Ensure Source Range channels automatically energize when 2N36 lowers to 7.0 E-11 Amps.
id. i 2N36 is over compensated. Ensure Source Range channels automatically energize when 2N36 lowers to 7.0 E-11 Amps.
--*.._J
'Answer' b I I 'Exam level IR! I Cognitive level 1 IApplication I ;Facility: , ISalem 1 & 2 I !ExamDate: 11 12/19/2016!
IKA:d 015000A202 I A2.02 I'RO Value:: [Ii} SRO Value: i[ill * .sect1on: i I~
I 1
RO Group: LJ .SRO Group:i LJ "~5-~~* D
- system!Evolution Title ! INuclear Instrumentation System I~_
IKA Statement:* Ability to (a) predict the impacts of the following on the Nuclear Instrumentation System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
Faulty or erratic operation of detectors or compensating components Explanation of 55.41.b(6, 10) TRIP-2 step 22 asks if both IRNI channels are reading <7E-11 A. If they are not, it asks if under compensation is Answers: preventing proper operation. If yes then the operator is instructed to manually energize SR channels. IRNI channels normally continue to lower until off scale on control console. If the reading is higher that expected, and SUR is abnormally low as indicated in stem, this provides justification for an undercompensated instrument, which allows more lower energy gammas to be seen. On
- -' I I Reference Title
'~acility Reference Number : *Reference Section ~~ag~ I Revision I Reactor Trip Response Ii 2-EOP-TRIP-2 I 1:r5130 I
I II I I I I I II I 11 11 I LO. Number Objectives I EXCOREE009 I EXCOREE010
'Material Required for Examination !I II I
'Question Sourcel Facility Exam Bank I!Ouestion Modification Method: IDirect From Source IfUsed During Training Program ! D
~:stion Source Comments' I I 1: . . . .i1111v111, I
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RO SkyScraper I SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List I Outline Changes I
~~u~stio~ Topic I IRO 41 Given the following conditions:
- Unit 1 is operating normally at 100% power.
Which of the following identifies how CFCU's would be affected if a MODE 1 SEC initiation signal occurs?
- a.i ONLY the running CFCU's will swap from High to Slow speed.
'b.I ONLY the running CFCU's will swap from Low to High speed.
c___j f I c.: Running CFCU's will stop, then ALL CFCU's will start in High Speed.
[] Running CFCU's will stop, then ALL CFCU's will start in Low Speed.
I 11
!Answer: Id I IExam Level 1 R I I !Cognitive Level i IMemory I :Facility:
- ISalem 1 & 2 I ~xamDate: ; I 12/19/201611 r** ~:
I KA:: I022000A301 I A3.01 J ,RO
' Value: 1@ SRO Value: *@:section:
I
' *I~ [RO Group: LJ SRO Group:: LJ 1?5.4~ D
!System/Evolution Title ! jContainment Cooling System I '022--]
KA Statement: I Ability to monitor automatic operations of the Containment Coolinq System including:
Initiation of safeguards mode of operation
[Explanation of I 55.41.b(?) By procedure, a maximum of 4 CFCUs can be running in High Speed. That would make choices a and b incorrect based I.Answers: ~
i on the 5th non-running CFCU which would start in Low Speed along with the 4 CFCU's which received a stop signal then a start signal. CFCU's swapping to low speed receive a stop signal, then a time delay to allow motor to coast down, before the Low speed start signal occurs. During a MODE 1 SEC initiation, (SI with vital power) ALL CFCUs running in high speed will be stopped, then A I I r"'r11~ *"'_, _ _,,in I ("HM ____ ,.., l1 ~n~ Q ~r~ . h* ,, nJa11sihle if it is thQ/ 1oht tbat.nnlv..ilie 01nnino CECI Is""" s .,__
I speed. C is incorrect because ~peed is wrong. * - * - *
- ===========R=e=fe=r=en=c=e=T=i=tl=e===========
- .
- ==F=a=c=i=lit=y=R=e=f=e=re=n=c=e=N=u=m==b=er===
- -
- ;,=R=ef=e=r=en=c=e=S==ec=t=io=n==:;]~e_N_o~.:~iR=e=v=is=io=n=
ISafeguards Equipment Control System ::::S::::0::::5=:S::::E::::C::::0::::00::::-::::0::::7=====::,!.:========114-15 117
- =:::================:::::::~=============~======::=::I
, _______________,, __________., _________., ,~I__
=== _.
ILo. Number I CONTMTE007 Objectives
'Material Required for Examination*. :I II lauestion Source: . : New I I!Question Modification Method: I I !Used During Training ProgramJ D lauestion Source Co~ments 1
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/Cv111u1""' . i I
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RO SkyScraper I SRO Skyscraper ( RO System/Evolution List ( SRO System/Evolution List I Outline Changes I Qu~stion To£i~ RO 42 I I 21 CFCU is running in Low speed during its weekly exercise and flush.
Which of the following identifies how steady state service water flow through 21 CFCU would be affected when the CFCU is transferred from Low Speed to High Speed?
Service water flow will. ..
d~
I
~
~
I
~
~
I L'!:J rise or lower based on initial SW header pressure.
I Answer i le I f Exam Level i IR I Cognitive Level :IMemory l I
,Facility: i Salem 1 & 2 I ~amDatel j 12/19/20161
?"
KA::I 022000K101 11~ :RO Group:jl t5i~~., D I I j _.K_1_.0_1_ _ !Ro Value: *I 3.5j ISROValue::l 3.7l ISection: 1j 1SRO Group:: I 11
- system/Evolutfon Title I IContainment Cooling System I 022 iKA Statemen_!J Knowled e of the ph sical connections and/or cause-effect relationships between Containment Coolin S stem and the following:
, SWS/coolin s stem
,Explanation of 1! 55.41.b(9,8) The CFCU SW flow control valve SW223 has a position limiter on it, typically 50% travel. The SW223 opens on a start
!Answers: signal from either low speed or high speed. With a mechanical stop employed, SW flow will be the same for high speed or low speed operation. The stem states "steady state SW flow" because the CFCU is normally stopped for 30 seconds when transferring speed. Distracter Dis plausible if it is thought that SW header pressure would change, which would affect SW system flows, but in
- Lo. Number Objectives I CONTMTE007 Material Required for Examination 11 II I
Question Source: 11Previous2 NRC Exams !Question Modification Method: *I Direct From Source IIUsed During Training Program D
- auestion Source Co~_mentsJ I I Com *.*
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RO SkyScraper I SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List I Outline Changes I iQuest!on Topi~ IRO 43 I Given the following conditions:
- Unit 1 has experienced a LOCA.
- Control room operators have progressed to the point where the SECs have been reset.
- Containment pressure was 4.5 psig when the SECs were reset.
Which of the following describes the Containment Spray System response should a HI-HI containment pressure signal be generated at this point in the accident?
CS system valves ...
na.* would realign for spray, the CS pumps would be started by the SEC.
1)1 I
~
would realign for spray, the CS pumps would have to be manually started.
I
~ must be manually realigned for spray, but the CS pumps would be started by the SEC.
I
~ must be manually realigned for spray, the CS pumps would have to be manually started.
I
.Answer i b I I !Exam Level . IR I !COgnitive Level I j Application I 'Facility: I ISalem 1 & 2 I ExamDate: : I 12/19/20161 l_A_3._01_~l!ROValuell 4.5liSection: 1 1~ RO Group: I 1l*SR0Group:,j 55:f~; D
~~-<;
IKA::I 026000A301 4.3j SROValue:!l I
11
- system/Evolution Title I !_c_o_n_ta_in_m_e_nt_S-'p_r_a:...y_S..:.y_st_e_m_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___, 0_2_6_ _
KA Statement: I Abilitv to monitor automatic operations of the Containment Spray System includinq:
Pump starts and correct MOV positioninq
,Explanation of' 55.41.b(7,8,9)The SEC controller operates the CS pumps at 2 different point in the sequence UNTIL the SEC is reset. The SEC IAnswers: ' ONLY control the CS pumps, not the CS valves. The valve realign on the hi-hi containment pressure signal whenever it is received, but once the SEC is reset, it will not start the CS pumps since the sequencer is no longer active.
I Reference Title Facility Reference Number :Reference Section ~*
1: Page No.!'
Revision, I Containment Spray Lesson Plan II NOSOSCSPRAY-06 I 1142-43 11 6 I I II I 11 II I I 11 I 11 11 l
!LO. Number Objectives I CSPRAYE006
- Material Required for Examination :' l!
'I Question Source: 11 Facility Exam Bank I:auestion Modification Method: *j Direct From Source I!Used During Training Program I D
- auestion Source Comments!
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RO Skyscraper I SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
[Question-Topic I IRO 44 Given the following conditions: I
- Unit 2 is performing actions in 2-EOP-LOCA-1 for a LOCA.
- Containment pressure peaked at 20 psig.
When performing CS Pump Stop Criteria steps in LOCA-1, the RO depresses both Reset Spray Actuation pushbuttons with Containment pressure at 15.1 psig.
Which of the following describes the effect of this action, if anything?
- a. . There will be no effect.
c:-1
- b. ! Containment Spray valves 21/22CS2, 2CS14, 2CS16, and 2CS17 will shut.
I L.__j r-~1
- c. Containment Spray Actuation signal will reset and NOT reinitiate after the Reset Spray Actuation pushbuttons are released.
~
I
~l
~ Containment Spray Actuation signal will reset, then Containment Spray Actuation WILL reinitiate after the Reset Spray Actuation pushbuttons are released. I
'Answer. I c I !Ex"am Level . 1R I [Cognitive Level 'I Application ! Facility: I ISalem 1 & 2 1 IExamDate: JI 12/19/20161 i 3.51 :section: *I~ RO GroUP:!I i~5.43 D
-=
,-- c:::-c:-
=-=-i KA:d 026000A405 I!_A_4._05_ _i RO Value: lj 3.5! SRO Value: 1j :SRO Group:1i I
11 System/Evolution Title i l_c_o_n_ta_in_m_e_n_t_S...:.p_ra-'y'--S:...ys_t_e_m_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __.l ,026 KA Statement:, Ability to manually operate and/or monitor in the control room:
Containment spray reset switches Explanation of; 55.41.b(7) Containment Spray actuation relays have retentive memory, which allows relays to be manually reset with an actuation I Answers: signal still present. So even though containment pressure remains above the Containment Spray actuation setpoint of 15 psig, the actuation signal can be reset. The Containment Spray pumps and Spray valves CS2, CS14, CS16, and CS17 do NOT reposition to their normal positions. The CS 14 is normally open with power removed. The remaining CS valves are normally shut and open
............... thn f""Q ..... : ....... .,, ....... ..,i ,....,nnot hp c!,os.e.d.J ioti! the snrav actuation sianal i~ .. ,., ..........
! * ~ . .. ....
- Reference Title ,! Facility Reference Number j 'Reference Section /I Page No.: ,Revision'
- =============================~~=====================~============;;;;;;;;;;;;;;;
I RPS Logics Safeguards Actuation Signals 11221057 I ii 1123 I
- ==1==============
- ::::::=::11;=============1:~======~1! II I
!, _ _ _ _ _ _ _ _ __,Ii 11 _ _ ____.lj ii I LO. Number I
1 CSPRAYE008
!Material Required for Examination :I II
!Question I
Source: I jNew I!Qu_estion Modification Method:, I I !Used During Training Program [ D
- Question Source G_~~ments; I I Comment i I I I I I I
RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List j Outline Changes Question Topic I I RO 45 I Given the following conditions:
- Salem Unit 1 was operating at 100% power when a LOCA occurred.
- A manual reactor trip and manual SI were initiated.
- When the Main Generator output breakers opened, a loss of off-site power occurred.
- 1A vital bus locked out on bus differential.
Which of the following identifies which Hydrogen Recombiners can be started when directed by procedure if required?
ra:
~
~ 11AND12.
I rd.I Neither Hydrogen Recombiner is available.
I
.Answer i b I I 1Exam Level . IR I :cognitive Level ' IApplication ! 1Facility:~ 1 & 2 I :ExamDate: 11 12/19/20161
~I 028000K201
~
1l~_____J ,RO Value: i 1[~
§ . .
SRO Value: §'section: 1I~ RO Group:
LJ 1SRO Group:/ LJ f~;1~ D
~~"' ~*, ' "..,.1 System/EvolutiOnTitlei j Hydrogen Recombiner and Purge Control System I 028 __.
KA Statement:! Knowledge of bus power supplies to the following: I Hydrogen recombiners I
,Explanation of 55.41.b(9). Hyd recomb are powered from 1A and 1B 460 volt vital buses, which are powered from their respective 4KV vital
'Answers: buses. With 1A bus locked out on diff, 1A 460 will not have power. Only 12 is available.
i I
Reference Title 1I,I Facility Reference Number J ,Reference Section J j Page No. I IRevision I1A Aux Building 460V Bus One line 11601231 I 11 !117 I 11 B Aux Building 460V Bus One line 11601232 I 11 i 118 I I II I, ii II I LO. Number Objectives I CONTMTE004 1_ ____.
'Material Required for Examination II II QuestionSou~ j Previous 2 NRG Exams IiOuestion Modification Method: i Direct From Source I[Used During Training Program D Question Source Comments, I I 1
Comment I
I I
RO SkyScraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
~estion Topic IRO 46 I Given the following condition:
Unit 2 Spent Fuel Pool makeup is required when responding to OHA C-35, SFP LVL LO, which has been determined to be caused by normal evaporation over the course of several months.
IAW S2.0P-SO.SF-0001, Fill and Transfer of the Spent Fuel Pool, which of the following is the LEAST preferred source of makeup water to the Spent Fuel Pool, assuming all sources of makeup are available?
la:]
it).' De
- .......--1
~
- c.'
I d.;
~o Refueling Water Storage Tank.
I
'Answer; Id I :Exam Level 1 R I I Cognitive Level . !Memory I :Facility: i ISalem 1 & 2 I !ExamDate: 11 12/19/20161 fill LJ LJ
"',,;*,,w
~I 033000K105 I.K1 .05 RO Value:.
- SRO Value:.~
- Section: *I~; RO Group:1 J f tSRO Group: 55:_4~ D System/Evolutio~ I Spent Fuel Pool Cooling System I [633-*I KA Statement: I Knowledge of the physical connections and/or cause-effect relationships between Spent Fuel Pool Cooling System and the following:
RWST Explanation of: 155.41 (13) The sources of water are listed, in order of preference, in Prerequisite 2.3 of procedure. RWST is last.
.An*w.,., 'I I
Reference Title Facility Reference Number ! Reference Section Jr Page No. . I Revision.
IFill and Transfer of the Spent Fuel Pool I 1 S2.0P-SO.SF-0001 II ii 1 j20 I I I II II 11 I I I II ii 11 I LO. Number Objectives I SFPOOOE010 1
Material Required for Examination 1 I q
~estion Source: 11 Facility Exam Bank J lauestion Modification Method: i Significantly Modified J 'used During Training Program : D Question Source Commentsj 144165 changed from preferred to least preferred to match KIA I
- Comment I I I I I I I
RO SkyScraper I SRO Skyscraper I RO System/Evolution List j SRO System/Evolution List f Outline Changes I lauestion Topic* I RO 47
/Which of the following describes an interlock on the Unit 2 Spent Fuel Handling Crane? I
~ A high load weight cutoff prevents lifting and movement of loads >2200 lbs. over the spent fuel pool.
~ A high radiation signal on 2R32A, Fuel Handling Crane, will lockout ALL crane motion to prevent excessive radiation dose rate on bridge.
~
- c. ~ A bridge over travel limit will stop the bridge from contacting the hard stops even if the direction button is held down, to prevent damage to the bridge. I
'dl A high radiation signal on 2R5, FHB-SFP, OR 2R9, FHB-New Fuel Storage Area prevents upward crane movement to prevent excessive radiation does rate on bridge. I
!Answer 11 a i *Exam Level i IR I !cognitive Level ! IMemory I 'Facility: 11 Salem 1 & 2 I 1 ExamDa~e: i j 12/19/20161 I!A3_.0_2-~!;RO Value: :12.5*! !SRO Value: i f""~
1 KA:ll 034000A302 3.11 !section: II~ 1RO Group:]! 21 iSROGroup:!I 2j f~J~, D
~/Evolution Title ,_F_u_el_H_a_n_d_lin~g"--Eq~u_ip~m~en_t_S~y_s_te_m~~~~~~~~~~~~~~~~~~~~~~~~~---'j ~J
!KA Statement: I Ability to monitor automatic operations of the Fuel Handlinq Equipment System includinq: I Load limits I
!explanation of I 55.41.b(10,12) The overload cutout is provided to prevent lifting loads >2200 lbs. If they can't be lifted, then they can't be moved Answers: over the spent fuel in the pool IAW TR 3.9.7, and is tested IAW TR 4.9.7. B is incorrect because downward crane movement is still available to lower the fuel bundle. C is incorrect because on Unit 2, the proximity switches only transfer the crane to slow, but movement will continue if the direction PB is continued to be depressed. On unit one, it stops movement. The 2R5 and 2R9 are
~oat 1otadacked Miitb tbe ccaoe. b11t ar:e interlocked Mlitb El::IB ~ieoti!atioo TechnicaLRequlr...e.ments....M.an* .~1 ., n 7 ~* *-
... TD
!4..
9 7 applicable with fuel in the SFP I Reference Title I! Facility Reference Number I!Reference Section 11 Page No.* iRevisi~"
ISpent Fuel Pool Manipulations II S2.0P-IO.ZZ-0010 II 11 1133 I j Technical Requirements Manual !ISGS-TRM 113.9.7 11 TRM 3/4 112 I I II II ii 11 I il.O. Number Objectives I IOP010E004 l--~
Material Required for Examination :I II
- Question Source: :IFacility Exam Bank l jauestion Modification Method: ;I Direct From Source I 'Used During Training Program I D
[auestion Source Comme~ 1111924 I
)Comment '
I I
I
RO SkyScraper f SRO Skyscraper I RO System/Evolution List
. . NN J SRO System/Evolution List I Outline Changes I
!Question Topicj I RO 48 Unit 2 is performing a plant startup to full power.
Predict the Steam Generator Narrow Range Levels for the following TURBINE power levels.
Assume a normal power ascension.
10% Turbine Power= - -% NR level.
60% Turbine Power= % NR level.
!J
~
~
~
- ~
L~:J 33%. 44%.
/Answer 11 b I .!Exam Level ' IR I Cognitive Level :IApplication I iF~cility: 11 Salem 1 & 2 I ,ExamDate: ,I 12/19/20161
~: :j 035000A 101 !~1A_1.0_1_ _:.ROValue:I! 3.6J'SROValue:Jj 3.8] Section:1j~
~
ROGroup:i--2J'SROGroup:
1
! 2j
!'>' .'"'.o/:'
- ?~.4~. D
)System/Evolution Title 1
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____.I :_0_35__ _
j_s_te_a_m_G_e_n_e_ra_t_or_S_y,_s_te_m
- KA Statement
- I Ability to predict and/or monitor chanoes in parameters associated with operatinq the Steam Generator System controls includino:
S/G wide and narrow ranqe level during startup, shutdown, and normal operations I I;Explanation of :155.41(4) SG NR level is programmed so that as Turbine power rises from 0-20% (Turbine steamline inlet pressure) it rises from 33-
/Answers: : 44%. On Unit 1 only,20-100 it rises from 44-48. A is incorrect but plausible if candidate thinks programmed level is based Turbine l
power but uses Unit 1 ramp from 20-100 (calculated at 60% power. Bis correct. C is incorrect but plausible if it is thought that that 1 the ramp is from 20-100% and uses Unit 1 ramp. Dis incorrect but plausible if it is thought that that the ramp is from 20-100%.
1 l Reference Title Facility Reference Number i !Reference Section rR--
. [Page No. I .Revision IAdvanced Digital Feedwater Control System I
11 NOS05ADFWCS-08 II' I
,,q14,17,22
,I ,
18 I l
I ll I 11 lj I
[Lo. Number Objectives I CN&FDWE008 Material Required for Examination 1 i II Question Source: 1 IFacility Exam Bank I;Question Modification Method: 'I Significantly Modified IiUsed During Training~Program D !
~-----------
Question Source Comments) 1125789 Modified "reactor power levels" to "turbine power levels". Changed correct answer from d to b.
I
- C~ .... ""'m I I
l I
RO SkyScraper I SRO Skyscraper f RO System/Evolution List I SRO System/Evolution List I Outline Changes I
,Question To~c:
1 IRO 49 I Given the following conditions:
- Unit 1 is operating at 1x10-8 Amps.
- A small (0.1%) steam leak occurs in containment on a single SG.
Which of the following describes how this will affect Rx power with NO operator action?
Rx power will rise ....
~
~ until it stabilizes after reaching the POAH.
!b.i until the power excursion is terminated by a Rx trip on OT/OT.
L__j
,.-*~*
!c. initially, then stabilize at a power slightly above 1X10-8 Amps.
~
I
~l until the power excursion is terminated by a Rx trip on high power (low range).
Answer i~ Beam Level : ~ .Cognitive Level 1 j Application I ~~ility: , j Salem 1 &2 I iExamDat~j j 12/19/20161
~I 039000K508 I1K5.08 i !Ro Value: r !))" iSRO Value: 11))" 'Section: 11.~~_J ,RO Group:/ LJ iSRO Group:! LJ System/Evolution Title j IMain and Reheat Steam System KA Statement: I owled e of the operational implications of the followin concepts as they a pl to the Main and Reheat Steam S stem:
ct of steam removal on reactivi
,Explanation of [ 55.41.b(1,5) At 1x10-8 Amps, the reactor is exactly critical. The steam leak will cause Rx power to rise. Before reaching the Point
!Answers: ' of Adding heat, reactor power will not have a temperature coefficient feedback. The power rise will be terminated AFTER reaching the POAH, as the negative reactivity added will offset the positive reactivity from the steam leak. The 2 reactor trips are plausible if it is thought that power will continue to rise uncontrollably, as the OT/DT trip is always active (not re-instated above 10% power as
.n9el trio wo1 ild he acfoie since it is only block.ed...a£ie Reference Title L.O. Number Objectives I REACOEE001
,Material Required for Examination 11 'l
!Question Source: *!New I'Question Modificatiop Method:
- I I iUsed During Training .Program J D
'Question Source Comments: I I I
I I I I I I
RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
~~est_ion Topic i IRO 50 Given the following conditions:
- Unit 2 is operating at 46% power steady state.
- The Main Generator trips due to a ground fault.
Which of the following describes how the Main Generator trip affects the plant with NO operator action?
- a.: A reactor trip will NOT occur. Main steam dumps will open and control rods will insert. Tavg will stabilize -547 °F.
I b.' A reactor trip will NOT occur. Main steam dumps will open, and control rods will insert. Tavg will stabilize -552 °F.
C.' A reactor trip will occur due to the Main Turbine tripping from the Generator Protection trip. The crew will perform TRIP-1 stabilization and c___J 11 diagnostics actions, then transition to TRIP-3. I
'd:l A reactor trip will occur due to the Main Turbine tripping from the Generator Protection trip. The crew will perform lmmedate Actions of TRIP-1 then transition to TRIP-2.
Ansmri ~ !Exam Level * ~ ~itive Level I !Application I Facility: j Salem 1 & 2 I j~~::_ I 12/19/20161
.~I 045000K301 I:K3.01 JRO Value: lj 2.81 SRO Value: I 3.11 JSection: :j_~~-.J )ROG~j 21 ;sRO Group:lj ;55:43 D 2J +,,, *:..,Ll~.
System/Evolution Title. j Main Turbine Generator System 1
KA Statement: Knowledge of the effect that a loss or malfunction of the Main Turbine Generator System will have on the followinq:
Remainder of the plant Explanation of : 55.41.b( 4,5,6,7) The generator trip causes a MT trip, but at less than P-9 (49% Rx power), a Reactor trip will NOT occur. With no Answers: : operator action, rods will insert in auto to lower Tave. The steam dumps will open in Average Temperature Control Load Reject Control Mode. With the reference signal being derived from Main Turbine Steamline inlet pressure, and the Main Turbine is tripped, the reference signal is set to 552°F. (There is a 5°F deadband in which the output to the steam dumps is zero.) Tave rises during 1the loac:Lr:elP-C.tlon and the rl11mns I
willm.od.J~hmle..na..J.oacf of -54Z Cq~to Rod Contr;I T-error is <1.0°F fr~m program, which in this case will be 547-548 since its program signal is based on Turbine 1mtil I Steamline inlet pressure, which is zero.
i '
Reference Title Facility Reference Number :Reference Section ! . Page No. : !Revis~
IMain Steam Dumps Lesson Plan II NOS05STDUMP-12 II l I35-36 1112 I I II ![ II Ii I I II ii II 11 l
~O. Number ISTDUMPE008 Material Required for Examination I II Question Source:. j j Facility Exam Bank I(Question Modification Method: 'I Concept Used I/Used During Training Program I D Question Source Comments; 157628 (100% power question changed initial power to 46% and added MT trip as the load reject vs SGFP trip)
I Comment *: ,, 1 l
I I
RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes au~stiori_l"o~ 1Ro51 I Given the following conditions:
- Unit 2 is at 35% power during a plant shutdown performed IAW S2.0P-IO.ZZ-0004, Power Operation.
- 21 SGFP is manually tripped as directed by S2.0P-SO.CN-0002, Steam Generator Feed Pump Operation.
- 24BF19 fails open, and 24 SG NR level rises and remains >67%.
Which of the following describes the effect of this failure, and how will the crew respond?
~
~_:_ NO AFW pumps start immediately when 22 SGFP trips. If total AFW flow is <22E4 lbm/hr when checked in TRIP-2, the crew will tran~*-*-
FRHS-1. FRHS-1.
ib.: NO AFW pumps start immediately when 22 SGFP trips. If total AFW flow is <22E4 lbm/hr when checked in TRIP-2, the crew will start AFW pumps to establish at least 22E4 lbm/hr AFW flow. Flow r-,
,c.' ONLY 21 and 22 AFW Pumps automatically start when 22 SGFP trips. If total AFW flow is <22E4 lbm/hr when checked in TRIP-2, the crew will transition to FRHS-1. FRHS-1. I rd. ONLY 21 and 22 AFW Pumps automatically start when 22 SGFP trips. If total AFW flow is <22E4 lbm/hr when checked in TRIP-2, the crew will start AFW pumps to establish at least 22E4 lbm/hr AFW flow. Flow I
- )\nswer 11 b I Exam Level IR I ~cognitive Level i IApplication I iFacility:
- lsalem 1 & 2 I [E~amoate:p I 12/19/20161 lll\_2.01___ 1 ~a~fIB~'.l.~1~§~11:.i~~()'P:1LJiS~ue:JLJ 5~c!i D r----*** - *- ~"i
! - - - - - - ' - - - - - - - - - - - - - - - - - - - - - - - - - - - ' 65-9 _____]
KA St~emen_t:: y to (a) predict the impacts of the following on the Main Feedwater System and (b} based on those predictions, use procedures ct, control, or miti ate the consequences of those abnormal operation:
Explanation of 55.41.b(4) The high SG NR level in one SG initiates Feedwater Isolation. This trips both SGFPs. Normally, a trip of both SGFPs Answers: would start the MDAFW pumps ONLY (21 and 22), but this does NOT occur when the SGFP signal is caused by a FW Isolation.
- * - - With power initially at 35%, SG NR levels will remain above the AFW pump auto start level of 9%, so NO AFW pumps will start IMMEDIATELY, they will ALL start when SGNR levels are <9%. If levels did not shrink low enough, then when asked in TRIP-2 Reference Title j . Facili_ty Reference Number !Reference section i-- - --- ---
Page No. Revision
!Fluency List
.. --- ---- ---* . ---~
11 NOS05FLUNCY-09 11 1114 I 9 I IReactor Trip Response 112-EOP-TRIP-2 II !ISh 1 I 30 I I II II 11 I I LO. Number Objectives I'------
CN&FDWE006 1_ ____,
Material Required for Examination
~uesti()_n SourcE!:l j_N_e_w_ _ _ _ _ __,l /auestio~ __
M__o_di_fi_cati_on_M_et_h()~=_j, _ _ _ _ _ _ _ __,I :use~ [)uring Training ~()gr~ll'.1.] D iQue~tio~ Source (:omme~~ I I
- ---------------------------------------~
~-
I I
i
RO Skyscraper I SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes 1oues~~nTop~~ *~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~__.
IWhich of the following identifies how over-cooling of the RCS is prevented on an uncomplicated manual Rx trip from 100% power?
,b.'
1.------
I
[!5A_stateme'!~ Knowledge of the physical connections and/or cause-effect relationships between Main Feedwater System and the following:
RCS 55.41.b(?)Feedwater interlock actuates when 3/4 RCS Tavgs <554°F and at least one Reactor Trip and associated bypass breaker open. This shuts the BF19's and BF40 Feed Reg Valves. Feedwater Isolation occurs when 2/3 SG NR levels on 1/4 SG's reaches 67% OR on a SI signal, and shuts BF19s, 40s, 13s, and trips the SGFPs. On an uncomplicated Rx trip this will not occur. P-10 is 3/4 PRNls <10% power, and blocks the low power Rx trips. P-12 is 3/4 RCS Tavgs <543°F, and will shut the Steam Dump valves.
. . . 0 .
Revision_
l=======================~================~!===========~===::::~l3=0==~
l=============:::::.~=======::l=====::::::::::~====.
- ~~~~~~~~~~~~~~~~~~*-~~~~~~~~~~~__. ~~~~~~~--' ~~~d I~~~~
i=I==
-*****--* ---*-i l~'.~b~_r_________ _ Objectiv ICN&FDWE006 Material Required for Examination I II I
iQuestioll Sour~~ Facility Exam Bank I 1auestion Modification Method: j Direct From Source I[u,.. """* Tralni~Og P*og""" I LJ I
~u:~uo~s~~ce c~-~_lnentsj 1159006
~orr .... - ... ~-- - - -
I I
I
RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes 1 ~uestion T~i>IS IRO 53 IWhich of the followin!i) describes the desi!i)n purpose of 21-23AF141, AUX FDWTR PMP INLET AUTO VENT RLSE valves? I
-1
~ To facilitate filling lines upon aligning alternate water sources to suction header.
~ To facilitate draining lines upon return from alternate water source alignment to the suction header.
1S To prevent AFW line voiding and water hammer upon AFW pump start when aligned to normal water source.
I
- d. To prevent AFW line temperature gradient if backleakage to AFW from Main Feed occurs with AFW pumps secured.
I iAnsw~rJ Ia I [§xam Level ' IR I rcogn!tive L~vel ! IMemory I rFacilit~ ISalem 1 & 2 I ~xamoaie: 1 I 12/19/20161
- - F
~1061000K505 llK~ .'.[()~eJ[DJ~_~jfEJ~i()_tsl~!~o~LJ~~u~LJ 1~*'1 D
~ W, isystern/EvolutionTitle I IAuxiliary I Emergency Feedwater System I roo~-- j KA S_t(iteme11tJ Knowledge of the ooerational implications of the following concepts as they apply to the Auxiliary I Emergency Feedwater System:
Feed line voidino and water hammer Explanation of i 55.41.(b)?,8. Alternate water sources can be aligned to the AFW pump suction header through the normally jacked closed AF52
..Answers:
I
"-*****--*****~
I Alternate Suction Valves from Demin water, Fresh Water I Fire Protection, and Service Water. During performance of S2.0P-SO.AF-0001, Auxiliary Feedwater System Operation, Section 5.10, Alternate Sources Alignment, operators are instructed to ensure open the Auto Vent Isolation Valves 21-23AF140. This is to allow the alternate suction line to fill and vent through the auto vents,
,,h' .L ...h .......... .f.h ...... 1: .......... : ... ~
,,_ _ _ _ _ - - - - - - - -.... - - - - - * * * * -....- - - - * - * * * * - * * - * * * * * * - - * ... _ . -*1~--- .. *--1 ***-*. . --
_ _Referen_~e Title___~---* ..* l_!acility Reference ~umb:r_ ~eference Secti~ I Page ~ i_F_levision' I Auxiliary Feedwater System Operation 11 S2.0P-SO.AF-0001 I 1165 1140 I I Auxiliary Feedwater System Lesson Plan ii NOS05AFW000-15 I lj 55 1115 I I II I 11 11 I
~--*-----***--------
.0. Number 1 Objectives
[ AFWOOOE004 I AFWOOOE013
,Materi~I ReqlJired f~r Examination ... JI 11 1
1
__auesti~n Sour_ce: 1 l_N_e_w_ _ _ _ _ ____,I ~Q_u_e_st_io_.n_M_._od_i_fi_ca_tio_n_M_et~_o_d_:_), ________..........! ~d Durif1Q Trainillg P_l'ogra..;:1 D
!~~~s~t_i_o_-~s_o-::_u-::_rc_e_C=o=m=m- . . ~~tsl I I
- ~-----------------------------------------'
!comment I I I I I I
RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes r§u~stion To*p~ IRO 55 I Given the following conditions:
- Unit 2 operators are responding to a valid safety injection signal.
- Safety Injection has been RESET.
- ALL SECs have been RESET.
- ALL EDGs are running unloaded.
- 4KV Vital Susses 2A and 2C are aligned to 23 SPT.
- 4KV Vital Bus 2B is aligned to 24 SPT.
Subsequently, 24 SPT experiences a failure causing its secondary voltage to drop and stabilize at 3600 volts.
Which of the following describes the effect of this failure on 2B Vital Bus?
2B Vital Bus will. ..
~ fast transfer to 23 SPT.
--1 ib. remain loaded onto 24 SPT.
I
---*----1
'c.1 I
be energized by its EDG in ACCIDENT loading.
I rd:1 I
be energized by its EOG in BLACKOUT loading.
I
@=] ~x~L._evel : j R I !~ognitive Level 11 Application I ~-~ ISalem 1 & 2 I ~~am Date: 1 ___1_21_1_91_2_0_16~1
,Ans~
~--**-- ""l 1
- ~1062000K302 1!~-=-1~~G~~U!JG~~l~~~:iu~a~u ~-*- o
~tern/Evolution Ti~ l_A_.c_._E_le_c_tr_ic_a_l_D_is_tr_ib_u_ti_on_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~I ~062 ---i
- -***~----***-
M Statementi_j Knowledqe of the effect that a loss or malfunction of the A.C. Electrical Distribution will have on the followinq: I ED/G I 1
Explanation of' 55.41.b(7,8) -A is incorrect because 3600V is not <70%, so the vital bus transfer relay will not energize. B is incorrect because Answers: the sustained degraded voltage relay will cause a UV signal to be generated for that bus.
~-----*****~****'
C is incorrect because after SI is RESET, the SEC will not actuate in MODE Ill
- 11 -**In.,,., 111<'\/ h,,c <--~ -<<-itn I ..
Dis correct because 3600V is below the setpoint for the degraded voltage (95.%) relays. When these relays actuate then 2B SEC
- -* ..... *C In ~Anni= 11* IC-:- ~ *C 111/\
-*** *-*Reference Title . - - - * * - - . _Jr !=acilityReference Number l Reference Section . l !p(lge No:l !Revision!
!I NOS054KVRLY-00
- - - - - - - - - - - - - - - --*------*-- ' - - * * - - - - * - - - * - - * - - - - * * * - * - * ' L _ _ _ _______ - - - * * * - - * * -----' - *- * - - - -
- 14160 Electrical System I 1123-28 11° I I II I ii I[ I I II I 11 11 I
~~~-;n-~=-] Objectives 14KVACOE006 I I
Material Requir~d for Examinatio~
I 'I I
!_Question Source:] Facility Exam Bank I;aue~tion Modification Method: .
~---*----------*-__J
,I Editorially Modified I ~ed During Training Program1 D
**---~- ----- --
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! I I I
RO SkyScraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes While operating at 100% power, the 1A 28 VDC bus becomes deenergized.
Which of the following identifies an effect this failure will have?
~ 13 AFW pump will start.
J;:l OHA G-6, 11 SGFP TRBL will annunciate.
I
~rC_o_n-tr-o-IR_o_o_m_E_m_e-rg_e_n_c_y_L_ig-h-tin_g_w_ill-li-g-ht-.---~-~-------~--~-----------------:-,
'Al
~ All indication on 1RP4 status panel will be lost.
I Answer/ j d I /Exam Level; j R I !cognitive .Level
- 1Memory I iFacillty: , j Salem 1 & 2 I ,examDate: : I 12/19/20161 J<A:ij,,.-.- - - - , I I_K_3_.0_2~~' )RO Value:*11-:ic;I .22J 1SRO Value: 'j-:i7l' 2!J 1Section: I'lc::vc::
~11 RO Group:i1-2J r-:i'il,SRO Group: 1r-:i'i
_2i ,55"4~'.
1 ~t n 0
1 063000K302 1 1
/S~~~&~~ooru~/ l_o_.c_.E_l_e_ct_ri_~_1_o_is_t_rib_u_ti_o_n_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~l 1 o~
- KA Statement:: Knowledge of the effect that a loss or malfunction of the D.C. Electrical Distribution will have on the following:
Components usinq de control power Explanation of! 55.41.b(7) A is incorrect but plausible since loss of 125VDC control power to MS132 steam supply valve will start cause it to fail 1
!Answers: ! open and start 13 AFW pump. B is incorrect since 115 VAC power is supplied to alarm panel functions. C is incorrect because 125VDC supplies control room emergency lighting. The purpose of the 28VDC Control Power System is to provide DC electrical power under normal, transient, and accident conditions to:
".'.:! C'. ,.;;i. ..... i...,... ............
I b.Main Control Room Control Console Bezel controls c.Annunciators d.Vital Instrument Buses e.Non safety-related equipment f.Status panel RP4 in the main control room Reference Title i Facility Reference Number ! [Reference Section l i Page No. I [Revision:
!DC Electrical System Lesson Plan 11 NOS05DEELEC-09 II 1110-11 11 9 I I#1 Unit 28 voe One Line Drawing !1211357 II 1ISh1 1115 I I II II ii ll I
!Lo. Number Objectives IDCELECE008 j_ ____,
1'Material ~eq'uiredforEX:ainlnatit:)h '.tl I ll
!OuestioriSource: i j_N_e_w______~l ILQ_u~e_s"""ti~o_n*~M~o_d..:.:*i~fi_c_at2[o: . .*n_**-'"M_e_tho::. .* d_:_:*_:_'JI________~! i~sed During Training Pr9gram j D 2
1
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.Comment* ';
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RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
'~~stiol'\TopicJ IRO 57 I Given the following conditions:
- 2A EDG is running and develops a fuel oil leak.
- 2A EDG Fuel Oil Day Tank level lowers below the start setpoint for both the REGULAR (33") and BACKUP (27") EDG Fuel Oil Transfer Pumps.
- The leak is isolated, and 2A EDG Fuel Oil Day Tank level is recovering.
With 2A EDG Fuel Oil Day Tank level now at 35", which of the following identifies which EDG Fuel Oil Transfer Pumps will be running, if any?
~!NEITHER.
- _.____J
[~~J BACKUP ONLY.
ONL'
!c.J RE I
'.d.11 BOTH REGULAR AND BACKUP.
I
-An~wer 11 d I ~)(am ~evel 11 R I rco~nitive_Level I
! Application I [Facility:l ISalem 1 & 2 I 1ExamDate: 11 12/19/20161
~~ 1 1064000K103 IEmergency Diesel Generators 064
'KA Stateme11!=J Knowledqe of the physical connections and/or cause-effect relationships between Emerqencv Diesel Generators and the followinq:
Diesel fuel oil suoolv system Explanation of 55.41(7) Regular starts at 33" and Backup at 27", as stated in stem. Once started, they BOTH run until the FULL level is reached
!Answers: __J (44"). The Backup does NOT turn off when the normal level is reached (33"). It is not require to know the exact setpoint at which
- -~-***--~
the pumps turn off, only that it is substantially higher that when the Regular pump turns on, and that the backup pump will turn off at the same level as the Regular pump.
-- - - * --****--- -- - -- -,- - - - -- -- --T ---- -- --, -- -- -- --
Reference Title ____ I ~cility Reference Number_ LReference Section__ ~~e No. I ~ision I NOS05EDG000-12 !IEMERGENCY DIESEL GENERAT I 1144 1112 i I II I 11 11 I I II I 11 11 I
~'.~b~_--*
Objectives I EDGOOOE007
,Material ~(!quired for Examination _J j 11
'a_ue_s~o_n_s_o~_rc_e'_: 1 j_N_e_w_ _ _ _ _ _~I ~ti_on_M_o_d_ifi_rca_tio_n_PJl_et_h_od~_J, _ _ _ _ _ _ _ __.I ~sed During Training Program J D
---* **----** - - * **--1 i~_l:l~~t~on Source<;omrl'l_ents I I 1
Comment _J I I l I I I
RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
!Question .Topi£ IRO 58 I Given the following conditions:
- Unit 1 is operating at 100% power.
- 1A EOG starting air receiver 11A is CIT.
- 11 B EOG starting air compressor is CIT.
- A Loss of Off-Site Power occurs.
- 1A EOG trips shortly after starting.
- 11 A starting air compressor will NOT run.
By design, what is the minimum number of subsequent 1A EOG start attempts available with the air start system in this configuration?
'a.l 2 lb.I l<:--:1 I
~ 5 I
i.Allswer~ Ia I ~(lm LevE!11 IR I ~ognitive LeveG IMemory I iFacmiY:J ISalem 1 & 2 I ~xamDate]
I 12/19/20161 I ~ .. _ I~~~J@r~~~IQ]~~!~I~ ~~u.e:JLJ~o~o~I[] ;i5';1 D
" //~~
t!<Aill 054000K60?
LSyst~m/Evolu!ionTitle~ lEmergency Diesel Generators ! 10~4
~Stateme_rii] ~owledqe of the of the effect of a loss or malfunction on the followinq will have on the Emerqencv Diesel Generators:
receivers
!Explanation of, 55.41.b(8) Salem FSAR section 9.5.6, "Each receiver is sized to hold sufficient air for three cold diesel starts". Each EOG has 2 air
'Ansvver_s: __ J receivers, but with one CIT, there will be 2 starts left after 1 attempt at starting.
1 =*=-*=*
(EOG Lesson Plan Refere11ce Title ~=--=--J ~ _ Fa_cilit¥ Reference Number ii NOS05EDG000-12
~ ~eference Section ~ ~ge N~ ~evil;i*o~
II If 48-49 1112 I IDiesel Engine Auxiliaries !1205241 II I j Sh 1 1142 I I II II 11 11 I
~~~~e~-- Objectives 1EDGOOOE014 Material Required fo~ Examination j I j
'au:stion Source: ; Facility Exam Bank I ~-ue_st_io_nM_o_d_i_fi_ca_tio_n_.M_et_ho_d:__J_E_d_ito_r_ia_ll"-y_M_o_d_if_ie_d_ __,l [lJsed l:!uring Training PrograO!J D r***-***-**-***-****-**-1 31Jestion Source: Comm_e~ I I rcolllment
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!auestion Topic j *-------------------------------------------~
Given the following conditions:
- Unit 2 is performing a normal Liquid Release from 21 CVCS Monitor Tank via 22 SW header to Unit 1 CW JAW S2.0P-SO.WL-0001, Release of Radioactive Liquid Waste from 21 CVCS monitor Tank.
- The Radwaste Overboard Discharge Flow Recorder is OPERABLE.
- The 2R18 and the 2R41D rad monitors are OPERABLE.
- After commencing the release, the operator is compiling the Initial Data JAW appropriate attachment.
- When recording the 2R18 reading, it reads 10E6 cps.
- The 2R18 red alarm light is lit on the 104 panel.
- The 2WL51 indicates OPEN in the control room.
Which of the following describes what these indications mean, and how the operating crew should proceed?
he 2WL51 should have automatically closed on the valid 2R18 high radiation alarm. The NEO should shut 2WL51 locally.
The 2WL51 should have automatically closed on the valid 2R18 high radiation alarm. The NCO in the control room should shut 2WL51.
high. Verify the flow recorder and 2R41 D are OPERABLE, block the R-18 input to the 2WL51 on 2RP1, and continue the Verify the flow recorder and 2R41D are OPERABLE, block the R-18
--~ [CJ ~~~lll:he~ IR I ~nl!~e Level IApplication I ~ ISalem 1 & 2 I ~~~Ill~~~- l___12_1_19_12_0_1_.6I
~1068000K610 l~~~~~'SROValue:i@[~~l~~~~[JJlsROGroup:ILJ ,~~:¥; D
_systemfEvolution iitlej KA StatemE!!lt:. ~e of the of the effect of a loss or malfunction on the followinq will have on the Liquid Radwaste System:
monitors I
' ...... *1 Explanation of I 55.41.b(11, 13)6.82E5 cps is the ALARM setpoint which will automatically shut the 2WL51 (S2.IC-CC.RM-0028) The current
,Answers: , reading is above the setpoint at which the 2WL51 should have automatically shut, and the NCO should shut the valve remotely.
Additionally, S2.0P-SO.WL-0001 for releasing the tank, Step 5.5.9, says if the 2R18 alarms, then the NEO is to inform the NCO to shut the 2WL51. There is no provision for closing the valve locally.
---***-***** -*--- ............. *1 I Reference Title l'f:aciiityReiE!rence Number I ~ef~r~nce Section ]I Page No. Revision IRELEASE OF RADIOACTIVE LIQUID WASTE 11 S2.0P-SO.WL-0001 II ii 13 1127 I I II II 11 11 I I II I 11 11 I Material Required for Examination II II
'cillestion Source: j IFacility Exam Bank I !Question Modification Method: J Editorially Modified I IUsed D~~~Tr;:iilling Progrl3m. I D c°.ll1rll~~t~
- auesti.on-source 183676 I
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RO SkyScraper I SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List I Outline Changes I
! QuestionTopic - IRO 60 I When performing a Source Check of a Process radiation monitor, which of the following describes how to initiate the Source Check, and why?
Activate the Source Check ......
~ for 30 seconds or less to prevent solenoids from overheating.
!b.i
___J just until indication of rising level is detected. This will prolong source life.
C. Ifor 30 seconds or less to prevent unwanted automatic action on high radiation level.
I
~I just until indication of rising level is detected. This will ensure radiation level outside monitor remains less than detectable.
I
[~nsvv~ ~ IExam Level IR I ~()~nitivelevei*** 1Memory I Facility:* 1Salem 1 & 2 I [ExamDate: I 12/19/20161 fIB ~<;~~on: 1I~:
LJ ~~_§_1'._?l1P: LJ §'ffl-'-~"'""""'"
- ~5,~~' D c* c __ ,
I
~~y:>tem/~volution Title i I Process Radiation Monitoring System KA Statement*
L::_ _____
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Ability to explain and apply all system limits and precautions.
Explanation of 55.41.b(11) Both the system operating and surveillance procedures contain precautions limiting check source operation to 30
~J\!1.S_.....~~s_:_ _ seconds or less. B is incorrect but plausible because it's a true statement , but it is not the reason. C is incorrect but plausible since there are some monitors whose alarm action functions are not automatically blocked during a source check. D is incorrect because source check operation is not intended to raise rad levels outside component.
L.
Reference Title I L.. ~a~ility:Jteterence*N~inber _:] Reference Section
!Pa-****~****
I ___
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ge No. i Revision IRadiation Monitors - Check Sources 11 S1 .OP-ST.RM-0001 II 113 1131 I IRadiation Monitoring System Operation 11 S1 .OP-SO.RM-0001 II 114 I 138 I I II II ii 11 I
~:~. Nun1~e~-=:J I RMSOOOE006 I I
Material Required for Examination 1Question Source: JI New I
I I I[Qllestion Modification Method:
' - - - - - - - * * * -----.---- - - - * *---------------- -- -- ----- ___________ _ _ j JI I [se~ [)u!ing_ Training Progranll D II
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1Question Topic *-------------------------------------------~
Given the following conditions:
- Unit 2 is operating at 100% power during a summer heat wave.
- 21, 24, and 26 SW pumps are in service.
- SW header pressure is 106 psig.
- The 2SW308 #2 Bay Overpressure Protection valve slowly fails open.
Which of the following describes how the plant will respond with NO operator action?
OHA's B-13 21 SW HOR PRESS LO and B-14 22 SW HOR PRESS LO will annunciate at 1) _ _ _ psig, and the standby SW pump will auto start at 2
~ 11) 105.0
- 2) 99.5.
12/19/20161
[t<A:I 076000K402 I K4.02 I~Y~Q]"~~-~~~~Q][~l!~~io11:JI~ ~~[JJ~-~~~ro~p~LJ fi5:i43 D System/Evolution Title . j_s_e_rv_ic_e_w_a_te_r_S.:.y_st_e_m_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___.I 076 ___ _
ice Water S stem desi n feature s and or interlock s which provide for the followin sociated with SWS
!Explanation of! 55.41.b(?) Low pressure 99.5, auto start 95.5 Answers: '
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!Reference Section ; _Page No. Revision:
136 i=======================::::.!====================*;=============-~===~I====
~*-------------'--------~ _____.I_~__.
1L.O. Number I SWBAYSE009 Material Required for Examination _j I II Question Source:
.IFacility Exam Bank I Question Modification Method:
!I Direct From Source I Used- During Training Program D
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'§~~~ti~n-~ource com~ents: I I
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'clllestion Topic__ RO 62 Unit 2 ECAC is running loaded for testing IAW S2.0P-PT.CA-0001, Emergency Control Air Compressor Functional Test.
Which of the followinq would have an effect on Control Air Header pressure?
~] 2A 4KV to 460V breaker 2A4D trips.
I
- 1>
- 1
~
2C 4KV to 460V breaker 2C4D trips.
!cJ 2E 4KV to 460V breaker 2E6D trips.
I I
'd.J 2H 4KV to 460V breaker 2H5D trips.
I
[Answerl I b I [~xam Level i IR 1 iCognitive Level 11 Memory 1 lf'acility: 11 Salem 1 &2 1 iExam~~te: :I 12/19/20161 I I K2._0L_j [ROYalue: .§ ~~~-Y'Ci_lu_~:J~ ~~on:JI~ RO Group: 0 ~~ 0 -~~:43 D
"~'~
iKA:j 078000K202
[system/Evolutio-~ Titl~~ 078 rKAsJ~te 111~1l!J 1-------...._--~------"----------------------------;-
Explanation of* 55.41.b(8) Unit 2 ECAC is powered from 2C 460 volt bus. Station Air Compressors are powered from Group buses.
Answers: *
- Reference Section
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17
~================== ~I ===
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'.i..o. Number Objectives I CONAIRE005
~aterial Requi~~~_f()r Examination I I 11
[Question Sour~e:_! INew I ~~i~~~on Modification Metho~:_J,, _ _ _ _ _ _ _ _~I ~sed During Training Program_] D
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~1.1estion_Topi~J IRO 63 Which of the following describes Station Blackout (SBO) Compressor operation and its connection to the Control Air System during a station blackout?
The SBO Compressor _(1 )__ automatically start on a loss of all station power. After starting, the SBO _(2)_ the 1A and 2A Control Air Headers.
lal l
1)will 2) l.
must be manually aligned to
~ 1)will automatically supplies 2)
,cJ- 1) will NOT
- 2) must be manually aligned to d-:1l1) will NOT L
- 2) automatically supplies I
A!lswer1 c I l IExa01Level1 IR I I !Cognitive ~evel 1 Memory I ~cHity: 1 ISalem 1 & 2 l ~amDat~I 12/19/20161
.. .. . .,_c"nN;Y,'q->li
[!<A:; I079000K401 i5Yst!m-1e_v_o11l_u_o_n Title] 079 *_-:=-1
~ statement:l r---"'""'--~~---'--'---'-"'---..;..;__,,_;..;;_...;..... _ _;..;._;;....o..;.t_...;._;__j_;;__;_.;.......;;.;__;.._;_'""""";;_;_-""'------~-----L
~-* * * - - ------:1 1
Explanation of I 55.41.b(B) The SBO Compressor is required to be isolated from, and independent of plant safety related equipment except when iAnswers: required during operation during a blackout or other situations when there is a total loss of Control Air. The SBO is manually started
- and manually aligned to the CA headers 1A and 2A.
LO. Number Objectives I~**--*---**--*
STAAIRE013 Material Required for Examination .. JI 11
!Question Source:
- 1l_N_e_w_ _ _ _ _ _~I /auesti_o_n_M_o_difi_*c_a_ti~~-M_e_t~o_d_:_!j________. . . l. ~sed During Trainin~ Prograll"I] D
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RO SkyScraper I SRO Skyscraper I RO System/Evolution List SRO System/Evolution List I Outline Changes I 1Questi.C1~_T()J.licJ IRO 64 I Given the following conditions:
- 28 EOG is in service paralleled with the 28 4KV vital bus for a scheduled surveillance run.
- A fire occurs in 28 EOG room, and the fire detector in the room senses the fire.
Which of the following identifies how the Fire Protection system responds, and how the EOG operator should respond?
- a. The EOG C02 fire suppression system must be manually activated by the operator as they exit the EOG vestibule area.
~
~
The EOG Halon fire suppression system must be manually activated by the operator as they exit the EOG vestibule area.
- c. The EOG C02 fire suppression system will automatically discharge after a 13 second delay, the operator must immediately exit the 28 EOG area.
.d. The EOG Halon fire suppression system will automatically discharge after a 13 second delay, the operator must immediately exit the 28 EOG area.
1a::--*
,Answer L -********* ., ...
I a I *Exam Leve~ ~ !cognitive Level 11 Memory I if'aciiityl Isa1em 1 & 2 I IExamDate:.l I 12/19/20161 l'f<~__ ,ROValue::~ SRO Value: fill'~~i()~~:I~ ROGroup:'f:~j~~LJ KA:jlo86000K504 '55.43 0
- system/Evolution. Title , ~__J AAStatementj Knowledqe of the operational implications of the followinq concepts as they apply to the Fire Protection System:
Hazards to personnel as a result of fire type and methods of protection Explanation of 55.41.b(?) The EOGs are protected by a C02 fire suppression system. This previously AUTOMATIC system was permanently Answers: changed to a MANUAL activation system under Salem OCP 80115237. The Fire alarm will alert the operator to the fire, at which time they exit the EOG room/control room to activate the fire suppression system from the vestibule area. There is a 13 second after activation before the system dumps. The Halon distracters are plausible because Salem has other vital areas which have
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Irequired to exit area) or if there is other action which must be taken, as well as knowing the methods of protection (co2 vs Haion) l!:~~:..".'.u.111ber FIRPROE006 Material Required for Examination 11 II I!Question Modification Method~ I 1used During Training Prog.ram
- ~
Question Source: '!New II lo Question Source Comment~ I I
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RO SkyScraper I SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
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!Question Topicl Given the following conditions:
- Unit 2 was operating at 100% power when a steam leak upstream of 22MS167 occurred.
- The Rx was tripped and a MSLI performed successfully.
- Operators have transitioned out of EOP-TRIP-1.
- The PO is attempting to open 21-24SS94s, SG B/D Sample Valves, but they will not open.
- SGBD sample isolation bypass has been RESET.
Of the following, which identifies the reason the valves won't open?
,~
t-J Both SGFPs have trip signals locked in.
1 cl] Either Train A or Train B Phase A isolation failed to reset when its reset PB was depressed.
12/19/20161 j(A St~tei:rient:, ~ilitv to manually operate and/or monitor in the control room:
hase A and phase B resets I
!Explanation of l 55.41.b(?) For a trip and SI due to a single faulted SG (unisolable) the flow path will go from TRIP-1 to LOSC-1. The SI will NOT
!Answers: **---- I have been reset in TRIP-1, nor will it be reset in LOSC-1. The SGBD sample isolation reset will be performed in LOSC-1 (step 6.1)
~' **-'-****-~~*
in order to open the SS94's. The step prior to that is RESET PHASE A. This is due to the fact that the blowdown isolation bypass only bypasses the lo-lo level input into the AFW auto start circuit, which closes the SS94's. If the Phase A hasn't been reset, the nA,..., ,...,..,.... ........... + h .....
l c::c::nA .... c1 ......... 1; ..... ...1 -::air 4= .............. '" *.a. ..... ;,.i,... ................. +
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L _________R~ference_Title ______ __J '___!:acility Reference Number__ ~erenc~ Section _J LPage ~ Revision IRPS AFW Startup Logic Diagram I! 221064 II ii 11 8 I ISS94 Loop Diagram 11621216-1 11 11 111 I I II II ii ii I
~.~m~----- Objectives RXPROTE019 I I
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!Material Required for Examinatio~ I lQuestion ~ourc_:J IFacility Exam Bank I f§:uestion Modification Method:_J Direct From Source
~uesti~n s~urc~ c~~men5 , . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -1 1
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RO SkyScraper I SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List I Outline Changes I
[Question Topic 11 RO 66 I During shift turnover, the on-coming RO notices an OHA with reflash capability has 1 (one) piece of red translucent tape diagonally across its window box.
Which of the following describes what the status of this OHA is?
- -*..1
- a. The alarm is inoperable, and will not annunciate under any circumstances.
1b. The alarm is identified for heightened awareness, and has all functionality present.
~ The alarm has at least one, but not all, inputs disabled, and may not be a reliable source of information.
I
~I The alarms reflash capability has been defeated such that if already in alarm, a second alarm will not be annunciated.
I
- Answer- c I I ~am ~evi:i.J IR I ~o~nitive Level 11 Memory I tacility: I
! Salem 1 & 2 1 IExamDate: 11 12/19/20161 I 3.al ISRO V_il!u~_: j 4.2 I1Section: 11 PWG I RO Group:! I I
>:'w-; V9 IKA: 11940018101 I~1._! __
~
I iRO Valuej I 11 ISRO Group:j 1 I ~~*4!! D
[~t~m/Evol~tion Title I ..---------------------------------------.,. -GEN_E_R_I_
'KA Statement*'
- l. *;
KnowledQe of conduct of operations requirements.
Explanation of I 55.41.b(10) The single piece of tape is placed on the OHA to alert the operator that the alarm is not a reliable source of Answers: information. 2 pieces of red tape in a "X" signifies that the entire OHA window is INOPERABLE. Additionally, if one or more inputs
--*~
to a multiple input annunciator are inoperable, then red tape should be placed diagonally across the annunciator window. A is incorrect because the window can still alarm from an operable input, since it is not ("X'd). B is incorrect because the tape signifies
+h~+ th :~ . n;n,-, -~~ :LL-:+ ,..,... it 1-- f\.lf"'\T L. ,,... f,,11 f, *--.a.: r ;.,.. ,..,...-- ~~ - ...,.__ *- n* ..
Ireflash capability is not defeated, and as long as a second valid input conies in with one already in, the reflash capability of the alarm will cause it to annunciate.
=I Page No. I ]Revision; Reference Title j Facility Reference Number ] Reference Section -
IOperator Burdens Program 11OP-AA-102-103-1001 I I 1 a I 2 !
II I II I I II I 11 I I IL.O. Number Objectives I CONDOPE005 j~aterial Requiredfor Examination _J I II Q~estion Sour~':_'._J IFacility Exam Bank 1louestion Modification Method:
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.auestionso~_rce comments~ I I
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~uestion Topic-] IRO 67 I Given the following conditions:
- Unit 2 is operating at 60% power.
- Power was reduced when 22 SGFP tripped 2 days ago, and has remained at this level for 2 days.
- Operators are preparing to start a Main Turbine power ascension using dilution and automatic rod control to maintain Tavg and AFD on program.
- Tavg-Tref deviation is 0°F.
IAW OP-AA-300, Reactivity Management, how should the power ascension be started?
Assume this is a normal power ascension with all equipment available.
~ The crew concurrently initiates the Main Turbine load ascension and a RCS dilution.
~- The crew initiates a RCS dilution. As soon as the dilution is in progress the Main Turbine load ascension is initiated.
,----1 c.: The crew initiates a RCS dilution and waits until a RCS temperature rise is detected. Then the Main Turbine load ascension is initiated.
I
[d:j I.The crew initiates the Main Turbine load ascension and waits until a RCS temperature lowering is detected. Then the RCS dilution is initiated.
I
!lio§werl !c t;is~m !,,gy:§jl IR !~ggnitillg !,,gy:g! IMemor.y I IFacility: Salem 1 & 2 IJExamDate: ! 12119120161 fi<A:] j 194001G102 1T1.2H Jl~§va~GJ} sRo va1ue:J8!~~_c:~I~ ~9~~=1LJlsRo Group:LJ :ss.43. D ISystem/Evoluti9n, l"itl_i:_ iGENERI
- ~-----------~-----------~--------------~ ---~--
-KA Statement: I
- --*****-.::.:.:.:.J Knowledqe of operator responsibilities during all modes of plant operation.
Explanation of ' 55.41(5,10) Listed under the responsibilities of the Reactor Operator, page 7, 4.6.5, "Typically, during planned load changes where
,Answers: dilution or boration is required, start with the dilution or boration. The initial effects (RCS temperature change) of the reactivity change should be seen prior to initiating the load change. (PWR)" All the distracters have the correct actions in the wrong order.
i l --** ]'--
Reference Title
- I Facility Reference-Number=1 ,Reference Section _: i Page f119* I Revision IReactivity Management l 1 OP-AA-300 I 117 I 7 I I II I ii I I I II I 11 I I LO. Number Objectives I
~NDOPE005 I I
I Material Required for~)(~_mi_nation Que~ti~n Source] j Facility Exam Bank I Question Modification Method: :j Direct From Source IIused During Training -Program
- o Question~~~~c~~~~ment~ 1......-1?-.,in-n--------------------------------------.....,.,
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RO Skyscraper I SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
~------------~------------------------------~*
!Question Topic,
- --~------------------------------~---------~
IWhich of the following conditions will REQUIRE the suspension of fuel movement in the Unit 2 Rx vessel?
la~ Chemistry reports Rx Cavity boron concentration is 2499 ppm.
L_:_
'b. A NEO reports BOTH 100' elevation containment airlock doors are open.
~:- The PO depresses Fire Outside Control Room on Unit 2 Control Area Ventilation.
[cl._ Containment Radiation Monitor 2R12A fails causing a Containment Ventilation Isolation signal.
~~ ~ 1 Ex-amievel; ~ [c::~gnitiveTe...:ei ISalem 1 & 2 I IExamoate: 12/19/20161
~J 194001G14o I '2-.1.40 _H Ro va1ue:H 2.a11s-ROValue~l3.9 1 l~~~~i()_f1J PwG 11-RoGro-Ui)~I 11 ~~~~<>u~d 11 155:43" D iSystem/Evolution Title n*c*
KAsiatemeni* I Knowledqe of refuelinq administrative requirements. I Explanation o~ 55.41.b(11) C is correct because operation in the recirculation mode requires suspension of fuel movement. (SO.GAV P&L 3.6.3
.Answers:_ ..~ When aligned to FIRE OUTSIDE CONTROL AREA (Recirculation Mode),Core Alterations and movement of irradiated fuel is NOT permitted (T/S Bases 3/4.7.6)). Dis incorrect because Containment Radiation monitors are not required to be operable for Mode 6 or Fuel Movement or Core Alts per Tech Specs. Bis incorrect because the airlock doors are only required to be CAPABLE of i... ..... : ........... a..., .... ............. h~ ~-~- /C::.'l f"lP_C::.T ('A "-'""'7 *~ 0\ ti.;.,. - .1.1-. f"'f"'\1 D ' . ' _ ... __ ... : ..... ; ..... ,, 1 ')('li Reference Title
[- H-- Facility Reference Number . . J Re!~r~~ce Seciionl ! Page No. ----***
Revision:
ISalem Tech Specs 11 II 11 11 I IRefueling Operations-Containment Closure 11 S2.0P-ST.CAN-0007 II ii 8 112a I IControl Area Ventilation Operation 11 S2.0P-SO.CAV-0001 II ii 8 i 141 I rir\-------****
LO. Number I REFUELE012 "1_a~erial Required for Examina~i()~ I II
,Question Source: 11 Facility Exam Bank I Question Modification Method: i Direct From Source I[used During Train!ng Program D I
I.. ~. -
11_c;i~estion~?~rce comments:
I i
1ment*- 1 I
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RO Skyscraper I SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List I Outline Changes I
'~~_s~io 11 !oil§J I Ro 69 I IWhen performin9 a plant startup, when is MODE 2, STARTUP, entered IAW S2.0P-IO.ZZ-0003, Hot Standby to Minimum Load? I
!. i
~ When the Rx is declared critical.
~ When Control Bank withdrawal is imminent.
,-Cl When the Reactor Trip Breakers are closed.
I
'd.J When Shutdown Bank withdrawal is imminent.
I
!Answer 11 b I 1examl..evel- IR I C()~nitive Level 11 Memory I r*c~
Facility: ISalem 1 & 2 I .Exam Date:
* I 12/19/20161 LJ L~R() <;~ LJ
- 7.W-"F:'f""' '"
'"~~()~ ~ ~E!(;ti().'1] I~ §O:Group:j l,!43~ D
- -*** "~
~J 1940018235 12.2.35 !RO Value: 1IJ]" '
! - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ' ;GENERI I KA Statement* I Ability to determine Technical Specification Mode of Operation.
Explanation of I 55.41.b(6) Step 4.2.21.3 When the withdrawal of Control Bank "A" is imminent, PERFORM the following:
'Answers:
L ...... __ .
RECORD time of Mode 2 entry in the Control Room Narrative Log.
UPDATE WCM to Mode 2.
RECORD Date and Time of Control Banks withdrawal in Attachment 3, Technical Specifications Pre-Criticality Surveillance Data,
<'--"-- /\
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Reference Title : 1---FacilityReferencE! Number l-ReferE!11ce ~E!(;ti()n______J if>a9e-No.. -Rev_~si()n:
j Hot Standby to Minimum Load 11 S2.0P-IO.ZZ-0003 II ii 18 1143 I I II 11 ii 11 I I II II 11 11 I fl.:~:-~-ll~~~ Objectiv 3E004
- Material Required_~or ~(illlil"lat~ I II Question s~~rce: J IFacility Exam Bank I Question Modification Method: i Direct From Source Ii.Jsed During Training Program D I
1 Questi_~n so~~e c-C>mmenis 1
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,.::;_ ...... _ ... **-*****'" c""'"'" *--~
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RO SkyScraper J SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes j :§uestion Topi~ ~R-0_7_0--------------------------------------------*
IGiven the following conditions:
- Unit 2 is operating at 100% power.
I- 100% AFD Target is -1.5.
- Between 0100 - 0140 today, 40 AFD penalty minutes were accumulated during a Main Turbine Valve Test which caused a rapid power reduction to be performed when a steam valve could not be re-opened initially.
- At 2300, 22 SGFP trips.
- At 2301, Rx power is 87% and lowering with AFD at -9.1.
- At 2303, Rx power is 66% and the Turbine load reduction is complete, with AFD at-10.1 Assuming power and AFD remain at 66% and -10.1 respectively, which of the following describes the required power reduction the crew must take IAW Salem Tech Specs?
Power must be reduced less than 50% by ....... .
.Exam Level , Cognitive Level \Facility: J :ExamDate: I
,KA::j 194001G239 112.2.39 /ROValue::l 3.9j!SROValue: ,4.5 !;Section;:jPWG l,ROGroup:I 1l;SROGroup:il 11 System/Evolution Title ' ,GENERI I
- --------------------------------------~ ~______]
KAStatement:'~----------------------------------------------
Knowled e of less than or equal to one hour Technical Specification action statements for systems.
1 Explanation of 55.41.b(5,6)LCO 3.2.1 action a (for >90% power) and action b (50-90% power) applies. The MT auto runback upon a SGFP trip
I 1
Answers: ! occurs at 15% per minute. The AFD Target at 100% power (Rev. 18 ofTables) is -1.5, with a band of +6, -9. The target is adjusted for Rx power, so with power at 87%, Target is -1.3, and band of-9 = -10.3, so at 2301 AFD is still within the Target Band. With power at 66%, Target~s -?.99, and ~and -9_= -9.99. With indicat_ed AFD at -10.1, AFD is out of b~nd at ~303, and Penalty Minutes l outside of Target Band at 2303+20=2323. The action for outside of band for 60 minutes of penalty minutes (but still within COLR IIlimits) is to lower power to <50% within 30 minutes. So Rx Thermal power must be <50% with 30 minutes of 2323, which is 2353.
The distracters are using the 15 minute action time required for power >90%, or using the 2301 time as the time AFD is out of band plausible if the -9 of Tar et Band is incorrect! used as the actual AFD limit or both.
Reference Title . _J L__£acility Reference Number I
'Reference Sectic:ri__j Page No.! jRevision
- ==========================~
I Salem Tech Specs l I3/4 2-1 11278
~==========~~======~!
I~T=a=bl=es=::=::=::=::=::=::=::=::=::=::=::=::::::.li~S=2=.R=E=-RA==.Z=Z=-=00=1=1=========~===========::=::. I~2=48=:::::::.
j_s_a_le_m_C_o_re_O_p_e_ra_ti_n_g_L_im_its_R_ep_o_rt_ _ _ _ ~l !_c_o_L_R_S_a1_e_m_2_ _ _ _ _ _~ ,_ _ _ _ _ _ _ __, ';.1_6~~=_::_=_=~=-l j_6_ _~
iL.O. Number i Objectives I FLUNCYE002 j_ ____,
!Material R~ciuH~d for Examination II I
Questicl!\Sourt:e: '.i New I fou~~tiot(M()CliftS~ti,()n M~t,~f):at I I !Used During Training Pro9rilmi D Que~ti~[l,S()ur~e, Co1t1ments; I
!~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~---'
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!Comment i I i I
l I I
RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes laues!~on !~pi?.i IRO 71 I I Which Emergency Classification results in an automatic extension of annual dose (TEDE) limits for ERO personnel that have an NRC Form-4 on file, and what is the dose limit extended to?
I
~ SITE AREA EMERGENCY, 5000 mrem.
I
~ SITE AREA EMERGENCY, 4500 mrem.
I
~ ALERT, 5000 mrem.
I Answer]! d I .Exam Level R I 11 Cognitive Level I Facility: 11 Salem 1 & 2 1 -examoa!&:-1 I 12/19/20161 I'_2._3._4_ _ -~~~~~J@ -~~~-~ClllJ~_:j fill !Section: 11~ RO G--;.oup:j LJ ls RO Group:! LJ 55.4~; D
'"~ n- *-~.,~
- ~*- -T~
IKA: JI 194001 G304 lsYsteffi/&olution Titt!] !-~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~--
1 GENERI m
1,'
!KA Statement:*
Knowledge of radiation exposure limits under normal or emerqencv conditions.
Explanation of 55.41.b(12, 10) Upon an ALERT declaration, workers with a NRC Form 4 on file have their dose limit raised from 2,000 mrem to
- Answers: 4500 mrem.
- ~--
Reference Title ILr--------*-------- * ---------] ~-------------- ,----
Facility Reference Number *Reference Section IPage No. 11**** ... **-***_*
~__El~is_ion:
IOPERATIONAL SUPPORT CENTER (OSC) RAii NC.EP-EP.ZZ-0304 I 11 I 16 I I II I 11 I I I II I ii I I i.o. Number - - -
~----------*-*_J Objectives DCONE003 Material Required for Examination I I
!Question Soutce] Facility Exam Bank I I[':'sed During Training Progralll ! D i~Ll_e~ti?l'l_~?Llr~e ?omment~.
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1135687 I I I I I I I
RO Skyscraper I SRO Skyscraper I RO System/Evolution List SRO System/Evolution List I Outline Changes I LQuestion Tor:iic 11 RO 72 I A Containment Entry must be made in Mode 1.
When is Radiation Protection Supervisor (RPS) approval required AND what is the limit for the number of personnel that may enter containment?
Assume the Shift Manager has NOT granted permission to exceed the procedural limit The RPS must give prior approval if the entry is made during ....
[~J a power ascension at >5% I hr ONLY, and no more than 10 people may be in containment at one time .
I
.t>.J any reactor power change at >5% I hr, and no more than 10 people may be in containment at one time.
I le.
c~
a power ascension at >5% I hr ONLY, and no more than 20 people may be in containment at one time.
I
'~ ny reactor power change at >5% I hr, and no more than 20 people may be in containment at one time.
I
,-*******1@=]
- Answer .£___J Exam Level : R I I Cognitive Leveij IMemory I Facility: J ISalem 1 & 2 I I ExamDate:
- I 12/19/20161
-~~
~=ii 194001G313 I _2-2_1_3_ _ ~()\fCl_lllE!_:j~ _SRO Value: l~ISection: "I~ I~() (;l"_Cl_llJ>~LJ.SRO Group:LJ ilf3; D System/Evolution Title GENERI
!KA StatemE!ntl , . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - : -
Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entrv reauirements, fuel handlina responsibilities, access to locked hiah-radiation areas, alianina filters, etc.
Explanation of 55.41.b{12) SC.SA-ST.ZZ-0001, (Rev. 5) SALEM CONTAINMENT ENTRIES IN MODES 1 THROUGH 4, requires prior RP
'Answers~ Supervisor approval to enter containment in Modes 1 or 2 during ANY power change >5% I hr. It also limit entry to 10 people per operable air lock. 2 airlocks = 20 people. See steps 2.4 & 3.2.
__ ___E!-__-_-!--it-le*-_-....- .- - - - i ~I_F_a_c_il_it_y_R_e-fe_r_e_nc_e_N_llmber ]
Refer_E!_l1c- iRefe!ence Section [Page No. Revision ISALEM CONTAINMENT ENTRIES IN MODES ii SC.SA-ST.ZZ-0001 II q3,4 I 5 I I 11 11 1I I I I 11, _ _ _ _ ____,11, _ _ ____.q I I
~H~ITI-il~~:== Objectives I CONTMTE012 I I
I, _ _ ___.
,MatE!!ial Required for Examination iI II I
Question Sourcej Facility Exam Bank I!.9~=~~().:"__f.1odification Method: !I Editorially Modified I[used During Training Prograrlll D 9uestion Source C~~~~nir;" 1159346 MODIFIED ANSWERS FROM "5%" TO "5% I HR."
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\,011111.~ ... I I
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RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes Question Topic I IRO 73
- IWhich of the following contains conditions that warrant entry to EOP-LOCA-5 "Loss of Emergency Coolant Recirculation"? __J
~ RWST LOW LEVEL alarm annunciates with <62% level in Containment Sump.
~
The hot leg recirculation flow path is unavailable due to blockage of flow paths.
~~
- c. RWST LOW-LOW LEVEL alarm annunciates requiring all ECCS pumps with suction from the RWST to be stopped.
- i
-d.1 LOCA outside containment is indicated, and both RHR pumps were stopped IAW EOP-LOCA-6, LOCA OUTSIDE CONTAINMENT.
'--~-
I I
Answer I ~ IExam Level I ~ ICogmtive Level l I .. .. j Appl1cat1on I ~_<=~~:J j Salem 1 & 2 I iExamDate: 1 I 12/19/201611
~I 194001G404 I;2.4.4 *,RO Value: :@~~Q!:Jsection: :i_~~.J !Ro Group::[J],SRO Group:ILJ
~stem/Evolution Title 1 KA Statement: I .------------------------------------------------:-
Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and I abnormal operatinQ procedures.
Explanation of, 55.41.b(10) EOP-LOCA-5 can be entered from 5 places. 1. LOCA-1 step 16 with no RHR pump and associated SJ44 available; 2.
Answers:
- LOCA-3 step 2, Containment sump level less than 62%; 3. LOCA-4 step 5, No RHR pumps running; 4. LOCA-6 step 6.2, with RH1 ,2,26 shut, 21 and 22 RH19 shut, 21 and 22SJ49's shut and RCS pressure not rising; 5. Loop from LOCA-5 step 28 when RWST level is still above LO-LO (1.2') setpoint. Answer is correct because containment sump level should be rising as RWST
- I r" ic- ~-------"' h--~ IC"O. i+ ;.,.. ..... ___ ..J:.1.: .... - J.L.. .... .a. ....... 1lrl hn. +................... ,.......... O\/\/QT 1.......... 1 ..J-----.....1,; . f"'I *- ~ .. ,...
as 1 CS pp continued to draw water from RWST. Dis incorrect because LOCA 5 only requires RHR pumps*t~ be avail~ble, not in 0
service. Bis incorrect because there is no provision in LOCA-4 to check if the flowpath is blocked or not. It only has the alignment performed, then return to procedure in effect.
l_ Reference Title i Facility Reference Number I
- Reference Section I! Page No. i Revision 1 I::============================:::'
Loss of Emergency Recirculation
!j 2-EOP-LOCA-5 j 111 I ~'3=0=~1
~'T=r=an=s=re=r=to=C=o=ld==Le=g=R=e=c=irc=u=la=ti=on==========l~l2=-E=O=P=-=L=O=C=A=-3============:1~===============1tl1====:::::::'.l~l3=0=:::::::'.I 1
1
_ _ _ _ _ _ _ ___.I! 11_ _ ____,Ij _ ___;l l_--'I iLO. Number Objectives ILCA3U1E007
!Material Req~iredfor E~(lminatiori I i l I!
I , ?"
- Question SourcE!: J IFacility Exam Bank I!O~estio~ Modification Methocl: **I Editorially Modified I!Used During Training Program D iauestion S~urce Comments; 142264 . Chan?,ed correct answer wording from "RWST inventory is being depleted .... " to "RWST LOW LEVEL alarm
-- annunciates ....
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- Comment'* .
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RO SkyScraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
- QIJestion Topicl l RO 74 Unit 2 has entered S2.0P-AB.STM-0001 EXCESSIVE STEAM FLOW due to an extraction steam line rupture. A Reactor trip and MSLI have been performed, and the steam leak has been isolated. Safety Injection was not required and did not initiate.
Which of the following describes how S2.0P-AB.STM-0001 will be used following performance of EOP-TRIP-1, Rx Trip or Safety Injection?
S2.0P-AB.STM-0001 .....
r:-: must be re-entered from point it was left and completed regardless if entry conditions are still met.
- itl*I
~ must be re-entered from the beginning and completed regardless if entry conditions are still met.
c____j C.* should be re-evaluated to see if entry conditions are still met. If they are, re-enter AB from the beginning.
I
~d.; should be re-evaluated to see if entry conditions are still met. If they are, re-enter the procedure from where it was left at Rx trip.
I Ans;eri le I Exam Le~ IR I cognitive Level I 11 Memory I !f:acmty:: ISalem 1 & 2 j 1ExamDate: 11 12/19/20161
~\l~~sRova1ue:J£D"~~l~~~LJ~~~~~LJ ,~r~~;J D
,,~~%1,Jl';'i1;
,KA: j 194001G411 1,2.4_.1_1__
r---. --~-- -,
System/Evolution Title 1 GENERI iKA Statement:
Knowled e of abnormal condition rocedures.
Explanation ojf 55.41.b(10) Step 4.4.1 If a reactor trip occurs while performing an AOP, either intentionally or as directed by the AOP, the AOP Answers:
*-*-** *~-
should be exited and the EOP entered. If the AOP calls for a trip of the reactor, the action is defined in the same manner as in 4.2.5 (fourth bullet, EOP-TRIP-1) for EOP action steps. There are cases where steps must be completed as directed in the AOP (i.e.
TRIP affected RCPs) prior to entering the EOPs. Once this action is completed, then entry into EOPTRIP-1 is directed by procedure re-evaluated to determine if performance of the AOP is still. required,(i.e. the reactor trip did not terminate the abnormal condition). If I performance is re uired, the AOP should be re-entered from the be innin .
il.0._t-Jumber Objectives I PROCEDE006 j_ ___.
Material Required for Examination II I!
-Questio~~ource~J lFacility Exam Bank 11~~-estion Mo~ification M~thod:-
- 1Editorially Modified I ',Used During Training Program
~-*-**--*----******* ,---***** ' **- D J
!Ques~ion Sour~~ Commen~
172934 changed from following TRIP-2 to TRIP-1 based on new rev to EOPs I
~-******-*" '
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RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
_Q~estion Topic
- IRO 75 Given the following conditions:
- Unit 2 is operating at 100% power steady state.
- The unit has achieved "black board" status on the OHA's with NO OHA's currently in alarm.
- An expected OHA is NOT received when opening a panel which provides an OHA.
Which of the following describes the control room response IAW S2.0P-AB.ANN-0001, Loss of Overhead Annunciator System, if it is determined that a complete and total loss of ALL Overhead Annunciators has occurred and cannot be restored within 15 minutes?
!a' c~
Initiate alternate alarm check of the OHA system every 15 minutes by opening and closing a RPS or SSPS cabinet door.
_b. I Initiate a controlled shutdown at <5% per minute to bring the unit off line. Line.
~
c.* Initiate continuous control console walkdown.
~~I Trip the Rx and GO TO EOP-TRIP.
__ I I JI I 'f:acility: I ISalem 1 & 2 I ~amoate:" I Answer I~ Exam Level R I :Cognitive ie~el Memory 12/19/20161
-- - ~'"~"",. ,
.~I 194001G432 I 2.~] ~~~~aiUel~ ~~I~ _Ro GroUP:]LJ ~~r~~LJ _§,~:43' D 1*---
[system/EVOiutio-n Title 1
,_GENERI]
KA-Statement-=1 c_ --**-------~-'
Knowledge of operator response to loss of all annunciators. I
[Explanation of 55.41.b(?) With a loss of all annunciators, tripping the Rx or initialing a power reduction are not warranted unless overriding plant
~_11i;wer~_1 status would direct it, not just from the annunciator problem. Initiating continuous walkdowns of control consoles(and P-250, etc.) is directed. With a total loss of OHA's, you don't check functionality by trying to initiate an alarm every 15 minutes, that's performed to verify status if some functionality is present.
=-- l Reference Title yacillty R~ference Nu!Jlber - ~ference-Secti()_~ : Page No. Re11is!on]
I Loss of Overhead Annunciator System 11 S2.0P-AB.ANN-0001 JI ii 14 1123 I I II 11 II 11 I I II Ii 11 11 I
~Numb-_e-r- - - - ]
I ABANN1 E002 I I
- ,M;:iterial Re(Juired for E~_amination_J I II Q~estio_l"l_~ource: 11 Facility Exam Bank I -Question Modification Method: .Ii Direct From Source I,Used Q_~rif19 Traini11g Programl D
-- I I.
,-Question Source Commentsj
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Comment i I
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U.S. Nuclear Regulatory Commission Site-Specific Written Examination Applicant Information Name: I Region: I
--- ---- ----- - - - - - -- --- ---- - - I-;:: --- ----- --- -- - -- - ------
Date: 12/19/2016 *Facility: Salem 1 &2 I
License Level: SRO I Reactor Type: W
--- -- --- - -- -- --- -- --- -- Ir --- -- -- - --- -- -- ---- ---- --
Start Time: Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
-- ------ - --- - - --- -- ApP-,icanl GertffiCaflori- -- - --- - ---
All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results RO/SRO-Only/Total Examination Values I I Points Applicant's Score I I Points Applicant's Grade I I Percent
Senior Reactor Operator Answer Key
- 1. a
- 2. d
- 3. a
- 4. a
- 5. a
- 6. d
- 7. d
- 8. a
- 9. b
- 10. a 11 . b
- 12. a
- 13. d
- 14. c
- 15. d
- 16. c
- 17. b
- 18. c
- 19. d
- 20. b
- 21. d
- 22. d
- 23. b
- 24. c
- 25. a Page 1
RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes J I
'Question Topic 11 SRO 76 Given the following conditions:
- Unit 1 is operating at 100% power.
- An automatic Rx trip occurs when a loose wire in Main Power transformer Phase B causes a Main Generator trip.
- The RO performs 1-EOP-TRIP-1 Reactor Trip or Safety Injection immediate actions with no SI required.
- The CRS transitions to 1-EOP-TRI P-2, Reactor Trip Response after verification of immediate actions.
- Only TRIP-1 Immediate Actions were performed prior to transitioning to TR\P-2.
- Upon entry into EOP-TRIP-2, the PO reports:
- 11 AFW pump has failed to start.
- 12 AFW pump has started but a malfunctioning Pressure Override circuit is keeping 11 AF21 and 12AF21 shut.
- 13 AFW pump tripped as it was accelerating during start.
- All SG NR levels are off-scale low.
- SPDS indicates a Heat Sink Red Path exists.
Which of the following describes the next action the CRS should take?
I a.: Direct the PO to establish Aux Feedwater flow IAW 1-EOP-TRIP-2, Reactor Trip Response.
I
'hl I nirPr.I thP PO In Od'lhli<;h ~~::iin F, - fl""' 14W 1- FnP-TRIP-? RP::irtr.r Trin ~ ",,*~~ I c.: II Immediately transition to 1-EOP-FRHS-1, Loss of Heat Sink, ONLY if 3 of 4 SG WR levels are <32% to establish SG Bleed and Feed.
i;f~l 11mmediately transition to 1-EOP-FRHS-1, Loss of Heat Sink, based on the SPDS indication of a valid Red Path, and perform a SGFP Prompt Recovery \AW S2.0P-SO.CN-0007, SGFP Prompt Recovery .
I .---;
Answer 1~ Exam Level 'i ~ Cognitive Level i j Application I :Facility: I t ISalem 1 & 2 I ,Exam Date: ! l___12_11_9_12_0_1_,61
~looooo7A202 J EA2.02 /fROvaiue?@~'section: I~ ROGroup:LJ:sROGiOUP:1LJ 55'.1¥£1 ~
- System/Evolution Title i Reactor Trip 007
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~--' ~~~-
KA Statement: i Ability to determine and interpret the following as they apply to Reactor Trip:
Proper actions to be taken if the automatic safety functions have not taken place
!Explanation of i 55.43.b(5) CFST's become active upon exit from EOP-TRIP-1. However, from CFST procedure .... "SPDS is not designed to be
! used as a primary indication, and no actions should be based upon SPDS indications without verification of the primary indications, Answers:
which are the installed Control Room 1 E instruments." The crew ould perform the actions at Step 3 to check total AFW flow >22E4 lbm/hr, and if not, start 11-13 AFW pumps as necessary to establish it, which would include defeating Pressure Override circuit.
Th~,.,,_:_ t:eed1Mater sten is AFTER the AEJill..sJ.eo This 011estion is SRO level based ac l,(no\Mioa M£hi,...h ..1 * ........ +,.. ,,...,... ,~,.. ..... ,...~
I!
\transition to another pro~edure) and the actions in that pro.cedure. The FRHS-1 distracters are plausible if incorrect applic~tion of CFST usage after transition out of TRI P-1 are applied.
.r
~ Reference Title jCritical Safety Function Status Trees ii II Facility Reference Number EOP-CFST-1 j ,Reference Section II
,,Ii Page No. : i Revision; II 31 I I Reactor Trip Response I! EOP-TRIP-2 II Sh 1 II 1130 I I ll II 11 i1 I ILO. Number ITRP001 E001 Objectives ITRP002E005
(Material Reql.Jfred for Exariiination *.. 11 jouestion SoursE!:
- i l_N_e_w________.I !Ouestion. M~~ificatio6M,~J~od: .'.JI ! :used During Traini11g Program I D
\Questioll S,ource Comment.s I I
- ~----------------------------------------~
- comment I I I I I I
RO SkyScraper I SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes iauestion Topic i , . . . S _ R _ 0 _ 7 _ 7 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - , i Given the following conditions:
- Salem Unit 2 is in Mode 3, at NOP, NOT.
- All four RCPs are in service.
- 22 RDMG set is in operation for testing, with its motor breaker and generator breaker shut.
- Reactor Trip Breaker "B" is racked in and shut.
- Reactor Trip Breaker "A" and both Reactor Trip Bypass Breakers are open.
Which of the followin identifies how Tech Specs will be applied if a RCP were to trip, and the bases for that application?
'a. l ALL RCPs are required to be operable to provide decay heat removal and to satisfy single failure criteria. A cooldown to Mode 4 IS required.
- b.
- Only TWO reactor coolant loops are required to be operable to provide decay heat removal and to satisfy single failure criteria. A cooldown to Mode 4 is NOT required.
ALL RCPs are required to be in operation to provide decay heat removal and ensure mixing, prevent stratification, and produce gradual reactivity changes during boron concentration reductions in the RCS. A cooldown to Mode 4 IS required.
@] Only ONE RCP is required to be in operation to provide decay heat removal and ensure mixing, prevent stratification, and produce gradual reactivity changes during boron concentration reductions in the RCS. A cooldown to Mode 4 is NOT required.
AnSv;e~ @=] f Exam Level j ~ !cognitive Level i IApplication I iFacili m 1 &2 ~am Date: 1 I KA:!joooo15G237 112.2.37 'ROValuelj 3.6liSROValue}~~Section:il~ ROGroup:lj 11 SRO Group:'
System/Evolution Title IReactor Coolant Pump Malfunctions
- KA Statement* I Ability to determine operability and/or availability of safety related equipment.
[Explanation of I 55.43.b(2) The first part of this questions require RO knowledge to determine what constitutes an "energized" rod control system. 3 1
Answers: i of the 4 RTB and RTBBs being open is considered de-energized, even with a RDMG set in operation and a single RTB shut. (TS page 3/4 4-2a). With the unit in Mode 3 (rod control deenergized means can't be in Mode 2, and at NOT can't be in Mode 4), LCO 3.4.1.2 requires TWO operable RC loops including RCP, SG, and loop. It also requires ONE loop in operation when rod control is
- Of"'D _.
rloqn.Amized ll11ilb EOl le Ei1CE!s land loons) ao.ei:ab~" * ,;,. .................... . J.:-- h.-,,,..,..._,...i ,... .... r--f.:11 IImeeting the minimum requirement for the LCO. The bases -for this LCO is as- stated in correct answer. Choice B is partially correct, since the operability portion is correct and the cooldown not required part is also correct. However, the bases does not reflect the reason as being single failure criteria. Single failure criteria refers in this case to the minimum required loops IN OPERATION.
(Bases B3/4 page 4-1.)
i Reference Title I
i Facility Reference Number ' 'Reference Section i ! Page No. : Revision' ISalem Tech Specs II II LCO 3.4.1.2 II3/4-2,2a ! 144/282 I I II II 11 !I I I II II 11 11 I LO. Number Objectives SOOOE009
- Material R~cjuired fe>r EX~mination *I l
- ou~stio~ :source:. l l_N_e_w________.l [Qu~~Hon~9,dificatfonMeth9d: ~ J I ,used Quriri91r~ining Program I o
~~~~~~rri~~1 ________________________________________ ~1
[cornmerit "
I I I I I I
RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes I
!ouestion Topic ! ISRO 78 Given the following conditions:
- Salem Unit 2 is operating at 4% power awaiting final approval to enter Mode 1.
- Main steam dumps are in service maintaining Tavg at 548°F.
- 21 SGFP is in service, 22 SGFP is latched and at idle speed.
- All AFW pumps are secured and aligned for normal standby operation.
Subsequently:
- An automatic Rx trip signal is received, but the Rx does not trip.
- All attempts to trip the Rx from the Control Room fail.
Which of the following describes how the CRS should proceed?
Initiate manual rod insertion ......
I
~ then enter 2-EOP-FRSM-1, Response to Nuclear Power Generation, and start both MDAFW pumps.
~I then enter 2-EOP-FRSM-1, Response to Nuclear Power Generation, verify feed flow >44E4 lbm/hr from SGFP's.
le.:
~
Ithen continue in 2-EOP-TRIP-1, Reactor Trip or Safety Injection, then TRIP-2, Reactor Trip Response, since FRPs are not in effect in MODE 2.
id.: Ithen continue in 2-EOP-TRIP-1, Reactor Trip or Safety Injection, then TRIP-2, Reactor Trip Response, since reactor trip is confirmed with Rx II Iµuwer "-;J7o.
I ! ..
!Answer i ~ tExam Level i ~ rCogmtive Level
- I Applrcatron
.. 11 Salem 1 & 2 I !Fac1lrty: I E~ ,___1_2_11_9_12_0_1~61 1
~I 000029G244 I[2.2.44 !RO Value: i@lsRO Valuej~ !Section::!~ jRO Group:"[J}lsRO Group: LJ ~~:~a;, ~
!system/Evolution Title IAnticipated Transient Without Scram 11029 IKA L..::
Statement:
Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
iExplanation of' 55.43.b(5) The EOP network (including FRPs) are in effect in Modes 1-3. Just because Rx power is initially <5% does not indicate
'Answers: a Rx trip confirmation, which also includes negative SUR and power lowering. FRSM doesn't check any feed flow, it specifically states AFW flow, so while Main Feed flow is still occurring, operators will still start both MDAFW pumps in FRSM-1.
i: Page No. !'I Revisi~*
Reference Title Ii Facility Reference Number ; Reference Section 1 1
j Reactor Trip or Safety Injection 112-EOP-TRIP-1 I 11 i 131 I I Response to Nuclear Power Generation 112-EOP-FRSM-1 I ii 1130 I I !I I 11 11 I
'.LO. Number I FRSMOOE001 Objectives I TRP001 E007
!Material Requir~d for Examlnatioif ;; ,j I
': Qu~stion so~ l_N_e_w______ __.I Question Mo~ification N)ethod:,'
f i I 'Us.ed During Tra"lnfog Program D j
!Ouestion'.Source ~omments; I I
!~-~--~-----~----------~----------~---------'
\Comment I I I I I I
RO Skyscraper I SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
- ~~E!~~ion-_~~:p~j Given the following conditions:
- S2.0P-IO.ZZ-0010, Spent Fuel Pool Manipulations is in effect.
- A tubing break causes a total loss of air being supplied to 21 Fuel Handling Building Supply Fan Inlet Damper.
Which of the followin describes how the CRS is required to roceed?
ystem inoperable based on not having ALL FHV fans operable. Suspend all operations involving movement of fuel within I.
- b. Declare the FHV system inoperable based on not having ALL FHV fans operable. Suspend all operations involving ANY movement of fuel in the Fuel Handling Building.
Declare the FHV system inoperable ONLY if the loss of air to the damper causes Fuel Handling Building D/P to become positive. Suspend all operations involving movement of fuel within the Spent Fuel Pool.
Declare the FHV system inoperable ONLY if the loss of air to the damper causes Fuel Handling Building D/P to become positive. Suspend all operations involving ANY movement of fuel in the Fuel Handling Building.
~n!:;Vl/E!r ~ !E:x_itl1l~E!1'e Date: I 12/19/20161
~loooo6sG142 112.1.42 1t~~:Ya1ue:ll 2.sjsRovaiuej 3.4l 1 secti'<>n:lj~R0Grouil:JI 11isRo-Grou?:'I 11 i=4~. ~
[syi;tt?l1l'E:ll'C>'~!ion_!it1E!.* . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . . . . , . ~~s___J
~ement*I -~
I ,, ~
' ~
.. *~'
Explanation of 55.43(b}7. LCO 3.9.12 states the Fuel Handling Ventilation System shall be operable with: 1) 2 exhaust fans and one supply fan
!Answers: operable and operating and 2) capable of maintaining slightly negative pressure in the Fuel Handling Building. The Inlet Damper is interlocked to open when its Supply Fan is started, and fails closed on loss of air. With no air supply, the fan must be considered inoperable even though it remains running. With no supply and 2 exhaust fans in service, building pressure will remain negative.
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/\ l\ln equipment are available OR OPERABLE prior to, and during, operations involving movement of irradiated fuel within storage pool.
With the FHV system inoperable, LCO 3.9.12.a, action a, states to "suspend all operations involving movement of fuel within the storaqe pool until the Fuel Handlinq Ventilation Svstem is restored to operable."
Reference Title I Facility Reference Number ___]
.. . . R_efE!~E!~CE! SE!ctio~ _] i Page No] [Re~ision:
I Salem Tech Specs 11 lj3.9.12 !I314 9-13 I 282 !
I Fuel Handling Ventilation System !I NOS05FHVENT-08 II 1116, 18 I 8 I I II II II I I I FHVENTE010 I I
j_ _____.
!Material Required for Ex~l1l~.<tt!on _J I II Question Source: J INew IiQuesr -- -- ,.
" I :used During Training Program D L_ -~ .. --~-. -
Question s?~~~~-~o~ I I
!C_..,;,~c*-*n J I
I I
RO SkyScraper I SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List I Outline Changes I Question Topic I l,_s_R_o_s_1________________________________________~I Given the following conditions:
- Salem Unit 2 was operating at 100% power when a LOCA occurred.
- Operators are performing actions in 2-EOP-LOCA-1.
- 20 minutes after the Rx was tripped:
- RWST level is 19 feet and lowering
- RCS pressure is 350 psig and stable.
- Containment pressure peaked at 16 psig, and is 13 psig and dropping slowly.
- Containmentradiationmonitorsread<1R/hr. ,1 _1 ..
- RVLIS Full Range is 100%. low h' i,t.(i(1 /1e; 1
- 26 minutes after the Rx was tripped, the RWS~level alarm is received.
- When checking containment sump level at the beginning of 2-EOP-LOCA-3, the RO reports that containment pressure is now reading 1.5 psig.
Which of the followinr:i identifies the HIGHEST ECG classification for these conditions?
~ 14 point Alert.
I
\b.] 15 point Alert.
I
~ 17 point Site Area Emergency.
I
~Io µu111t .:i1u; r11ect crner!,Jem;y.
I
!Answer i [Q' iExam Level!~ Jcognitive Level I !Application I !Facility: 11Salem1 & 2 j ,ExamDate: 1 j___ 12_1_19_12_0_1~6I
~I 000069G441 I 2.4.41 I RO Value: {~j~ Section: :I~ RO Group: LJ 'sRO Group:! LJ ,§5.4:f ~
System/Evolution Title ! /Loss of Containment Integrity I ~~:
KA Statement* i Knowledqe of the emergency action level thresholds and classifications.
!Explanation of 1155.43(1,5) A LOCA which results in RCS pressure lowering to 350 psig will result in subcooling being lost. This yields 5 points due I IAnswers:
I i to the loss of the Reactor Coolant System Barrier. Containment pressure rise followed by rapid, unexplained pressure drop (13 psig to 1.5 psig during a LOCA over 6 minutes) is 3 points for the loss of the containment barrier. The 4 point alert is if the loss of subcooling was not recognized and the loss of containment not recognized. The 5 point alert is if only the loss of the RCS barrier is
-- --* Tho 7 ' ,+ C' /\ C ;,... ;.; .1.1- - Df""C' h",.,.;,.....,. 1,....,...,... ....
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I I Reference Title I Facility Reference Number J'Reference Section ! , Page No. I Revision:
I Salem ECG Fission Product Barrier Table II EP-SA-111-121 I 11 110 I I II I 11 II I I II I ii 11 I IL.a. Number Objectives I EL0_11.b
iMatefialRequifec(for'Ex.aminatio~.)J ISRO 81 Salem ECG iOt1estlOn~9llrce:'*j IFacility Exam Bank I !9uestionMo.~if!.ctit\6n'Meth~d:\; :j Direct From Source iOuest!on s6llr~~goin111entsi 1136652
!~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
I
!Comment.**
I I
I
RO Skyscraper I SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List I Outline Changes I 1 ~u!_stion l"o?i£J 1sRo s2 Given the following conditions:
- Unit 2 is responding to a LOCA coincident with a LOOP, and has transitioned from EOP-LOCA-1, Loss of Reactor Coolant, to EOP-LOCA-2, Post LOCA Cooldown and Depressurization.
- RCS cooldown has been initiated.
- The RCS has been depressurized as required with a PZR PORV.
- All RCS Thots are 450°F.
- When performing Step 19 RCP Status, the RO reports that RCS subcooling is NOT >0°F.
Which of the followinq identifies how the CRS should proceed?
I
~ Initiate SI to restore RCS subcooling and return to LOCA-1, step 1.
riJ.11 Start ECCS pumps as necessary to restore PZR level and return to LOCA-1, step 1.
I
~ Initiate SI to restore PZR level, and ensure BIT isolation valves open if previously shut.
id.] IStart ECCS pumps as necessary to restore RCS subcooling, and open BIT isolation valves if previously shut.
~,\ns..;,er] Id I IExam L_evei Is I l~_ognitive Le~~i] IApplication I rfacility:J ISalem 1 & 2 I IExam Date: i I 12/19/20161 I
KA: OOWE03A201 I EA2.1 __ ]:ROV~i11e:ll 3.4j s~~~ 1 Section~]j~~-~iOUP:lj 2l~~OGroup:]~ ~
iS"Ystem/E\(olution~ ILOCA Coo Id own and Depressurization
!KA5tate~E!iii:1 appl to LOCA Cooldown and Depressurization:
- Explanation ot ! 55.43.(b) This question is SRO level based on having to assess conditions, then select a section of procedure, in this case going
'Answers_:_~ from Step 19.1 RNO to Step 34, bypassing charging and SI pump reduction steps based on inadequate RCS subcooling. The distracters stating to restore PZR level are incorrect because the stem states that RCS depressurization has been performed, which is only stopped when PZR level is adequate (>25%). The initiate SI distracters are incorrect because only specific required ECCS that the next steps would include isolating the ECCS accumulators, which are not part of the choices and could lead to question.
Reference Title ~ __ Facility Referll_nce Number _J _R_e_fe_re_nce~ectio!l! [!'ag~_N_o_.
1 Revision I Post LOCA Cooldown and Depressurization 112-EOP-LOCA-2 I I F='---""'
__J ~I===~===
- ~----------------~ --------------'*~-------~!-~~~ *---~
1,--- ------
l~.o. Number Objectives I LOCA02E001 1--~
!Oues!i~~Source: 11 New Irouestion Mo_~ification Me!~~~: l, ___________,I [gsed _D_uring Training ~_r()grcir.nJ D
'ouestio~-source Comm~~~~] I I
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- i I I I I I I
RO Skyscraper I SRO Skyscraper J RO System/Evolution List J SRO System/Evolution List I Outline Changes I puestio~ Topic l !SRO 83 Given the following conditions:
- Unit 2 was operating at 15% power prior to synchronizing the Main Generator.
- A Main Steam line rupture occurred that resulted in multiple Steam Generators depressurizing in containment before 2 steam generators could be isolated from the 2 faulted SGs.
- The 2 faulted SGs Tcolds are reading 270°F and lowering.
- The intact 2 SG Tcolds are 330°F and stable.
- RCS pressure is 500 psig and slowly lowering.
- Containment pressure is 16 psig and slowly lowering.
- All SG NR levels are <9%.
- Total AFW flow is 24E4 lbm/hr.
- Source Range Nls are NOT energized.
- Intermediate Range SUR is 0.0 DPM.
With CFST's in effect, which of the following identifies the procedure entrv required, and actions which will be performed in that procedure?
,lal !2-EOP-FRTS-1, Response to Imminent Pressurized Thermal Shock Conditions. Maintain AFW flow >22E4 lbm/hr until at least ONE intact
- SG NR level is >15%, stop all ECCS pumps except 21 or 22 charging pump.
I
'b. i 2-EOP-FRTS-1, Response to Imminent Pressurized Thermal Shock Conditions Isolate any faulted SGs, depressurize RCS with ONE PORV
~I to within 100°/hr Cooldown Curve.
'C:' 12-EOP-FRSM-2, Response to Loss of Core Shutdown. Energize Source Range channels and verify SR SUR is 0 or negative.
~ 12-EOP-FRSM-2, Response to Loss of Core Shutdown. Establish AFW flow >44E4 lbm/hr, borate RCS until IR SUR is negative.
I
- Answer I~ 1Exam Level IS J I 1Cogmtive Level ! j Application i .. l Salem 1 & 2 I ;Facility.: I ,ExamDate. 'i 1_ _ _1_21_1_91_2_0_16_.1I
~I OOWE08G406 I 2.4.6 ..RO Value:* [DJ jSRO Value(ID jsection: \I~' RO Group:ILJ SRO Group:: LJ 1
~f4,~; ~
'System/Evolution Title i I Pressurized Thermal Shock l '_E08 __J
[KA Statement*
Knowledge of EOP mitigation strategies.
ii
!Explanation of 55.43(5) A is correct because the stem conditions result in a PURPLE path on FRTS. Actions for maintaining AFW flow (Step 3.5)
'Answers: ' and ECCS pump reduction (Step 12) are correct.Bis incorrect because depressurizing the RCS to restore conditions within the 100°F/hr curve is performed in FRTS-2 in response to a Yellow Priority Condition. FRTS-1 is entered from either RED or PURPLE conditions, and with SG NR levels <9% (which means you're less than 15% adverse) you are directed to maintain AFW flow> 22E4 lbrn lbt llllitb tbe SR t:>lls oot eoemized IR SI IR is rnai 1ired to be r:noce oeoa!hie !bao -0 2 dm:n oc a :X:EI I Ollll oatb e:.:ists fuc ED"'"-
lI
- 12. The FRTS is a higher priority, and i~ a PURPLE p~th. C is incorrect b;cause it is the wrong procedure with. the correct actions of that procedure. D is incorrect because it is the wronq procedure, and the actions are performed in FRSM-1.
L...
Reference Title __J. . Facility Reference Number j '.Reference Section 11 Page No. ! ',Revision; ICritical Safety Function Status Trees !j 2-EOP-CFST-1 I ii 11 I IResponse to Imminent Pressurized Thermal Sh 112-EOP-FRTS-1 I I! 11 !
IResponse to Loss of Core Shutdown !12-EOP-FRSM-2 I 11 11 I LO. Number I FRTSOOE002 Objectives
Material Required fo~ Examination , l I 1j
- QUestion So~rce
- I J Facility Exam Bank I \Que,,stlon iyt()difi,c:;<!tion ~~tho5f:'.' IDirect From Source 1iusEicl Durihg 'rr~inillg program i O
.::======.'.:================:::============-================-=1 louestionSource':comm~nts: '--------------------------------------------'!
Comment I
I I I I
RO SkyScraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes IQuestioll Top~ ISRO 84 I Given the following conditions:
- Unit 2 experienced a LOCA from 100% power.
- At step 16 of LOCA-1, Loss of Reactor Coolant, a transition to LOCA-5, Loss of Emergency Recirculation, was made with both RHR pumps stopped and unable to be started.
- Just prior to initiating a cooldown, the RWST LO level alarm is received.
- CONT SUMP CH A/B LEVEL >62% lights are lit.
- RCS subcooling is <0°F.
Which of the followini:i describes how the CRS is required to proceed?
1a.l Remain in LOCA-5 and initiate makeup to the VCT at maximum rate.
I b." Remain in LOCA-5 and initiate a RCS cooldown at less than Tech Spec limit.
I I.~' - , to LOCA-3, Transfer to Cold Leg Recirculation, perform valve realignment steps, return to procedure in effect.
I
- d. Transition to LOCA-3, Transfer to Cold Leg Recirculation, align cont sump to RHR suction, then remain in LOCA-3 until direction is provided by the TSC.
I
~swerj Ib I ~xam 1:-evel Is I Lcognitive Level] IApplication 1
I !Facility: 1 ISalem 1 & 2 I !ExamDate: 1 I 12/19/20161
- o-,,.
KA~ 1 00WE11A202 1CE~ _ _1~~~1:TI"~~~L~~ti@1~~~~~o~~G~-:io ~!:~~Ji~
... I ":>"ci'
~YstemiEvolution-Title: ILoss of Emergency Coolant Recirculation I .E11 - I KA Statement: i Abilit to determine and inter ret the followin as the appl to Loss of Erner enc Coolant Recirculation:
Adherence to appropriate procedures and operation within the limitations in the facilit 's license and amendments.
55.43.(b)5 The stem says the transition to LOCA-5 was at LOCA-1 step 16 so RWST level >15.2'. There is no LOCA-3 CAS in LOCA-5. The cooldown in LOCA-5 is done at <100°F/hr, which is the TS RCS cooldown limit to prevent an unwanted Thermal Shock condition, which would complicate matters since CFSTs are still in effect in LOCA-5. Restoring any Train of recirc is the concern with no RHR pumps, the transfer to CL recirc will occur only after a RHR pump has been restored. Makeup to the RWST is
~~~-~
ILOCA05E001
'--~
Material Required for_ Examination_J I II lou~stio~_Sour~=-J IFacility Exam Bank I ouestion Modification Meth~_<i_:___JEditorially Modified I!used During Training Program I D I
1 ~- ----- *~-
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.Question Source Comments L_ ---*-------- --------------~
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I I
I
RO SkyScraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes puestion-Topic-,
ISRO 85 Given the following conditions:
- Unit 2 has experienced a MSLB at the Mixing Bottle.
- All attempts at MSLI have failed, and 21-24MS167s remain open.
- Operators have just completed SI termination steps in EOP-LOSC-2, Multiple Steam Generator Depressurization, and PZR level is being maintained stable.
- AFW flow to each SG is 1.0E4 lbm/hr.
- The RO reports rising pressure in 22 SG.
Which of the followinq describes how the CRS should proceed, and whv?
I
~ Transition to EOP-LOSC-1, Loss of Secondary Coolant, since one SG is now available for subsequent recovery actions.
I ib.J Transition to EOP-LOSC-1 Loss of Secondary Coolant and stop RCPs if RCS pressure is <1350 psig, since RCPs cannot be stopped i11
- LOSC-2.
re: IRemain in EOP-LOSC-2 since returning to EOP-LOSC-1, Loss of Secondary Coolant will require a transition to EOP-LOCA-1, Loss of
- Reactor Coolant, upon completion.
lci.-1 l~n in EOP-LOSC-2 until positive control can be established over the cooldown after the remaining Steam Generators have fully
- * ** n transition to EOP-LOSC-1, Loss of Secondary Coolant. I
!Answer 11 a I ~xam Level. Is I Icognitive Le_vei 11 Memory I j~acility: 11 Salem 1 & 2 I [E~-amDate: 11 12/19/20161
.. .. , t"'~'~'
'~_\'a~§ ~!~e~[se~I~ ~G~LJjsRO Group~o .55.43. ~
- ~ *--~
1 lKA: 1OOWE12A201 I[EA2.1 **""' .til
[Syste~~E:VoiUtion:ritle j Uncontrolled Depressurization of all Steam Generators I ~12~~
~ Statell!E!ll!J ffiility to determine and interpret the followinq as they apply to Uncontrolled Depressurization of all Steam Generators:
cility conditions and selection of appropriate procedures during abnormal and emergency operations.
- Explanation<>f] 55.43(5) LOSC-2 CAS states that upon a pressure rise in any SG except when performing SI termination in Steps 8-20, GO TO
~'!~!'.'fir~_:---*' EOP- LOSC-1. The stem states that it is after Step 20. LOSC-1 Basis Document, page 7, states that.."Any cooldown operations that are performed as subsequent recovery actions will require at least one nonfaulted SG."
Reference-Ti!Ie - - - - ~= -.=~cility Refe~~nce Number J'Reference Se_~iiorl! ~age No. , -Revision!
IMultiple Steam Generator Depressurization 112-EOP-LOSC-2 I 11 1130 I ILoss of Secondary Coolant 112-EOP-LOSC-1 I II 1130 I
! II I 11 II I rt.-.o-.N-u-ffiber Objecti I LOSC02E005 1_ ____,
~te_rial Require_d for Examinat~ I q IQUesti~n Source: ~ IFacility Exam Bank !'Question Modification Method: IDirect From Source I~sed During Training Progrc1m I D I
'-"" ---**-- -----~
~~esti~n sour~~ ~omments' I
re<>;..... ~ ...
~-** "--~, ~--- --"~
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RO SkyScraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
-f 1auestion opic- 1 ISRO 86 I Given the following conditions:
- Unit 2 is operating at 100% power.
- Chemistry reports at 1000 on March 10th that a routine sam pie of the RCS indicates that DEl-131 is 8 uCi/gm.
- A second sample confirms the elevated reading.
If DEl-131 remains at this level, which of the following identifies the Tech Spec required time that the below listed action must be performed, and the bases for performing that action?
Be in at least Mode 3 with Tavci <500°F bv .....
La'." 1600 on March 10th. This prevents the release of activity should a steam generator tube rupture occur since the saturation pressure of the primary coolant is below the lift pressure of the atmospheric release. I
~ 1600 on March 12th. This prevents the release of activity should a steam generator tube rupture occur since the saturation pressure of the primary coolant is below the lift pressure of the atmospheric release. I 1c.I 1600 on March 10th. This ensures the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> dose at the Protected Area Boundary will not exceed an appropriately small fraction of r-Part 100 limits following a steam generator tube rupture accident in conjunction with an assumed primary-to-secondary steam generator leakage rate of 1 gpm. I id .. 1600 on March 12th. This ensures the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> dose at the Protected Area Boundary will not exceed an appropriately small fraction of c ..J Part 100 limits following a steam generator tube rupture accident in conjunction with an assumed primary-to-secondary steam generator leakaqe rate of 1 cipm.
~swer 1[E_j !xam ~evel 1 I~ Eognlti"-e Level 1 IMe~ory I [a"cllity: j ISalem 1 & 2 I iExam-Date:! I 12/19/20161
~loo2000G225 IL@--=-l~~~@~~~~~n::Jl~i~r~:1LJ~~u.£::LJ ~~~ ~
lSystem/E~o!'1tlon Titl!J IReactor Coolant System 002 nowled e of the bases in Technical S ecifications for limitin conditions for o erations and safet limits.
Explanation of 55.43.(b)2 LCO 3.4.9 states that with activity greater than 1.0 uCi/gram DEl-131 but below the line of graph 3.4-1, then operation jAns~ers:_. can continue for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, then HSB with tavg <500°F in six hours. The bases for the limitation of specific activity is contained in the correct answer and distracter a. The other 2 distracters contain the bases for the LIMIT on RCS activity, but with the wrong area with regards to where the dose is limited. Protected area Boundary is wrong, Site Area Boundary is correct.
Reference Title Reference Number ~~on~
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[L_.O_. N_u_m_~e_r-**--: Objectives I RCSOOOE009 j_ ____,
,Material Required for Examinatio'!.._J ISRO 86 Salem Tech Specs Figure 3.4-1 DEi vs Rated Thermal Power II LCluest~onS~urc~ j Facility Exam Bank I [Question Modification Method:_j Concept Used I!uSed During Training Program I D I
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- QuestionSom~e Cornme~t~ Combination of 86338 (limit) and 58158 (bases)
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Comment _ .*~
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RO Skyscraper I SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List I Outline Changes I L~uestion Top~ ISRO 87 I Given the following conditions:
- Unit 2 was operating at 100% power when a SBLOCA occurs.
- Operators transitioned from 2-EOP-LOCA-1, Loss of Reactor Coolant, to 2-EOP-LOCA-2, Post LOCA Cooldown and Depressurization with RCS pressure of 1050 psig.
- When performing RCS Depressurization to Minimize Subcooling with a single PORV, RCS subcooling is lost when the PZR PORV fails to shut and is isolated by closing its Block Valve.
- Charging flow through the BIT is in service due to no RCS subcooling.
Which of the following conditions, if any, describes the action the CRS will direct after the depressurization with regards to ECCS Accumulator isolation?
~I Accumulators will be isolated if RCS Thats are <375°F.
I
!b-.j IAccumulators will be isolated if RCS pressure is <1,000 psig.
I
~11 Accumulators will be isolated if PZR level is> 11% (19% adverse).
I I
d.
Accumulators will NOT be isolated since SI has not been terminated.
I I ~nitive Level j IMemory I [Ficil_i!~:J ISalem 1 & 2 I ~ate:l l___12_1_19_;2_0_1___.6I
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[Exam Level: IS
~I 005000A212 1:~-:-~ ~q~@!sRoValue~~:~I~ ~q~LJ[SRo Groul>:LJ ~
- sYSie~/Ey_oltJ!i?n-Title~ I Emergency Core Cooling System 006 J
[~statemen~: Ability to (a) predict the impacts of the following on the Emergency Core Cooling System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
Conditions requiring actuation of ECCS
-Explanation of - 55.43(b)5. SRO level because question requires knowledge of a section of procedure, LOCA-2, where ECCS Accumulators will be Answers: isolated when RCS Thats <375 (Step 35.3.) With no subcooling, RCS Thats must be below 375° for Accumulators to be isolated,
- - - - - ----~ otherwise the step to do it is bypassed. Accumulators WILL be isolated <1,000 psig, BUT ONLY after IOP-6 has been entered, the initiation of which is performed later in LOCA-2 (Step 42)
Reference Title --1, __ Facility Ref:rence Nu~ber l~r:ll~e_Section ---,j_i:i_~ ~v~
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ECCSOOE009 Objectives I ECCSOOE013
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RO Skyscraper I SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List I Outline Changes I jOuestion TopiCJ ISRO 88 Given the following conditions:
- Fuel handling is in progress in the Unit 2 Spent Fuel Pool when a fuel assembly in the Spent Fuel Handling Tool is dropped.
- Gas bubbles are observed in the vicinity of the dropped fuel assembly.
- 2R5, Fuel Handling Building (FHB) radiation monitor goes into alarm and stabilizes at 25 mR/hr.
Which of the following describes the effect of this event, and contains actions that will be performed IAW S2.0P-AB.FUEL-0001, Fuel Handling Incident?
~-* , ~L* Fuel ~andling Crane motion is locked out to prevent further damage to an affected fuel assembly. Ensure all available FHB Exhaust fans e in service. I
~* 1ALL Fuel Handling Crane motion EXCEPT downward movement is locked out to prevent raising a damaged fuel assembly. Ensure the FHB
____ J Truck Bay Roll Up Door is closed. I
~J I.The FHB Evacuation alarm actuates to alert all personnel of the FHB high radiation condition. Evacuate ALL personnel from the FHB until Radiation Protection has performed area surveys. I I
Id.: FHB ventilation automatically swaps to place the Charcoal Filter in service to prevent a release to the environment. Ensure the FHB
- Watertight Door remains closed except for normal personnel passage. I iA.nslf,/e? Id I !Exam ~evel 1 Is I "cognitive level I i Memory I [Facility:l ISalem 1 & 2 I [E~a_rnoate: I 12/19/20161
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lsystef1l}Evolut~ IFuel Handling Equipment System I 634==._J
[t<A ~tatement:' Ability to (a) predict the impacts of the following on the Fuel Handling Equipment System and (b} based on those predictions, use procedures to correct, control, or miti ate the consequences of those abnormal operation:
Dro ped fuel element Explanation of 55.43(7) The 2R5 in alarm (11 mR/hr alarm, 7mR/hr warning) swaps the FHB exhaust ventilation to the Charcoal Filter and starts j~swers: both FHB Exhaust Fans. The normal configuration for FHB ventilation is the single Supply Fan running, and BOTH Exhaust Fans running. C is incorrect because non-essential personnel are evacuated, as actions are required to be performed prior to evacuating ALL personnel. The alarm will actuate. A and B are incorrect because the FH crane only locks out as described in B with the i - -- - - * -Reference Title- --- -~ - - * - . ' - - *****~~' -Revi~on:
_J Facility Reference Number j 1Referen_c:e Section _ Page No._
IFuel Handling Incident 11 S2.0P-AB.FUEL-0001 I 11 i 1s I IRadiation Monitoring System Lesson Plan II NOS05RMAS000-14 I 11 1117 I I II I 11 11 I Objectives I ABFUEL01 E002 Material Required for Examination
-* - - I II
~~e~tion Sour~~~ IFacility Exam Bank I[Question- M°._~ification Ml!_tho£ *JI Direct From Source I[!ls~_d During Trai~il")s:J~rogra~ D Question Source Comments I 59673 I
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~uestion Topic I SRO 89 Given the following conditions:
- Unit 2 is operating at 84% power.
- All Condensate pumps are in service.
- NO Heater Drain pumps are in service.
- The Condensate Polisher is in service.
- Power is reduced based on the Condensate I Heater Drain pump configuration Subsequently, 21 Condensate pump trips.
Which of the followinq describes the effect on the Condensate svstem of the pump trip, and how should the CRS respond?
I
~ The 21-23CCN108s Polisher Bypass valves automatically open when SGFP suction pressure lowers <320 psig. Reduce reactor power to 65%
or less.
~I The 2CN47 23/24/25 Heater Strings Bypass Valve automatically open upon the Condensate pump trip. Reduce reactor power to 30% or less.
I
[c] 21A Condenser level will rise. Open Polisher Bypass valves and reduce reactor power to 65% or less.
I I
,_dl 21A Condenser level will lower. Open Heater Strings Bypass valve and reduce reactor power to 30% or less.
I
- Answ~rJ Ic I E~am Level~ Is I cognitive Lev~ IApplication I I ~acitity: J ISalem 1 & 2 I 'Examoate: ! I 12/19/20161
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~tern/Evolution Tiitel 1....:....:..-~_;;_,:_.;.;...___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _----1 [056 --_J
~-~---------------___J l<A Stat~ment: _ Ability to (a) predict the impacts of the following on the Condensate System and (b) based on those predictions, use procedures to correct, control, or mitiqate the consequences of those abnormal operation:
Loss of condensate pumps Explanation of 1' 55.43(b)5. This question is SRO based on having to determine the section of AB.CN which will be performed, and the sub-section of 1
!Answers:
c__:_:_::__:_ ----
,1 Attachment 2 knowing that with 2 Cond pumps running with no HOP running power reduction to 65% or less is required. The CN108s do NOT auto open on low suction pressure, but are directed to be opened when SGFP suction pressure lowers <320 psig, which it WILL, based on initial power level and initial pump configuration. The CN47 only auto opens on a SGFP trip, not a Cond
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expected to restore suction pressure above the point which would require CN47 opening. Hotwell level will RISE with the cond l pump 0/S, as condensinq is still occurrinq, with the pump not runninq.
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j Main Feedwater I Condensate System Abnorma 1 S2.0P-AB.CN-0001 I J 1 I 1128 I I 11 I lj JI i I II I 11 II I r;-~---
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Number Objectives
~----------------
ABCN01 E003 I I CN&FDWE008 I Material Required for Examination
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~u~~tion So~rce: 1 INew Ifau:_stion Mo~ificatio~Method: I I IUs~d During TrCiining Program I D foueslion source comments~
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!Question Topic 11 SRO 90 Given the following conditions:
- Unit 2 is operating at 7% power during a normal power ascension.
- A total loss of Control Air occurs on Unit 2 causing control air header to rapidly lower.
- The CRS enters S2.0P-AB.CA-0001, Loss of Control Air, and operators manually trip the reactor.
Prior to any operator action being performed other than TRIP-1 immediate actions, how is feed flow to the SGs affected by the loss of control air, and how is the CRS required to respond?
~ MDAFW pumps previously in service will cease to supply feed to the SGs as the 21-2AF21's fail closed. Dispatch operators to locally L::.:J manually open 21-24AF21s to establish 22E4 lbm/hr total AFW flow.
~ MDAFW pumps previously in service continue to supply all SGs, but now at runout flow with 21-24AF21 s failed open. Dispatch operators to locally manually throttle 21-24AF21 s to prevent MDAFW pump failure. I (2 The feed flow being supplied to SGs from the SGFP in service was lost when the Feedwater Interlock actuated with the reactor tripped and Tavg low setpoint reached. Direct the PO to start 23 AFW pump since Pressure Override circuit will prevent using 21 or 22 AFW pumps as feed supply.
,d.'
___J The feed flow being supplied to SGs from the SGFP in service was lost when the Feedwater Interlock actuated with the reactor tripped and Tavg low setpoint reached. Direct a Field Operator to establish manual control of 23 AFW pump which started when 2MS132 opened to prevent 23 AFW pump runout and SG overfill.
I IAnswer- r dmm m 'Exam Level I rs mmm! !cognitive Level l.i\ppli~tio~ I Facility: i [Salem 1 & 2 1 I !ExamDate: : I 12/19/2016 b~!061000A207 I A2.07 IROValue:\~ 1 SROValuej~'section:*j~IROGroup:jLJlsROGroup:iLJ ~~I3 ~
r$ystem/Evolution Title i IAuxiliary I Emergency Feedwater System I )!J~-
KA StatEiment: I Ability to (a) predict the impacts of the following on the Auxiliary I Emergency Feedwater System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
Air or MOV failure II iExplanation of 55.43(b)5 This question is SRO level based on the requirement to know what section of a procedure to use in AB.CA. At 7% power,
!Answers:__JI Main Feed will already have been established and AFW secured. The rapid loss of CA, and the trip in AB.CA (which would have been directed when the BF19s/40s failed SHUT on loss of CA indicate that feed flow from the operating SGFP was lost. The l
2 0 0 1 1 I I~~; 1~ d%~~~~ ~~v:o~~:!~~~a 1~~~~!~~a ~1~~ ~~~ed~~a~:~~tt~b!t~~~~Fg~iau: ~b:~~~e~~~ ~si~~~i~!t~~l~~c~e~~ ~~~~~~iag I MDAFW pump initial flow are incorrect but plausible if the operator doesn't not know at what power the IOP directs swapping AFW to Main Feed. Choice a has wrong failure mode, but correct action if that were the correct failure mode. Choice b has correct failure mode and action. Choice c has correct status of feed flow, but wrong action i Reference Title I Facility Reference Number j !Reference Section i J Page No. : !Revision!
I Loss of Control Air IIS2.0P-AB.CA-0001 I II 1121 I j Auxiliary Feedwater System Lesson Plan II NOS05AFW000-15 I 11 1115 I I ll I ii II l
- LO. Number AFWOOOE006 Objectives I I ABCA01 E002
'Material Required for EJCar:nination . II Question S~urce: 11 New j ,Question Modificatiop Method: . *I I [used During Training Program I D louestion Source Cqmments' I j
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Comment '*I I I I I I I
RO Skyscraper I SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List I Outline Changes I lc2ue~ti_<:>ll!opic 11 sRo 91 I Given the following conditions:
- Unit 2 is operating at 100% power.
- 2B EOG is CIT for scheduled maintenance, with a scheduled return to service in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- It is discovered that 2A EOG monthly surveillance was not performed within its 31 day required periodicity.
- The required 2A EOG surveillance was last performed 33 days ago.
Which of the followinq identifies the status of 2A EOG IAW Tech Soecs, and whv?
~I INOPERABLE because it has exceeded its 31 day surveillance requirement.
~I INOPERABLE since the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> delay time past the 31 day requirement has been exceeded.
I
~ OPERABLE because the normal surveillance interval plus 25% extension has not been exceeded.
I I
d.-~ OPERABLE because the surveillance can be performed within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> delay time which starts upon discovery of the missed surveillance. I cAnswer-1 j c I 1Exam LeveT! Is I Cognitive Level , I Application I FacilitY~l I Salem 1 & 2 I ,ExamDate: 11 12119120161
~:I I064000G240 1 2.2.40 J[ifo Value:' I 3.41 l~~~ ValueJ~ lsectio11:J I~ [RO-Group: I 1I[SRO~ LJ ~ D
~~~!E!rn/Evolution Title] IEmergency Diesel Generators I !o64 IKAstat~l:fi~~tJ....-~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~---:-
Abilit to a I Technical Specifications for as stem.
i--- ---------,
1Explanation of 55.43(2) Tech Spec 4.0.2 states ... "Each Surveillance Requirement shall be performed within the specified surveillance interval with
- Answers: a maximum allowable extension not to exceed 25 percent of the specified surveillance interval." Since the 25% of 31 days has not been exceeded, the EOG remains OPERABLE, since its surveillance is not required to be performed until 31+7.75 days. A is incorrect because of the 25% time. B is incorrect because the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> delay time is from time of discovery. D is incorrect because
~===================~==============~~========:::::: 1~==-
[Lo. Number Objectives ITECHSPE011 PE014 Material Required for Examination I I II Question Source:
-*; IFacility Exam Bank I!Question Modification Method: II Direct From Source I,Used During Training Program ] D Questi~l"l_~ource*c~~mentsi I I
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RO SkyScraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List . I Outline Changes iOuestion Topic 11 SRO 92 I Given the following conditions:
- Unit 2 is at 40% power performing a shutdown.
- 4 SW Bay is isolated due to a leak on the 25SW3, 25 SW Pump Discharge Isolation Valve.
- Operators are performing the shutdown to comply with TSAS 3. 7.4 because difficulties arose during the leak repair of the 25SW3.
- 2A EDG is supplying 2A 4KV vital bus for a scheduled surveillance.
- 22 Charging pump is in service.
- 23 Charging pump is available.
- 21 and 23 SW pumps are in service.
- 22 SW pump is in auto and standby.
- 23 SW pump trips, and one minute later 2A EDG output breaker opens on 2A 4KV Vital Bus Differential Which of the following identifies:
- 1) The effect this will have on the SW system
- 2) How the CRS is required to respond
- al
~
- 2) Enter S2.0P-AB.SW-0001, Loss of Service Water Header Pressure. Reduce loads on Service Water listed on Attachment 2, Loads Affected bv a Loss of Service Water.
b.l
- 1) All SW flow capability is lost.
- 2) Enter S2.0P-AB.SW-0005, Loss of All Service Water. Trip the Rx, confirm the trip, and stop RCPs to limit the heat input to the CCW svstem.
c.I SW flow capability is lost.
er S2.0P-AB.SW-0005. Trip the Main Turbine and reduce Rx power <5% to lower heat input to the RCS.
e:.J 1) 22 SW pump will auto start on low SW header pressure.
- 2) Enter S2.0P-AB.SW-0001. Place 23 Charging pump in service and remove 22 Charging pump from service.
~~ ~ 'Exam Level I ~ !Cognitive Level I IApplication I J'acilliY:l lSalem 1 & 2 1 IExamDate: j j___ 12_11_9_12_0_1~6I jKA:jjo76000A201 liA2.01 __JiROValue:jl3.5*jSROValuej~ Section:j~s I ROGroup:/j 1jlSROGroup:I 11 f5i43; ~
'system/Evolution Title i _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~I 1076 __I j_s_e_rv_ic_e_W_a_te_r_S_y_s_te_m KA Statement: 1 Ability to (a) predict the impacts of the following on the Service Water System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
Loss of SWS I Explanation of [ 55.43(b)5 21-26 SW pumps are powered from AA, BB, CC vital buses. With all 4 SW Bay isolated, 24,25,26 SW pumps are Answers: . unavailable. A Bus Differential signal will open the EDG output breaker, and ALSO prevent the vital bus infeed breakers from Station Power to close. This will result in no SW pumps running. AB.SW-5 states to perform actions listed in correct answer. The other AB.SW-5 action is wrong in that tripping the MT when power is <49% will NOT trip the Rx. The 2 distracters regarding 22 SW r'\llr'Y'lr"'\ ..... 11+/"'\ -*-~=-- . ., __ :_______ L..- *-**-- iJ ~JJ - .l. L. ..... ,..,,.,,..--* *-c Red1 icing S)J\/ J-- ,..., .......... H 0 i .... ..., -- ... .1. ...,,....+;,...,..., L--...., ,...,-F 1 ... -
ISW header pressure. The action to swap charging pumps is found in AB SW-5, not AB SW-1
]i I~,--.~
Reference Title 1: Facility Reference Number . ] [Reference Section 1: Page No.J ,Rev1s1on
! Loss of All Service Water 11 S2.0P-AB.SW-0005 II II 114 I I Loss of Service Water Header Pressure _JI S2.0P-AB.SW-0001 II 11 1116 I I ll II 11 11 I
- Lo. Number IABSW04E004 Objectives
Material Required for Examinatiqn * .j I Questior1Source: .*. j l_N_e_w________,I !Qu,e~tior ~od,ificatiori 11J1etha,d: , ~ I !Used Dlirin~!'Trainingprogram I D
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- o"ii-estion Topic 11 SRO 93 Given the following Initial Conditions at 0800:
- Unit 2 is in MODE 5.
- Containment Purge is in service.
At 0830, Containment Purge is stopped to support a maintenance visual inspection of purge ductwork inside containment.
At 1015, a Containment Ventilation Isolation (CVI) signal inadvertently actuates due to a rad monitor switch mis-positioning.
At 1030:
The duct inspection is complete.
Radiation Protection reports containment was not breached in the past 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> except to allow entry and exit of workers through the airlock.
Chemistry reports there is operational assurance that no radiological changes to containment environment have occurred and requests containment purge be restored.
I IAW S2.0P-SO.WG-0006, Containment Puroe to Plant Vent. is a new containment purqe release form required and why?
a.:
- b. I Yes, because of the CVI signal.
I Yes, because the purge was secured.
I I
ic.' No, because the termination was <4 hours and there is operational assurance of unchanged radiological conditions.
L~
[dl I No, because the termination was <12 hours (one shift) and containment has not been breached except as allowed for worker ingress/egress
~ through containment airlocks.
!Answer i ~ Exam Level J ~ !Cognitive Level J IMemory I ,Facility: 11 Salem 1 & 2 I IExam Date: j___1_2_11_9_i2_0_1~6I
~-
~ j 103000G123 'RO Value: l@;SRO Valuej~ 'Section: : I~ iRO Group: LJ 'SRO Group:: LJ .~~!3- ~
System/Evolution Title j i------'------------------------------------' 1_03_-_--_---
KA Statement! .,
IAbility to perform specific system and inte<:irated plant procedures during all modes of plant operation. I
- Explanation of i 55.43(4)Procedure S2.0P-SO.WG-0006 allows for reinstatement of purge if of short duration (-4 hours) and containment rad Answers: conditions have not changed ( P&L 3.3) Short duration is NOT 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and distracter does not address rad conditions. New effluent permit not always required. Can block CVI signal IAW Att 2, Temporary Termination and Reinstatement of Containment I
Purge.
Reference Title 1 I Facility Reference Number ' [Reference Section I
- Page No. I (RWision; IContainment Purge to Plant Vent 11 S2.0P-SO.WG-0006 I 11 1130 I I II I 11 11 I I Ii I 11 11 I LO. Number Objective I WASGASE011
Materlal Required for Examiriadon *.** .II jauesticin,Spurce: i IFacility Exam Bank I!used, ou*ririg Training Program I D
- auesti?I'! sou~c!'. Coirirnents[ I0126340
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RO SkyScraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
~ues!ion fopiCl I sRo 94 Given the following conditions:
- Both units are operating at 100% power.
- Reactor Engineering has determined that a single fuel assembly in the Spent Fuel Pool must be moved to a new storage location.
- A Notification has been submitted.
- The assembly has been in the SFP for 100 months.
- The SM has given permission, and Radiation Protection has been notified of the movement.
Which of the following describes the Operations Department requirements for this evolution IAW S2.0P-10.ZZ-0010, SPENT FUEL POOL MANIPULATIONS?
A qualified Senior Reactor Operator ...
- 1 I
~'..J must directly monitor the fuel movement from the crane trolley.
~:I is NOT required if SFP boron concentration is verified >2000 ppm.
I l~ must be present in the Fuel Handling Building during the fuel movement.
I
~d~ is NOT required to observe the fuel movement if a Qualified Reactor Engineer is present.
!Ans~i @=] :§_m Le~ Is I ~ognitive Lev~ IMemory I rFacili~ ISalem 1 & 2 I [.:xamDate:l j___12_11_9_12_0_16_,I
~~11940018135 1lD~-=-1~~~@~~~~~~,~~~~o~~o ~;s ~
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1Syste~/Evolution Titl!J
'KA Statement-1 Knowledqe of the fuel-handlinq responsibilities of SROs. I
- Explanation of I 55.43(7) S2.0P-10.ZZ-0010, Precautions and Limitations, 2.2 states a Reactor Engineer OR SRO must be assigned for Spent Fuel
~nswe_rs: ----~* Pool manipulations. A is incorrect because even if a SRO was assigned, they are only required to supervise from the area, not specifically on the trolley. B is incorrect because SFP boron concentration is not a pre-requisite to who is required to supervise fuel
==-1 movement. C is incorrect and D is correct because a RE OR SRO is required.
~-=== Reference Title L_ Facility Reference NumbElr -~!Reference Section~ ~age Nol rRevislo~
ISpent Fuel Pool Manipulations 11S2.0P-IO.ZZ-0010 II ii 1133 I I II !I II 11 I I II II 11 11 I
,!-_:Q:__N~b!!:_ __ J Objectiv I REFUELE012
~aterial Requir13d for Examination _J I II j
[9uest!on Source:l Facility Exam Bank Ifauestion Modification Method:* i Direct From Source 1 IUse~ Duri~g l"rainif_lg PrograrnJ D
- auestion-source Comments' L-**-****-**-**-***-****--J I I L--******-*'"
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RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
~~uestionTopicl !SRO 95 Given the following condition:
- Salem Unit 2 is in a refueling outage, with all fuel removed from the reactor vessel.
Which of the following identifies when Mode 6 will be entered during actions to refuel the reactor IAW S2.0P-IO.ZZ-0009, Defueled to Refueling?
Mode 6 is entered when ......
ra.i 1fuel movement is "imminent".
~J I
~~ the first fuel assembly is lowered in the reactor vessel.
1C:. l the first fuel assembly is moved over the reactor vessel.
I
~ all Administrative Requirements are satisfied and the SM signs Attachment 1 authorizing Mode 6 entry.
[Answeil b I I Exam LevelJ Is I cognitive Levell IMemory I IFacility~l ISalem 1 & 2 I ~amDa1=J I 12/19/20161 1 ~1194001G136 1
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~ystemiEvolution_Title= /GENER~
~Statement~.--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~---,
Knowled e of procedures and limitations involved in core alterations.
55.43.b(6) IOP-9 specifically states (Step 5.1.6), that when the first fuel assembly is lowered into the reactor vessel, Mode 6 is entered. A is incorrect but plausible if it is thought that you enter Mode 6 just prior to moving fuel. The use of the word "imminent" is found in IOP-3 when performing a reactor startup, when withdrawal of Control Bank A is "imminent", the crew is directed to enter MODE 2, Reactor Startup. C is incorrect but plausible if it is thought that the action of moving fuel over the vessel is when Mode 6 Ientered.
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'Revision
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~~~~-=- Objectives
! IOP009E004
.Ma~erial Required for Examination JI II 1
I QuestionSourc.=_J Facility Exam Bank IJc:iuestion Modification Method:. i Editorially Modified i lused During Training Program I D
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'ciUestion Sou~C:e CommerltS! 1118980 replaced 2 distracters with 2 new distracters, correct answer remains the same.
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ISRO 96 I Given the following conditions:
- Unit 2 is operating at 100% power, BOL.
- 2A EOG is inoperable for maintenance and won't be available for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- The current time is 1200.
- Which of the following would require the Unit to be in Hot Standby by 1900?
~ 128 EOG is declared inoperable due to an oil leak and Maintenance reports 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> later that it will be at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to repair.
I I
~ A slow nitrogen leak causes 21 ECCS Accumulator pressure to lower to 595 psig, and initial attempts to raise nitrogen pressure are unsuccessful. I
~'The containment 100' elevation airlock air leakage test is UNSAT IAW S2.0P-ST.CAN-0004, CONTAINMENT AIR LOCK LOCAL LEAK RATE TEST.
fdl I The CRS is informed that a faulty test device was used during the recent refueling outage to test and adjust the lift setpoint of all PZR Code
~ Safety Valves, and that actual lift pressure for ALL 3 valves is 2,735 psig.
~nswer 1 Id I IExam Leveil Is I iCognitive Level 11 Application I IFacilify; .1Salem1
&2 I r1::x,amDatej I 12/19/20161
,ROValue:1[I§J~:section: l~l~()Group:!LJ~~[JJ SM~j ~
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~J 1194001 G222 1_2._2.2_2___
~~~~rn/Evolution TitI~ !~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-'
I GE NERI
'KAstatem~
Knowledge of limiting conditions for operations and safety limits. I
- Explanation of I 55.43(2,5) Only one PZR Code safety can be inop in MODES 1-3, and this is 3.0.3. 2 EDGs inoperable in MODES 1-4 is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to Answers: restore, then 6 to HSB. Accumulator has 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore. Airlock has 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> action time.
Reference Title
- -**-==:J ~ciiiiy Refer~11ce Number I ReferEmce Section-] rf.age No:! l~!!-~jOn ISalem Tech Specs I 1 314 8-1. 8-2. 3/4/4-6, 3/4/5-1, 314 6 I 11 11 I I II l q ii I I II I 11 11 I il.0'. ~I.Imber TECHSPE015
- Material Required for Examination jI II
'Que~tion Source:_] INew I:auestion.Modification Method: ***1 I[liSedDuring Training Progr~m D
-~~=~ti~11_Source Commentsi I I
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@luestiol'l Topi~ IsRo 97 Given the following conditions:
- Salem Unit 2 is in Mode 4.
- All RCS Tcolds are 280°F.
- 21 Charging pump is in service.
- 22 RHR loop is in service in SDC.
While hanging a tagout for 23 Charging pump, the suction valve for 21 charging pump is closed instead of the suction valve for 23 Charging pump.
Which of the followinQ identifies how the CRS is required to respond?
l'!J IRestore at least one ECCS subsystem to operable status or maintain RCS Tavg <350°F.
rt,~ Immediately suspend all operations which may result in a change in RCS boron concentration.
cc:1 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action shall be initiated to place the unit in Cold Shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
fd.1 Restore at least one ECCS subsystem to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in Cold Shutdown within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
Answer; Id I e:X:am Level 1 Is 1 I I
~gnitive..Levei-1 Application I [f~cili~alem 1 & 2
-I ~xam~ate:J I 12/19/20161
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194001G231 1 1 System/Evolution Title
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[!9\sta,tem~nt:l..-~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~__.,.
Abilit to determine operabilit and/or availabilit of safet related e uipment.
~xplanationotl 55.432.b(2) This question meets the KA by having to determine that with RCS Tcolds<312°F, all but 1 charging pump must be Answers: , rendered inoperable, as well as both SI pumps, and that one ECCS loop is required to be operable with that 1 charging pump, and closing the suction valve of that pump makes it inoperable. Distracter a is incorrect because it is the action (for the same LCO 3.5.3) if a required operable RHR pump were to become inoperable. Distracter b is incorrect because only positive reactivity Reference Number
!.========================!.================~!==========~~=====-1~2=58==~
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LO. Number Objectives I ECCSOOE010
'i-----'
,Material Required for Examination .J I II
@iUe~tion Sourc_!:J
~-*-----.
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INew Source Comment~
I~uestio,n Modification Method:
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_j I [1,JsedDurinQ Training Prograr:'1J D I
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RO Skyscraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes Question Topic i ISRO 98 Given the following conditions:
- Unit 1 is shutdown during a refueling outage.
- A normal release of 14 Waste Gas Decay Tank to the plant vent is scheduled to be performed on day shift IAW S1 .OP-SO.WG-0011, Discharge of 14 Gas Decay Tank to Plant Vent.
When reviewing the schedule, which of the following activities is allowed to be scheduled during the period 14 WGDT is being released?
- ] I Release of 11 WGDT.
I
'b. I
~_.] I Transfer of gas between 12 and 13 WGDTs.
I
'd-. ~ Aligning Unit 2 Vent Header to Unit 1 Waste Gas Compressor suction.
triswer Ib I !Exam Level 11 S I [c?g_nitive Level
- 1Memory I ~acllitY:- ISalem 1 & 2 I 'examoate-:
-***-**- ****--* I 12/19/20161 I~=---= ~~y~j~~][J]"~~E'El]~ !section: II~ RO Group: LJ lsRO Group: LJ
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~ 1194001 G311 i~~~" ~
!sy~t~~l§_~~ution 1:§] IGENER_i]
KA Statement* I Ability to control radiation releases.
'Explanation of 55.43(4) A is incorrect because only a single WGDT is allowed to be released at a time (page 3). B is correct because the release Answers:
. ~--*~***--~~~
procedure specifically allows a VCT purge to plant vent to occur during the WGDT release (page 16). C is incorrect because the release procedure specifically disallows transfer of gas between tanks when another tank is being released (page 3). D is incorrect because while waste LIQUID can be transferred from one unit to the other, waste GAS cannot.
Reference Title ,l -~c:t<"'.ility Reference Number 1Reference-secii0r1=1 ~Pag_E!_f-1~*1 Revisie>~ 1 IDischarge of 14 Gas Decay Tank To Plant Vent 11 S1 .OP-SO.WG-0011 I 11 1131 I ITransfer of Waste Gas 11 S1 .OP-SO.WG-0007 I 11 116 I I II I 11 11 I Number WASGASE011
!Nla_ter!al Required for Examination ,I II Question Source: 11 Facility Exam Bank I !ciuestion Modification Method: !I Direct From Source j 'uS~_[)l!ring Training Progra~ D Question Source Comments! I
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I Comment I
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RO SkyScraper I SRO Skyscraper I RO System/Evolution List I SRO System/Evolution List I Outline Changes f
@uestion ToPIC'1 SRO 99 I I Unit 2 is responding to a degraded core cooling condition in accordance with 2-EOP-FRCC-2, "Response to Degraded Core Cooling." After depressurizing to inject the accumulators, the STA reports a RED priority on the Thermal Shock Status Tree, and recommends transitioning to 2-EOP-FRTS-1, "Response to Imminent Pressurized Thermal Shock."
Which actions describe the operator response?
j
~~I Do not implement 2-EOP-FRTS-1 until 2-EOP-FRCC-2 is completed because thermal shock is a lower priority CFST.
I lt.>J I Implement 2-EOP-FRTS-1 immediately because the potential damage done to the RPV by delaying entry into FRTS after entry conditions are met may be irreparable.
I I
~ Do not implement 2-EOP-FRTS-1 until 2-EOP-FRCC-2 is completed because while in FRTS the core will continue to boil away injected accumulator water, and could lead to a RED path for CC. I
[d.J I Implement 2-EOP-FRTS-1 immediately because it is a higher priority CFST and rules of usage stipulate the transition to a higher priority
-- procedure always takes precedence over notes and cautions. I
~ns.;.;en Ic I Exam Le~ Is 1
I 'Co9niti~e LeveU IMemory I rFacllity: 1 ISalem 1 & 2 I ~xamDate: 1 I 12/19/20161
- KA---
- 11194001G404 1
system/Evolution Title j GE NERI
__J IKA
'- * -Statement*
--*--- .I Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operatina procedures. I fElc-planation ofl 55.43.b(5) Stopping the depressurization to go to FRTS would cause the cooldown to be stopped, and a thermal soak to be Answers:
~- * - ___ .. _J
' performed. The core will continue to boil away injected accumulator water, and could lead to a RED path for CC. Step 15 Continuous action Step.
!-~~=--Reference Title * ==-""] [_ Faci_lity Reference NIJmbE!r *--: ~erence Se_ction _J [Page No] ~ision~
IResponse to Degraded Core Cooling Basis Doc j j 2-EOP-FRCC-2 I 1123 11 2 I I II l II Ii I I II 11 11 11 I 11------.
~'.()~u~__ __J Objectives I FRCCOOE006 I I
1_ ____.
Material Required for Examination.
. - I I II L?uestion Sourc~~J IFacility Exam Bank I!Question Modification Method: ] Direct From Source L__________* - . - - . - - . - -..*
1lused During Training ..___________
Program j D
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Question Source Comments
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RO SkyScraper SRO Skyscraper RO System/Evolution List SRO System/Evolution List Outline Changes
-O~estion Topic I ISRO 100 Given the following conditions:
- Unit 2 is in MODE 3, performing a normal cooldown/depressurization going to Cold Shutdown IAW S2.0P-IO.ZZ-0006, Hot Standby to Cold Shutdown.
- RCS pressure is 870 psig.
- RCS Tes are 3g5 deg.
- PZR level is being maintained stable by adjusting charging flow during the cooldown.
- Charging flow is 79 gpm.
- The 45 gpm orifice is in service.
A step change of 10 gpm has just been performed on charging flow (from initial value of 79 gpm) to maintain PZR level stable, and is determined NOT to be associated with the cooldown in progress.
Which of the followinq describes an acceptable procedure proqression, and the outcome of usinq the procedure(s)?
I a.* Enter S2.0P-AB.LOCA-0001, Shutdown LOCA. Isolate letdown, adjust charging flow, go to Section 4.0.
- b. IEnter S2.0P-AB.RC-0001, Reactor Coolant System Leak, perform an RCS inventory balance, attempt to identify source of leak.
rz.: IEnter S2.0P-AB.RC-0001, Reactor Coolant System Leak, transition to AB.LOCA if leakrate is determined to be> normal charging system makeup capacity.
I
~ Enter S2.0P-AB.LOCA-0001, Shutdown LOCA. Isolate letdown, re-align charging pump suction to RWST, isolate containment penetrations
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Answer i ~ [Exam Level. j S
. . Level I Cogmttve ! j Appl1catron
.. i ISalem 1 & 2 I 1Fac1hty: I :ExamDate:
' I j___1_21_1_9_12_0_16~I
~j194001G409 I 2.4.9 1 iROValue:il 3.8jfSROValueL+/-~~tion: 1PWG j'ROGroup:'I 1l'SROGroup::j 11 SJ::;:,, ~
55.43
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!system/Evolution
Title:
~ IGE~@
!KA Statement:!~--------------------------------------------
Knowiedge of low power/shutdown implications in accident e.g., loss of coolant accident or loss of residual heat removal) mitigation strate ies.
Explanation of* 55.43.b(5) The 79 gpm charging flow given in the stem to start, +the 10 gpm step,= 89. The stem states that a 45 gpm orifice is in Answers: 1 service. The first thing to do in AB.LOCA is isolate letdown. This will remove 45 gpm from the required charging flow necessary to maintain PZR level stable, so step 3.3 (asking if PZR level can be maintained stable or rising) will be YES. Adequate subcooling is available, and with charging flow less than 100 gpm at 3.13, GO TO Section 4.0. While technically acceptable to go to AB.RC-1 I Reference Title J: Facility Reference Number l Reference Section JI Page No.\ [Revision; IShutdown LOCA !IS2.0P-AB.LOCA-1 I Ii lj 8 I I II ! 11 Ii I I II I 11 11 I
- L.o. Number Objectiv I ABLOCAE007
tlVlaterial Required for Exar,iiin<)tior;i ' .. l l lI jaue~tion S8ifrce'.' l IFacility Exam Bank !la~es~iC>rj.~?Cl~rtc,~tiOijMet~od: * :I Direct From Source !fused Ouring'Jrain(og'Program' ! D
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- <luestion soi'.frc~ Commehtsj 185098 j
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Comment I
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