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{{#Wiki_filter:Draft Submittal (Pink Paper) DRAFT Written Exam Quality Checklist (ES-401-6)
{{#Wiki_filter:Draft Submittal (Pink Paper)
ti Written Exam Sample Plan ES-401 Written Examination Form ES-40M Quality Checkllst 5. Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies)
DRAFT Written Exam Quality Checklist (ES-401-6)
and appears appropriate: - the audit exam was systematically and randomly develcped:
ti Written Exam Sample Plan
or 2 the examinations were developed independently:
or - the licensee certifies that there is no duplication; or the audit exam was completed before the license exam was started: or from the bank at least 20 percent new, and the actual 80 / SRO-onl Between 50 end 60 percent of the questions on the RO exam are written at the comprehension/analysis level; the SRO exam may exceed 60 percent if the randomly selected WAS support the higher cognitive levels; enter the actual RO / SRO question distribution(s)
at a. Author b. Facility Reviewer (") c. NRC Chief Examiner (#) d. NRC Regional Supervisor Note: ' 'I he facility reviewer's initialsisignature are not applicaDle for NRC-developed examinativn # inde~!!~~e!?!NRC,eviewei~~~!eal items i'l Column . . . . .
'c;" . . . . . .
chief . ._ examiner co~currence.!pql;lred..........-
.. . . . . . . . . . . . . .
3Qof 34 NUREG-1821, Draft Revision


'43 46 6bility to determine and interpret the following as they apply to ABNORMAL PLANT EVQLUTION):(CFR:
ES-401    Written Examination  Form E S - 4 0 M Quality Checkllst Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:
41.10 / ~ system or into reactor building atmosphere 43.5/45.13), ieakage of reactor coolant from RHR into closed cooling water 3.4 00 DO Tier 't Group 1 RB Sa0 Fun c t I o n : K1 K2 K3 Ai A2 G KIA Number Question Type KIA Topic 1 ReactorTnp-0 0 0 0 Stabilization - 11 uecovery I 1 I 1 0 0 007EA2 02 Ability to detmmine and interpret the following as they WA Randomly Rejected apply to (EMERGENCY PLANT EVOLUTION) (CFR 41 10/435/4513)
-the audit exam was systematically and randomly develcped: or the audit exam was completed before the license exam was started: or 2 the examinations were developed independently: or-the licensee certifies that there is no duplication; or from the bank at least 20 percent new, and the actual 80 / SRO-onl Between 50 end 60 percent of the questions on the RO exam are written at the comprehension/analysis level; the SRO exam may exceed 60 percent if the randomly selected WAS support the higher cognitive levels; enter the actual RO / SRO question distribution(s) at a. Author b. Facility Reviewer (")
I Pressurizer Vapor Space Accident I3 000 0 1 0 'OOBA41.01 , Ability to operate and  
c. NRC Chief Examiner (#)
/ or monitcr the following as they KIA Randomly Rejected ~ apply to (ABNORMAL PLANT EVOLUTION):(CFR:
d. NRC Regional Supervisor Note: ' 'I he facility reviewer's initialsisignature are not applicaDle for NRC-developedexaminativn # inde~!!~~e!?!NRC,eviewei~~~!eal
41.7 I 45.6) , 1 ii Small Break LOCA I3 ~ 0 10 ~ 0 ~ 0 -- *---. ~ . o stem statement is associak Knowledge O F how to conduct and verify valve lineups. 0 OllEK3 WAKnowledge of the reasons for the following responses as Placing wntainment fan cooler damper in accident pasition they apply to (EMERGENCY PLANT EVOLUTION) (CFU 41 5 / 45 6) Large Break , LOCA / 3 0 11 0 , I 2 3 I1 1oc I26 I 3 2.6 RCP Malfunctions
    ..........items .....'c;"
/ 4 LO55 Of RX Coolant Makeup / 2 1 o c 3 o O+~AI(L ofifinow e& nf tne .r.teireial ons uewecn {ABNORMAL ccws PLANT ~vOLLT,ON, anJ Ihr lo ww,nr, CrR 41 7 s 45 81 .\ 3 o O+~AI(L ofifinow e& nf tne .r.teireial ons uewecn {ABNORMAL ccws PLANT ~VOLLT,ON, anJ Ihr lo ww,nr, CrR 41 7 s 45 81 .\ I ., 0 0 ;022AA1 .OF ~ Ability to operate and /or monitor the following as they CVCS charging low iiow alarm, sensor and indicator apply to (ABNBUMAL PLANT EVOLUTION):(CFR:
    ..... i'l Column ......chief
41.7 / ~1 45.6) h 0 ,o 1 2.9 3.8 3.5 38 4 5 5 ', I1 I1 1 0 025AA202J Loss of RHU System / 4 I boss of Component Cooling Water
      .._ examiner co~currence.!pql;lred..........-
/ I8 0 lo 0 0 0 0 026AK301 I 32 Knowledge of the reasons for the following responses as they apply lo (ABNORMAL PLANT EVOLUTION) (CFR 41 5/456) KIA Randomly Uqected Pressurizer 0 ' pressure 1 Control System Malfunction I3 0 Isolation of PZR spray following loss of PZR heaters 35 hnowlcoge of the reasons for the fu owing responses as tnev apply to ,ABNORMAL PLAN1 FVOL'JT ON, (CFR Pier *-Group I 75 Point Te h... Name i Safely Function:
3Qof 34  NUREG-1821, Draft Revision 9
Kt KZ K3 AI A2 G KIA Number ~ Question Type Power 16 KIA Topic RO SRO IATWSII Steam Gen. , Tube Rupture / I3 Steam Line Ruptuie - Transfer I4 Loss of Main Feedwater
/ 4 1 Excessive Heat Stat ion Blackout / 6 Loss of Off-site Power 16 Loss Of Vlkl AC lnst Bus 16 029EK2 O&Knowledge ofthe interrelations between (EMERGENCY PLANT EVOLUTION) and the following (CFR 41 7 145 8) h ., Ability to operate and
/or monitor the following as they amlv to EMEUGENCY PLANT EVOLUTION):(CFR:
41.7 0 0 0 1040AK1 05 Breakers. relays, and disconnects KIA Randomly Rejected Ueactivity effects of cooldown -4 ,.. 1 0 0 054AA1.02'
Ability lo operate and /or monitor the following as they ' Manual staltup of electric and steam-driven ARM pumps apply to (ABNORMAL PLANT EVOLUTION):(CFR:
41.7 / ~- 45.6) ,! &=&Ib/ \ 0 1 0 ,055EA2.04 Ability lo determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTICJN):(CFR:
41.10 /43.5 /45,13H 0 0 0 056AK1 03 Knowledae of theooerational a~~l~calions of the followinQ - - co:icepls as they appy to me ARNORMh PLANT EVOLiTlONl (CFR 41 81041 10) Instruments and cantrols operable with only dc battery power available Definition of subcwling:
use of steam tables to determine it ... 0 ! 0 1 '057AG2.1. his is a Generic, no stem statement is associate Ability to explain and apply all system limits and precaution .~ - I! o ~ o o O~~AKI.O$
1 Knowledge of the operational applications of the following concepts as they apply to the (ABNORMAL PLANT
~ EVOLUTION):(CFR:
41.8 toAl.10) 0 1 0 %?AA2 C1 L'kb I 1y 111 oetermine and nterorel tho follow ng as lnoy apply to ABNORMA PIAN1 EVCl.Lh'Olu, (CFH 41 10 ' i ,, L(-& 4 ~(?* &< , P Battery charger equipment and instrumentation Location of a leak in the SWS 2.9 3.1 3.4 3.4 I ! 4.1 4.4 I 1 4.4 ~ 4.4 ~ 3.7 , 4.1 ! 3.1 , 3.4 3.4 28 3.8 31 2.9 j Tier Wroup 1 75 Point Teb<..- Name I Safety Function:
Kf K2 K3 AI A2 0 WANumhgr QueStiQnType
~ 3.1 3.8 3.2 4 boss of Instrument Air / 18 *, LOCAQutside , 1 0 0 Containment
/ 3 ,I I 1 ~ i:1 !\b ET ~ LOSS of , Emergency , /C4001ant Recirc Steam Line Rupture - Excessive Heat Transfer I4 Inadequate Heat Transfer - Lass of Secondary Heat Sink / 4 0 '0 ~0 ~ ! i! Ability to operate and I or monitor the following as they 41.7 / Knowledge of the operational applications of the following EVOLUTION):(CFR:
41.8 to 4Z.10) ncepts as they apply to the EMERGENCY PLANT 0 1 0 0 0 0 ' 0 ,M12EA2.1 , Ability to determine and interpret the following as they ~ apply to (EMERGENCY PLANT EVQLUTION):(CFR:
41 .IO / 43.5 / 45.13) ~ il 000 0 1 0 lWE05EA2. . Ability to detennitie and interpret the following asthey ~ yapply to (EMERGENCY PLANT EVOLUTm(CFR:
41 .IO I43.5 / 45.13) > /' WA Topic Restoration of systems served by instrument air when pressure is regained Annunciators and conditions indicating signals, and remedial actions associated with the (LOCA Outside Containment).


Knowledge of event based EOP mitigation strategie WA Randomly Rejected Adherence to appropriate procedures and operation within the limitations in the facility's license and amendment Tier ?--Group 2 75 Point Tes.-- Name I Safety Function:
Tier 't Group 1 FunctIon: K1 K2 K3 A i A2 G KIA Number Question Type    KIA Topic    RB Sa0 1   1         '43 46 ReactorTnp- 0 0 0 0 0 0 007EA2 02 Ability to detmmine and interpret the following as they WA Randomly Rejected Stabilization -    apply to (EMERGENCY PLANT EVOLUTION) (CFR uecovery I 1 1 1  41 1 0 / 4 3 5 / 4 5 1 3 )
K1 K2 K3 Al A2 G KIA Number Question Twe KIA Tonic LOSS of Intsrmediate
I I
' Continuous Dropped Control Rod / 1 inoperable/Stuc i k Control Rod / 1 1 0 Emergency Boration I1 I 1000 3 0 Pressurizer
Pressurizer Vapor Space 0 0 0 0 1 0 'OOBA41.01 , Ability to operate and / or monitcr the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 I KIA Randomly Rejected
~ o Level Malfunction I2 1 ~ng;y;= i O i 1 1 Fuel Handling 0 Accident I & Steam Generator Tube Leak / 3 00 % COnCeptS as they apply to the (ABNORMAL PLANT EVOLUTION) (CFR 41 8 to 41 IO) 003AK1 01 , Knowledge of the operational appilcations of the following Reason for turbrne following reador on dropped rod event 0 085AK305 1 .- Pj 26 0 024AK203 0 0 0 028AKI 01 0 0 0 032AKZa " , I !1 enowledge af the reasons for the following responses as Power limits on rod misaligflment they appiy to (ABNORMAL PLANT EVOLUTiON):(CFR:  
          ,
~ -.;? . 41.5 145.6) I. C<'v Lw<d%l.:l k: / ! Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION)
    ~
and the foilowing:(CFR:
Accident I 3    45.6)
41.7 !45.8) KIA Randomly Rejected I Knowledge of the operational applications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION) (CFR 41 8 to 41 IO) KIA Randomly Rejected Knowledge of the interrelations between (MINORMAL PLANT EVOLUTION)
i i
and the foiiowing:(CFR:
 
41.7 / 45.8) Power supplie including proper switch positions
Small Break ~ 0 10 ~ 0 ~ 0    o stem statement is associak Knowledge OF how to conduct and verify valve lineup LOCA I 3
~ Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION)
--  *---. ~ .
and the following (CFR 41 7 I 45 8) 0 1 0 ~036AG2.4.22 This is a Generic, no stem statement is associate !: i 0 0 037AG2.4.31 This is a Generic, no stem Statement is associate : KIA Randomly Rejected KiA Randomly Rejected KIA Randomly Rejected RO SRO 2.8 2.9 3.2 3.7 I 3.4 4.2 2.6 , 2.5 2.8 ~ 3.1 2.7 ~ 3.1 00 34 3.3 POIP~ re. Name I Safety Function:
Large Break 0 0 11 0 OllEK3 WAKnowledge of the reasons for the following responses as  Placing wntainment fan cooler damper in accident pasition
K1 K2 K3 AI A2 G KIA Number Question Type ~ I Tier ?-tSr~t.ip 2 LOSS of Condenser Vacuum / 4 Acudental Llquld ~ /RQadWaste Re1 "T" 0000 ! Accidental 00 Gaseous Radwaste Re1 0 Inad. Core Cooling / 4 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTiON):(CFR:
, LOCA / 3  ,  they apply to (EMERGENCY PLANT EVOLUTION) (CFU 41 5 / 45 6)       2 RCP  1
41.10 / 43.5 /45.15) 19 I ARM System 10 1 o ' 0 Alarms / 7 Plant Fire On- 0 0 0 site / 9 8 Control Ueom 0 0 0 Evac /8 Loss ofCTMT 0 0 0 Integrity
 
/ 5 1 High Reactor Coolant Activity /9 000 a10 1 I 0 0 059AK3 02 Knowledge of the reasons for the following responses as they apoiy to (ABNORMAL PMNT EVOLUTlONl (CFR I 0 0 069A41 01 ' ' Ability to operate and I or monitor the following as they 1 ' I aPPIv to (ABNORMAL PLANT EVOLUTI0N):ICFR:
I o 1c o c 3 o O + ~ A I ( ofifinow L  e& nf tne .r.teireial ons uewecn {ABNORMAL ccws    I26 Malfunctions / 4    PLANT ~ V PLANT
41.7 / KIA Topic Conditions requiring reactor and/or turbine trip WA Randomly Rejected WA Randomly Rejected WA Randomly Rejected Bypass of a heat detector KIA Randomly Rejected KJA Randomly Rejected 0 0 0 074FA1 OG Aoilly 10 Operate ard I or monilo: rhe fo low8ng as they &A Ranaonily Re.ec1eo app:y tu .EMERGENCY PLANT EVOLUTi3N! (CFH 41 7 0 0 0 076AK20 nowledee of the interrelations between (ABNORMAL PLANT &OLUTIOM)
      .\
and the foilowlng (CFR 41 7 I45 8) RO SRO 3.9 4 1 4.5 1 2.6 3 I 34 36 2.5 2.7 I 29 33 3.5 3.6 Process radiation monitors 26 37 39
v O L L T , O N anJ
""?UP 2 I A2 G KIA Number Question Type Rediagnosis/3 0 0 0 0 0 1 WEOlEG2 This is a Generic, no stem statement is associated I Steam ~ 0 Generator 0 0 0 0 0 'WE13EG2.1, ~ This is a Generic. no stem Statement is associated, High 00 Containment Radiation
      , Ihr lo ww,nr, C r R 41 7 s 45 81 I
/ 9 l SI Termination 0 0 I 13 LOCA 00 Cooidown - Depress I4 I I Natural Circ I4 0 0 ply to (EMEUGENCY PLANT EVOLUTiON):(CFR:
I 3
41.7 i 145.6) I,, I!! 0 , 1 , 0 0 1WEi5*A to operate and I or monitor the following as they 1 0 0 ' 0 0 WE16EA Ability to operate and /or monitor the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:
  . ,
41.7 I / 45.6) il I .. i EVOLUTION):(CFR:
LO55 Of R X 0 ,o 1 0 0 ;022AA1.OF ~ Ability to operate and / o r monitor the following as they CVCS charging low iiow alarm, sensor and indicator 3 Coolant Makeup / 2  ~I1 1 apply to (ABNBUMAL PLANT EVOLUTION):(CFR: 41.7 /
41.5 /45.6) 0 0 0 0 WE03EA2 I Ability to determine and interpret the following as they NaturalCirc 0 0 0 With Seam 1 Void/ 4 I 0 0 0 0 WE09EA21 RCS Overcooling PTS / 4 000 0 WE08EK2 2 apply to (EMERGENCY 41.10 / 43.5 145.13) ' PLANT EVOLUTION  
45.6) h        4 Loss of RHU 0 0 0 lo 1 I 10 025AA202J
):(CFR: Aoility 10 aeterm ne and ntarpiet !ne follow.ny as ttiey apply 10 (*MtHGENCY PLANT EVOLUT:ON, oCFR 41 :OI 43 5, 45 13) This s d Geiiei c no olein st3lement IS assooa.:cJ Knowledge 01 lne inle.rela1ions Deheen iEMERGEhCY PLAhl' EVOLUTION, and li~c lo ow.ng (CFH 41 I 45 8, KIA Topic Knowledge of loss of cooling water procedures KIA Randomly Rejected Components and funciiens of control and safety systems, including instrumentation signals, interlocks, failure modes and automatic and manual features KIA Randomly Rejected Normal. abnormal and emergency operating procedures associated with (SI Termination)
    ',
KIA Randomly Rejected KIA Randomly Rejected KIA Randomly Rejected KIA Randomly Rejected 29 33 34 31 34 36 3.0 3.8 tq. 4.2 3.8 3.8 4.0 ~
6bility to determine and interpret the following as they ieakage of reactor coolant from RHR into closed cooling water .8 System / 4   apply to ABNORMAL PLANT EVQLUTION):(CFR: 41.10 /  system or into reactor building atmosphere 43.5/45.13),
Tier Tdroup 2 75 Point T& -. Name I Safety Function:
          ~
KI K2 K3 Al A2 G KIANumber QuestionType KIA Topic RO SRO 41.10 143.5 /45.13) Saturated Core Cooling Core Cooling I4 i LossofCTMT 0 lntegrdy / 5 0 ""'I 0 ' 0 0 0 0 ,WE07EG This is a Generic, no stern statement is associate i KIA Randomly Rejected 1.1 I I 0 0 0 0 0 :wE14*A2.2 , Ability to determine and interpret the following as they 1 KIA Randomly Rejected apply to (EMERGENCY PLANT EVOLUTION):(CFR: ,I I , 41 10/435/4513)
 
25 134 11 ,34 38 Tier z Group 1 75 Point \,-- Name / Safety ,.-I- Function:
I boss of D O 0 0 0 0 026AK301  Knowledge of the reasons for the following responses as KIA Randomly Uqected  I 32 Component    they apply lo (ABNORMAL PLANT EVOLUTION) (CFR Cooling Water /    41 5 / 4 5 6 )
K1 KZ K3 K4 K5 K6 A1 A2 A3 A4 G WANumber QuestionType
I8 Isolation of PZR spray following loss of PZR heaters 35 38
\ \&ti- __.__~~ ~ ~ ~ ~ ~ ~ ~ ~_ . -1 ;~/L~~ ! ~4~~~~ ~~ 0 0 0 0 ~0 1 !ChGiczand Knowledge of the effect that a loss or malfunction of the ' Volume Cmtrol following will have on the (SYSTEM):(CFR:
'1 Pressurizer pressure Control System 0 0  hnowlcoge of the reasons for the fu owing responses as tnev apply to ,ABNORMAL PLAN1 FVOL'JT ON, (CFR
41.7 / 45.7) Emergency 0 '0 0 10 ' 11 1 0 0 U 0 0 0DtiKfi.tB mafun:tiunof Ilie Core faoiing .. _.___ ~ ~~~ 1: ~ _ , , Pressurizer 0 0 0 0 007A1.01 ity to predict and/or m6nitor changes in parameters Relief/Cltlench Tank ociated with operating the (SYSTEM) controls I I including:(CFR:
 
R 41.5 I45.5) i 008K3.03 4 howiedge ofthe effect that a loss or malfunction of the I (SYSTEM) will have on the following:(CFf?:
Malfunction I 3
41.7 I45.4) r Knowledge of the physical connections and/or cause- effect relationships between (SYSTEM) and the foliowing:(CFR:
 
fl.2 lo 41.9 I45.7 to 45.8) Ability10 predict andlor monitorchangesin parameters associated with operating the (SYSTEM) mntrols including:(CFR:
75 Point Teh...
41.5 / 45.5) F, 1 Reactor j Protection 1 R--___-~ ~ ledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:(CFR:
Pier *-Group I Name i Safely Function: Kt KZ K3 A I A2 G KIA Number ~ Question Type   KIA Topic    RO SRO IATWSII  029EK2 O&Knowledge  ofthe interrelations between (EMERGENCY Breakers. relays, and disconnects .1 PLANT EVOLUTION) and the following (CFR 41 7 145 8)
41.7 / 45.4) Features ~____ ~~ i ~~~.~~ . KIA Topic R5 SR5 I I id ~ ~ ~_ Maintaining quench tam water level 3.1 ~ within limits I RCP Trip setpoint adjustment 75 Point 't Tier ~Group I KIA NumhRr Question Tv~e KIA ToDic Name / Safety Function:
h
K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G RO SUO \I .. lo (a) predict the impacts of the fo!lowing on the ures to correct, contro or mitigate th% STEM) and (b) based on those prediction use consequences of those abnormal operatlon:(CFR:
  . ,
41.5 / Knowledge of th@ operational implications oFthe following copCeptS as they apply to the (SYSTEM):(CFR:
Steam Ge Ability to operate and / o r monitor the following as they KIA Randomly Rejected .4
41.5 I 45.6) ~ -~ 025K5 02 - 0 - 0 0 - 0 - 0 0 -. 0 - 3.0 __ 2.8 - 3.5 3.7 - 34 Containment Cooling .- Ice Condenser I I j .. Containment
, Tube Rupture /    amlv to EMEUGENCY PLANT EVOLUTION):(CFR: 4 I I3
! Spray Fan motor thermal overiaadlhigh-speed
            !
>peration Up. Rejected -~ D26A4.05 &&uaiy operate and/or monitor in the control ~ room:(CFR:
Ueactivity effects of cooldown .4 Steam Line  0 0 0 1040AK1 05 Ruptuie -
41.7 I45.5 to 45.8) ~~ ~ ___- Knowiedge of (SYSTEM) design feature@)
1 Excessive Heat Transfer I 4 Loss of Main Feedwater / 4
and of interlock(s)
 
which pmvide for the foHowing:(CFR:
  ,
41.7) __~ 3mtsinment spray reset switches .~~ . . . . . . . . . . i""' . . . . . . . . . . . ..... . . . . . w*+#&sm .. ... . .. I 0 'I 00 3.9 00 00 9bllily to locate and operate component ncluding local controls ~~ - Main Feedwater 3.4 -~ 4.2 __ 4.4 3.1 .- 0 059Y1 02 hiowledge of (he physica ccnnectms andlor case- I affect relatioiishios between (SYSTEM) and the ~~ ~ Auxiii2rylEmerg 5' ency Feedwater . - .. AC Electrical i Distribution hdtty to mw:w ddomiltic operations of the (SYSTEM) (CF9 41 7 145 I) - 4.1 _- 3.0 :DIG ~- ___ 3attery discharge rate QC Eiectrical Distribution
 
! o 063~d.03 ,Ability to manudly operate and/or rlionitor in the wntrui mom:(CFH:
  . .
41 7 / 45.5 to 454 r\ 1- ' .> , _...--- I f\.!;. Y-- .
0 054AA1.02' -4 Ability lo operate and / o r monitor the following as they
75 Point Te-.. Name I Safety Funetion:
        ~-
K1 K2 K3 K Tier 2-Group 1 G WA Number Questian Type . -P K5 K6 AI A2 A3 RO SRO WATopic Establishing power from the ring bus (to relieve EBiG) - 3.2 2.5 3.8 3.3 4.0 __ 2.9 ~. 3.1 ___ 2.5 __ 2.7 -- - 3.3 3% 3.4 - 3.5 - 1.3 ~~~~ 3.2 3.4 3.2 .~~~~ 2.9 1 00 I ~ Emergency , o o , Generator Diesel Ability to manually operate andior monitor in the MntrOl rmrn:(CFR 41.7 145.5 to45.8) ~~ edge of the operationai i ons of the foilowing M):(CFB: 41.5 / , no stem statement is associate Radiation theory. including sources, types. units and effects Ability to locate and operate component including bcal control l ~- - )78K2.02 power supplies to the Emergency air compressor 01 10362. fPQs is a Generic, no stem statement is associate A / Ability to recognize abnormal indications fw system operating parameters which are entry-level conditions for emergency and abnormal operating p:osedure Automatic start features associated with SWS pump mntrois ~- ~ ~. lo - ~ 0 0,l 0 ~~~~ 17Mr&nowledge of (SYSTEM) design feature(s)
apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 /
and or interlock(s)
45.6)
which prov.$e for the fallo-R: 41.7) 00 Service Water 0 ~ I ..I- - instrument AI^ o ___. ~~~ ~ ~~~~~~ of the effect that a loss or malfunction of the (SYSTEM) will have on the 0 - 0 0 I io Containment air system . ___ o (a) predict the impacts of the following on the ures to correct. wntro e M) and (b) based on those predictions, use equenses of those abno (CFR: 41.5 I ~ ~~ nowledge of eleclrical power supplies to the following:(CFR 41.7) /---- 0 Io Paint T- Name I Safety Function:
        ' Manual staltup of electric and steam-driven ARM pumps ~
KI K2 K5 K4 K5 K6 AI A2 A3 A4 G Emergency i Generator ency Feedwater 1 - 0 0 - 0 0 Tierk Group 1 KIA Number Question Type sociated wlth operating the (SYSTEM) contro!s cludmg:(CFR 41.5 / 45.5) ~~~~~~~~~~~~
I , !  &
~~ the operational implications of the following ncepts as they apply to the (SYSTEM):(CFR 41.5 / . KIA Topic RO BRO Operating voltage currents and 3.2 3.3 temueratures
      \ = & I b /      ~
~ __ Pump head eff@cts when contrul valve I S 75 POI! -. Name I Safety Function:
Instruments and cantrols operable with only dc battery power 3.7 , Station  0 1 0 ,055EA2.04 Ability lo determine and interpret the following as they Blackout / 6    apply to (EMERGENCY PLANT EVOLUTICJN):(CFR: available 41.10 /43.5 /45,13H        !
K1 K2 K3 K4 K5 K6 A7X2 A3 A4 G Tier Group 2 KIA Number QuesttDoPt Type KIA Topie RO SRQ TTq7 000 t 4 lo 1 Hydrogen Recombiner and Purge Control 028A1.02 1 hbiiity to predict andh monitor changes in paramaters 1 including:(CFR:
Loss of Off-site Power 16 0 0 0 056AK1 03  -
41.5/45.5)
Knowledae of theooerational a ~ ~ l ~ c a l i of co:icepls as they appy to me ARNORMhl. PLANT o nthe -
KIA Randomly Rejected associated with operating the (SYSTEM) controls i 3.4 j 3.7 -~ ~ ~ -- - ~ - - - __ - 029hZ.03 Ability to (a) predict the impacts of the foilovdng on the KIA Randomly Rejected 2.7 3.1 (SYSTEM) and (b) based on these prediction use procadures to correct, control, or mingate the consequences of th3se abnormal operation:(CFR 41.5 / __ - - - KIA Randomly Rejected ~ __ ~ ~ .- ~ ~ ~. no stem Sfatement is associate Containment Purge Spent Fuel Pool Cooling - - __ - 0 0 0 1 _ 00 00 f- 00 I 4 - ~ ~ ~ ~__~ - - ~~ - -. ~ 034K6.02 wledge of the effect that a io% or malfunction Radiation monitoring systems owing will h,aw on the (SYSTEM):(CFR:
s followinQ Definition of subcwling: use of steam tables to determine it 3.1 , EVOLiTlONl (CFR 41 81041 10)
41.7 /45.7) i\ I Fuel Handling 1 Equipment i I L&,CL--.--
  . . .
hSF -. -~ wiedge of the physical connections andlur cause- ct relationships between (SYSTEM) and the followingJCFR4 to41.9/45.71045.8)
Loss Of V l k l 0 ! 0 1 '057AG his is a Generic, no stem statement is associate Ability to explain and apply all system limits and precautions. .8
i 1 Steam , Generator i ll 1 /A- I I-.- ~ L-~~- - __ 341K1.02 1 Knowledge of the ~5,vsical wnnections andIa cause- i ihxid&y&iected , Steam 1 Dump/Turbrne Bypass Control I - ~ Main Turbine , Generator I. eftzct rcliionshipi between (SYSTEM) and the folfowing.(CF'R 41.2 tu 41.9 145.7 tu 45.8) -~ I ~~~ ~~~ Turbine Slop/govemo:
 
valve closure on 1 turbinetrip l- Condenser Air Remavat -t 00 i 0 OI PRM system 0 , 055K1.06 wledge of the physical connections andlor cause- ct relatiofwhips between (SYSTEM) and the owing:(CFR 61.2to41.9/45.7to45.8)
AC lnst Bus 16        ,,
i'l-,/ ~~~ ~~~~ &Ac effect relationships between (SYSTEM) and the following:(CFR:
L(-& 4 i
41.2 to 41.9 I45.7 to 45.8) edge of the physical wnnections and/or cause- i_.~ Liquid 1 Radwaste ---- KIA Randomly Rejected 0 lo Tier 2 Group 2 00 KIA Topie 190 SRO 75 Point I.- Name I Safety -,-.- Function:
          ~(?*&< ,
K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G KIA Number Question Type 7 1' 00 OI 00 00 071K6 Krfowlae of the effect that a loss or malfunction of the following wiil have on the (SYSTEM):(CFR:
P I !
41.7 / 45.7) KIA Randomly Rejected 0 3 - 3.3 ~- 1.1 1 1.4 1.6 -- 4.5 - 3.3 2.8 + .- This is a Generic. no stem statement is associete __ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .~ Knowledge of system status criteria whioh require the notiflcation of plant ~~~~ 07262.1.16 u' Y 1 I I ,- monnel. I 1t9 .~~ -~ Circulating Water - Statim Air ~ __ __ WA Randomly Rejected 075K1.02 - 079K2 - 086K5.03 L/ bWl@dQe of the physical connections and/or cause- effect relationships betwean (SYSTEM) and the fdlowing:(CFR 41.2 to41.9 /45.7 to 45.8) - --p Knwrledge of e:edncat powet nupp!ies lo tho foliov!'r:g:(CFR:
    .~ -
41.7) WA Randomly Rejected i +T Fire Protection 0 __ ___ ~ Effect of water spray on electrical components nowledye 01 the operatioiiai imp:ications o! the fdlowinp !i ic~pts as Ibey apply lo the (SYSTEM):(CFR:
o o o
41.5 1 45.3) ,. - .,. -.--. - . . . . . . .. Know:edge of eiectfica:
  ~ O ~ ~ A K I . O $ 1 Knowledge of the operational applications of the following Battery charger equipment and instrumentation  28 31 Power 16    concepts as they apply to the (ABNORMAL PLANT
power supplies 10 Ihe 1ol:owing:iCFR:
    ~ EVOLUTION):(CFR: 41.8 toAl.10)
41.7) jjs ~ Control Rod 0 0 Drive ~ . Ueactor Coo!ant 0 0 001K2.01 KIA Randomly Rejected ~ .~~ ~ ~__~ -~ Knowledge of the effect that a loss or malfunction d the (SYSTEM) will have on the following:(CFR:
0 1 0 %?AA2 C1 L'kbI 1y 111 oetermine and nterorel tho follow ng as lnoy  Location of a leak in the SWS  2.9 j apply to ABNORMAI. PIAN1 EVCl.Lh'Olu, (CFH 41 10 '
41.7 / 45.4) . _- 1.2 _- 3.2 2.5 002K3.02 ~_ 0HA3.03j h 014K3.02~
 
WA Randomly Rejected i 01 00 I -~ Charging and letdown Ability to monitor automatic operations of the (SYSTEM) 'nduding:(CFR:
75 Point Teb<..-
41.7 / 45.7) Pressurizer Level Control __ - ~- Rod Position Indication knowledge of the effac: lhal a loss ar maifunctior, of the (SVSIEM) will have on the fo lovnng (CFR 41 I I45 4) Plant computer Tier L Group 2 75 Point -- Name I Safety Function:
Tier W r o u p 1 Name I Safety Function: Kf K2 K3 A I A2 0 WANumhgr QueStiQnType    WA Topic boss of    Ability to operate and I or monitor the following as they Restoration of systems served by instrument air when Instrument Air /      41.7 / pressure is regained
K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G WA Number Question TVDR I Nuclear . ~ ~. ~~ ~ In-core Temperature Monitor Containment Iodine Removal - 0 0 - 0 - a .. ~ ~ Ability to predict andlor monitor changes in parameters associated with operating the (SYSTEM) cOntrols including:(CFR:
 
41.5/45.5)
  * ,
1 I 01782.2.22 Hhis is a Generic, no stem statement is associated 0 027A4.02 'lity to manually operate andlor monitor in the control m:(CFB: 41.7 I45.5 to 45.8) KIA Topic KIA Randomly Rejected KIA Randomly Rejected ~ Kmwledge of limiting conditions for operations and safety limits. Remote oDeratiin and handiinu of iodine RO SRO - 3.1 __ 0 3.4 Point Test Tier 3 KA Number KIA Toplc RO SRO Category - - .- ility to make accurat clear and concise verbal reports. 17 +-- .. __ ~~~ Conduct of Operations 1 ~- ~ - Conduct of Qperatiins ity to direct personnel activities inside the control room. (g 11 .- wledge of new and spent fuel movement procedure ons and safety limits. ~ Got IimGconditions for operations and safety limits. ~ nowledge GEOP entry conditions and immediate adion steps.
LOCAQutside , 1 0 0 Knowledge of the operational applications of the following Annunciators and conditions indicating signals, and remedial Containment / 3  ncepts as they apply to the EMERGENCY PLANT  actions associated with the (LOCA Outside Containment).
 
EVOLUTION):(CFR: 41.8 to 4Z.10)      !\b
  ,I I 1          ~
,
~
,
LOSS of Emergency
/C4001ant Recirc i :
0 ' 0 ~0
  !
i1 !
 
  ~
Knowledge of event based EOP mitigation strategie .1 .8
 
            ~
ET Steam Line 0 0 0 0 0 ' 0 ,M12EA2.1 , Ability to determine and interpret the following as they WA Randomly Rejected Rupture -  ~ apply to (EMERGENCY PLANT EVQLUTION):(CFR:
Excessive Heat  41 . I O / 43.5 / 45.13)
Transfer I 4 ~
i l Inadequate 0 0 0 0 1 0 lWE05EA2. . Ability to detennitie and interpret the following asthey Adherence to appropriate procedures and operation within the Heat Transfer -  y a p p l y to (EMERGENCY PLANT E V O L U T m ( C F R : limitations in the facility's license and amendment Lass of  ~ 41 . I O I43.5 / 45.13) > /'
Secondary Heat Sink / 4
 
75 Point Tes.--
Name I Safety Tier ?--Group2 Function: K1 K2 K3 A l A2 G KIA Number Question T w e    KIA Tonic    RO SRO
' Continuous .9 I
Dropped Control Rod / 1 1 0 0 0 003AK1 01 %, Knowledge of the operational appilcations of the following COnCeptS as they apply to the (ABNORMAL PLANT Reason for turbrne following reador on dropped rod event I EVOLUTION) (CFR 41 8 to 41 IO)
inoperable/Stuc 3 0 0 0 085AK305 1 enowledge af the reasons for the following responses as Power limits on rod misaligflment .2
 
i k Control Rod /  they appiy to (ABNORMAL PLANT EVOLUTiON):(CFR: ~ -?
          ;. .
1    41.5 145.6) C<'v Lw<d%l.:l
    .P- j 26 Emergency 0 0 024AK203
    /
k:
Knowledge of the interrelations between (ABNORMAL
        !
KIA Randomly Rejected , Boration I 1  PLANT EVOLUTION) and the foilowing:(CFR: 41.7 !45.8)
I Pressurizer ~ o 0 0 0 028AKI 01 Knowledge of the operational applications of the following KIA Randomly Rejected  2.8 ~ Level    concepts as they apply to the (ABNORMAL PLANT Malfunction I 2  EVOLUTION) (CFR 41 8 to 41 IO)
1 ~ng;y;= i O 0 0 0 032AKZa Knowledge of the interrelations between (MINORMAL PLANT EVOLUTION) and the foiiowing:(CFR: 41.7 / 45.8) ~
Power supplies. including proper switch positions 2.7 ~ i " ,
  ! 1 I
LOSS of 0  Knowledge of the interrelations between (ABNORMAL KIA Randomly Rejected  0 0 Intsrmediate  PLANT EVOLUTION) and the following (CFR 41 7 I 45 8)
 
1 Fuel Handling 0 0 10 ~036AG2.4.22 This is a Generic, no stem statement is associate KiA Randomly Rejected  3 4 Accident I &  ! :
i Steam  0 0 037AG2.4.31 This is a Generic, no stem Statement is associate KIA Randomly Rejected .4 Generator Tube Leak / 3 1 :
 
75 POIP~ re.
 
Name I Safety Tier ?-tSr~t.ip2 Function: K1 K2 K3 A I A2 G KIA Number Question Type  KIA Topic  RO SRO LOSS of Condenser Vacuum / 4 Acudental
  "T" 0 0 0 0 0 0 059AK3 02 I
Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTiON):(CFR:41.10 /
43.5 /45.15)
Knowledge of the reasons for the following responses as Conditions requiring reactor and/or turbine trip WA Randomly Rejected 3.9 41 Llquld    they apoiy to (ABNORMAL PMNT EVOLUTlONl (CFR
~ /RQadWasteRe1
!
Accidental 0 0 0      WA Randomly Rejected I Gaseous Radwaste Re1 19  ~
I ARM System Alarms / 7 10 1o ' 0 I
WA Randomly Rejected  34 36 Plant Fire On- 0 0 0 1      Bypass of a heat detector .7 I site / 9 8 Control Ueom 0 0 0     KIA Randomly Rejected  29 33 Evac / 8 I Loss ofCTMT Integrity / 5 0 0 0 0 1 0 069A41'01 I
  '
    ' Ability to operate and I or monitor the following as they aPPIv to (ABNORMAL PLANT EVOLUTI0N):ICFR: 41.7 /
KJA Randomly Rejected Inad. Core 0 0 0 0 0 0 074FA1 OG Aoilly 10 Operate ard Ior monilo: rhe fo low8ngas they &A Ranaonily Re.ec1eo Cooling / 4  app:y tu .EMERGENCY PLANT EVOLUTi3N! (CFH 41 7
 
High Reactor a 1 0 0 0 0 076AK20 nowledee of the interrelations between (ABNORMAL Process radiation monitors  26 Coolant Activity  PLANT &OLUTIOM) and the foilowlng (CFR 41 7 I 4 5 8)
/9
 
      ""?UP 2 I A2 G KIA Number Question Type    KIA Topic Rediagnosis/3 0 0 0 0 0 1 WEOlEG2 This is a Generic, no stem statement is associated Knowledge of loss of cooling water procedures I Steam Generator
  ~ 0 0 0 0 0 0 'WE13EG2.1, This is a Generic. no stem Statement is associated,
    ~    KIA Randomly Rejected I ! !
I , ,
Components and funciiens of control and safety systems, 0 , 1 , 0 0 1WEi5A to operate and I or monitor the following as they ply to (EMEUGENCY PLANT EVOLUTiON):(CFR:4 including instrumentation signals, interlocks, failure modes i 145.6)    and automatic and manual features
 
0 0 0 WE16EA Ability to operate and /or monitor the following as they KIA Randomly Rejected  29 High Containment 0 0 0 '
i l I apply to (EMERGENCY PLANT EVOLUTION):(CFR:4 Radiation / 9 I / 45.6)
  . .
l SI Termination 0 0      Normal. abnormal and emergency operating procedures 33 associated with (SI Termination)
I 13    i EVOLUTION):(CFR:41.5 / 4 5 . 6 )      t LOCA 0 0 0 0 0 0 WE03EA2 I Ability to determine and interpret the following as they KIA Randomly Rejected  34 Cooidown -  apply to (EMERGENCY' PLANT EVOLUTION):(CFR:
Depress I 4  41.10 / 43.5 145.13)
I  I I Natural Circ I 4 0 0 0 0 0 0 WE09EA21 Aoility 10 aeterm ne and ntarpiet !ne follow.ny as ttiey KIA Randomly Rejected  31 apply 10 (MtHGENCY PLANT EVOLUT:ON, oCFR 41 : O I 43 5, 45 13)
NaturalCirc 0 0 0  This s d Geiiei c no olein st3lement IS assooa.:cJ KIA Randomly Rejected  34 3.8 1 With Seam Void/ 4 RCS 0 0 0 0 WE08EK2 2 Knowledge 01 lne inle.rela1ions Deheen iEMERGEhCY KIA Randomly Rejected  36 Overcooling  PLAhl' EVOLUTION, and li~clo ow.ng (CFH 41 I 45 8,      ~
PTS / 4
 
75 Point T& -.
Name I Safety Tier Tdroup 2 Function: K I K2 K3 A l A2 G KIANumber QuestionType    KIA Topic RO SRO 41.10 143.5 /45.13)
Saturated Core Cooling Core 0 " "0' I 0 ' 0 0 0 ,WE07EG2.2. This is a Generic, no stern statement is associate i KIA Randomly Rejected
 
25 134
 
Cooling I 4 i
LossofCTMT lntegrdy / 5 0 0 0
  , I
 
1 I
 
  . 1 0 :wE14A I
    , Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:
1, I
KIA Randomly Rejected ,34 38 41 1 0 / 4 3 5 / 4 5 1 3 )
 
75 Point \,--
Name / Safety  ,.-I-Tier z Group 1 Function: K1 KZ K3 K4 K5 K6 A1 A2 A3 A4 G WANumber QuestionType    KIA Topic  R5 SR5
!ChGiczand 0
  ~
 
  ~_
 
  .
0 ~0 1-1 ; ~ / L! ~4~~~~
    ~ ~ ~~ __.__~~ ~
      \\&ti-
      ~ ~ ~ ~ ~
Knowledge of the effect that a loss or malfunction of the I I id
' Volume Cmtrol    following will have on the (SYSTEM):(CFR: 41.7 / 45.7)
Emergency 0 '0 0 10 ' 11 1 0 0 U 0 0 0DtiKfi.tB    mafun:tiunof Ilie Core faoiing
~~~
  ~
_ ,1 :
  ,    .. _.___  ~ ~ ~ ~_
Pressurizer  0 0 0 0 007A1.01 ity to predict and/or m6nitor changes in parameters Maintaining quench t a m water level 3.1 ~
Relief/Cltlench    ociated with operating the (SYSTEM) controls within limits i Tank I
I including:(CFR: R 41.5 I45.5)
I 008K3.03 4 howiedge ofthe effect that a loss or malfunctionof the RCP I (SYSTEM) will have on the following:(CFf?: 41.7 I45.4)
r Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: f l . 2 lo 41.9 I45.7 to 45.8)
1 Reactor    Ability10 predict andlor monitorchangesin parameters Trip setpoint adjustment j Protection    associated with operating the (SYSTEM) mntrols 1      including:(CFR: 41.5 / 45.5) F, R--___-~ ~
ledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:(CFR: 41.7 / 45.4)
Features i ~~~.~~ .     ~~
        ~____
 
75 Point 't Name / Safety Tier ~ G r o u pI Function:
  -
K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G
    - KIA NumhRr Question T..v ~ e
      \ I KIA ToDic  RO SUO
            - Containment  0  0  lo (a) predict the impacts of the fo!lowing on the Fan motor thermal overiaadlhigh-speed Cooling    STEM) and (b) based on those predictions. use >peration ures to correct, control. or mitigate th%
consequences of those abnormal operatlon:(CFR: 41.5 /
  .- - - 45.6)  -~   __
II
        ~
Ice Condenser  0  0 025K5 02 Knowledge of th@operational implications oFthe following Up. Rejected copCeptS as they apply to the (SYSTEM):(CFR: 41.5 I j ..       -~ _ _ ~ -
Containment 0 0 D26A4.05 & & u a i y operate and/or monitor in the control 3mtsinment spray reset switches ! Spray    ~ room:(CFR: 41.7 I45.5 to 45.8)
i""' w*+#&sm
... ...
..
  .. .
  ......~~
.......................
0 'I 0 0
    -.
 
        ~~
Knowiedge of (SYSTEM) design feature@)and of
        ~
interlock(s) which pmvide for the foHowing:(CFR: 41.7)
___- I             -
0 0 0 0      9bllily to locate and operate components. ncluding local controls
  ~~ -
Main Feedwater    0 059Y1 02 I hiowledge of (he physica ccnnectms andlor c a s e -
affect relatioiishios between (SYSTEM) and the ~~ ~
            -~
hdtty to mw:w ddomiltic operations of the (SYSTEM) Auxiii2rylEmerg 5' ency Feedwater      (CF9 41 7 145 I )
i .
AC Electrical Distribution
  - .
          :DIG
            - __ .4
            ~- ___ _- .1
!    o QC Eiectrical    063~d.03 ,Ability to manudly operate and/or rlionitor in the wntrui 3attery discharge rate Distribution    mom:(CFH: 41 7 / 45.5 to 4 5 4 r\
I 1-f\.!;. .>
      ' ,
Y--
_...---
        .    .-
 
  ,
75 Point Te-..
Tier 2-Group 1
 
Name I Safety  .-P Funetion:
I K1 K2 K3 K K5 K6 A I A2 A3 G WA Number Questian Type    WATopic
            -
RO SRO
            -
3.3
~ Emergency o o    Ability to manually operate andior monitor in the MntrOl Establishing power from the ring bus (to Diesel    rmrn:(CFR 41.7 145.5 to45.8)  relieve EBiG)
, Generator
        ~~
edge of the operationai i ons of the foilowing Radiation theory. including sources, %
M):(CFB: 41.5 / types. units and effects
      , no stem statement is associate Ability to locate and operate components. .4 l          including bcal control ~--   -
    )78K2.02  power supplies to the  Emergency air compressor .5 0 0
            - .3 0 1 10362.4.4 fPQs is a Generic, no stem statement is associate Ability to recognize abnormal indications lo    A /  f w system operating parameters which are entry-level conditions for emergency and abnormal operating p:osedure ~      ~~~~
          ~  ~. ~- __ ~~~~
1 7 M r & n o w l e d g e of (SYSTEM) design feature(s) and or  Automatic start features associated with .2 Service Water 0 0 0 , l 0 0 0 interlock(s) which prov.$e for the fallo-R:  41.7) SWS pump mntrois
  ~
I instrument AI^
  -
o
  ..I-I io  0
    ~~~  ~ ~~~~~~
__ of the effect that a loss or malfunction of the (SYSTEM) will have on the Containment air system ~. .___    ___ .2 0 Io  0  o (a) predict the impacts of the following on the M) and (b) based on those predictions, use ures to correct. wntro  e equenses of those abno  (CFR: 41.5 I
        ~ ~~
__ .~~~~ .9 nowledge of eleclrical power supplies to the following:(CFR 41.7/----
            --
 
75 Paint T-         .
Name I Safety Tierk Group 1 Function:
Emergency
  --
KI K2 K5 K4 K5 K6 A I A2 A3 A4 G KIA Number Question Type    KIA Topic Operating voltages. currents and RO BRO i Generator sociated wlth operating the (SYSTEM) contro!s cludmg:(CFR 41.5 / 45.5)
temueratures
      ~~~~~~~~~~~~ ~~  __ ~
0 0 the operational implications of the following Pump head eff@ctswhen contrul valve IS ency Feedwater    ncepts as they apply to the (SYSTEM):(CFR 41.5 /
 
75 POI!
-.
Name ISafety Tier  Group 2 Function: K1 K2 K3 K4 K5 K6 A 7 X 2 A3 A4 G KIA Number QuesttDoPt Type    KIA Topie  RO SRQ 1 Hydrogen  TTq7  1 hbiiity to predict a n d h monitor changes in paramaters 028A1.02      KIA Randomly Rejected i j t
Recombiner and Purge Control 1 associated with operating the (SYSTEM) controls including:(CFR: 41.5/45.5)      3.4 ~ ~ ~  --   - ~ - - - __ -
Containment  0 0 0 029hZ.03  Ability to (a) predict the impacts of the foilovdng on the KIA Randomly Rejected  2.7 Purge      (SYSTEM) and (b) based on these predictions. use procadures to correct, control, or mingate the Spent Fuel Pool Cooling
- - __
4lo
_ -
    ~ ~ .-
    -.
    ~ ~
    ~
      ~.
consequences of th3se abnormal operation:(CFR 41.5/
      ~
      ~
      ~ _ _-~ - -
__
no stem Sfatement is associate ~~  -
__
KIA Randomly Rejected
          ~
            - -
            ~
            -
Fuel Handling  0 0 0 034K6.02  wledge of the effect that a io% or malfunction Radiation monitoring systems 1 Equipment      owing will h,awon the (SYSTEM):(CFR: 41.7/45.7)
f-i i\  I L&,CL--.--
I 1 Steam
, Generator  i 0 0 0
        -. -~
wiedge of the physical connections andlur cause-ct relationships between (SYSTEM) and the h S F ll I
followingJCFR41.2 to41.9/45.71045.8)  i 1I-.- /A-  __  I
, Steam 1 Dump/Turbrne 0 0 0 341K1.02  1
      ~ L-~~- -
Knowledge of the ~5,vsicalwnnections andIa cause-eftzct rcliionshipi between (SYSTEM) and the i ihxid&y&iected I .
Bypass Control    folfowing.(CF'R41.2 tu 41.9 145.7 tu 45.8)
I
,
-
Main Turbine Generator
  ~
4 1
    ~~~ ~~~    -~
I
 
Turbine Slop/govemo: valve closure on turbinetrip l -
Condenser Air -t 0 0  0 , 055K1.06  wledge of the physical connections andlor cause-ct relatiofwhips between (SYSTEM) and the PRM system i
Remavat owing:(CFR 61.2to41.9/45.7to45.8)
i'l-,/
      & A c i_.~        ~~~ ~~~~ - - - -
Liquid  0 lo  O I 0  edge of the physical wnnections and/or cause- KIA Randomly Rejected 1 Radwaste    effect relationships between (SYSTEM) and the following:(CFR: 41.2 to 41.9I45.7to 45.8)
 
75 Point .-
Tier 2 Group 2 I
Name I Safety  -,-.-
 
Function: K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G KIA Number Question Type    KIA Topie    190 SRO 071K6 K r f o w l a e of the effect that a loss or malfunction of the KIA Randomly Rejected  0 3 following wiil have on the (SYSTEM):(CFR: 41.7 / 45.7)
    + .-    .~ __    -
 
          ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
0  07262.1.16 This is a Generi no stem statement is associete Knowledge of system status criteria Y whioh require the notiflcation of plant u'    monne I
.~~-~
-
Circulating Water Statim Air
 
I, -
I 0 0 1' 075K1.02
    -
079K2
    -
b W l @ d Q of e the physical connections and/or cause-effect relationships betwean (SYSTEM) and the fdlowing:(CFR 41.2 to41.9 /45.7 to 45.8)
Knwrledge of e:edncat powet nupp!ies lo tho foliov!'r:g:(CFR: 41.7)
__
WA Randomly Rejected WA Randomly Rejected
__
__
___
            ~~~~
            -
1t9
            --p i
              ~- !i        +T
~          ~
Fire Protection 0  0 0 086K5.03 nowledye 01 the operatioiiai imp:ications o! the fdlowinp Effect of water spray on electrical i c ~ p t sas Ibey apply lo the (SYSTEM):(CFR: 41.5 1 components L/ 45.3)
      -
~
Control Rod Drive 0 0 O
0 0I 001K2.01
      .,.., -.--.
      - . ... . . ..
Know:edge of eiectfica: power supplies 10 Ihe 1ol:owing:iCFR: 41.7)
KIA Randomly Rejected  jjs ~ .    ~ .~~ ~ ~ _ _ ~  -~    . _- --
002K3.02 Knowledge of the effect that a loss or malfunction d the WA Randomly Rejected .5 Ueactor Coo!ant 0 0  0 0 (SYSTEM) will have on the following:(CFR: 41.7 / 45.4)
i
    ~_      -~    _- -
Ability to monitor automatic operations of the (SYSTEM) Charging and letdown .3 Pressurizer Level Control  0HA3.03j 'nduding:(CFR: 41.7 / 45.7)
h
__ - ~-
 
0 01  0 1 4 K 3 . 0 2 ~ knowledge of the effac: lhal a loss ar maifunctior, of the Plant computer .8 Rod Position  0 0 Indication    (SVSIEM) will have on the fo lovnng (CFR 41 I I 4 5 4)
I
 
75 Point --
Name I Safety Tier L Group 2 Function:
I Nuclear
  -
K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G W A Number Question TVDR .. KIA Topic
          -
RO SRO 0      KIA Randomly Rejected
. ~ ~. ~~
      ~  ~
__
0  Ability to predict andlor monitor changes in parameters KIA Randomly Rejected  0 associated with operating the (SYSTEM) cOntrols including:(CFR: 41.5/45.5)
~  -      ~
In-core  0 1 I 01782.2.22 H h i s is a Generic, no stem statement is associated Kmwledge of limiting conditions for Temperature        operations and safety limit Monitor
  -
Containment a  0 027A4.02 'lity to manually operate andlor monitor in the control Remote oDeratiin and handiinu of iodine Iodine Removal    m:(CFB: 41.7 I45.5 to 45.8)
 
75 Point Test Tier 3 Category KA Number KIA Toplc    RO SRO
.. __ ~~~
  - -  .-
Conduct of  ility to make accurate. clear and concise verbal reports.
 
Operations
    + - -
 
  ~- ~
      -  1 Conduct of  ity to direct personnel activities inside the control room.
 
Qperatiins (g
 
    .-
wledge of new and spent fuel movement procedure ons and safety limit ~
G o t IimGconditions for operations and safety limit ~
nowledge GEOP entry conditions and immediate adion steps.
}}
}}

Latest revision as of 01:07, 24 November 2019

V. C. Summer April 2004 Exam 50-395/2004-301 Draft Written Exam Quality Checklist ES-401-6 & Sample Plan
ML041410410
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 09/15/2003
From: Laska G
Division of Reactor Safety II
To:
References
Download: ML041410410 (17)


Text

Draft Submittal (Pink Paper)

DRAFT Written Exam Quality Checklist (ES-401-6)

ti Written Exam Sample Plan

ES-401 Written Examination Form E S - 4 0 M Quality Checkllst Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:

-the audit exam was systematically and randomly develcped: or the audit exam was completed before the license exam was started: or 2 the examinations were developed independently: or-the licensee certifies that there is no duplication; or from the bank at least 20 percent new, and the actual 80 / SRO-onl Between 50 end 60 percent of the questions on the RO exam are written at the comprehension/analysis level; the SRO exam may exceed 60 percent if the randomly selected WAS support the higher cognitive levels; enter the actual RO / SRO question distribution(s) at a. Author b. Facility Reviewer (")

c. NRC Chief Examiner (#)

d. NRC Regional Supervisor Note: ' 'I he facility reviewer's initialsisignature are not applicaDle for NRC-developedexaminativn # inde~!!~~e!?!NRC,eviewei~~~!eal

..........items .....'c;"

..... i'l Column ......chief

.._ examiner co~currence.!pql;lred..........-

3Qof 34 NUREG-1821, Draft Revision 9

Tier 't Group 1 FunctIon: K1 K2 K3 A i A2 G KIA Number Question Type KIA Topic RB Sa0 1 1 '43 46 ReactorTnp- 0 0 0 0 0 0 007EA2 02 Ability to detmmine and interpret the following as they WA Randomly Rejected Stabilization - apply to (EMERGENCY PLANT EVOLUTION) (CFR uecovery I 1 1 1 41 1 0 / 4 3 5 / 4 5 1 3 )

I I

Pressurizer Vapor Space 0 0 0 0 1 0 'OOBA41.01 , Ability to operate and / or monitcr the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 I KIA Randomly Rejected

,

~

Accident I 3 45.6)

i i

Small Break ~ 0 10 ~ 0 ~ 0 o stem statement is associak Knowledge OF how to conduct and verify valve lineup LOCA I 3

-- *---. ~ .

Large Break 0 0 11 0 OllEK3 WAKnowledge of the reasons for the following responses as Placing wntainment fan cooler damper in accident pasition

, LOCA / 3 , they apply to (EMERGENCY PLANT I EVOLUTION) (CFU 41 5 / 45 6) 2 RCP 1

I o 1c o c 3 o O + ~ A I ( ofifinow L e& nf tne .r.teireial ons uewecn {ABNORMAL ccws I26 Malfunctions / 4 PLANT ~ V PLANT

.\

v O L L T , O N anJ

, Ihr lo ww,nr, C r R 41 7 s 45 81 I

I 3

. ,

LO55 Of R X 0 ,o 1 0 0 ;022AA1.OF ~ Ability to operate and / o r monitor the following as they CVCS charging low iiow alarm, sensor and indicator 3 Coolant Makeup / 2 ~I1 1 apply to (ABNBUMAL PLANT EVOLUTION):(CFR: 41.7 /

45.6) h 4 Loss of RHU 0 0 0 lo 1 I 10 025AA202J

',

6bility to determine and interpret the following as they ieakage of reactor coolant from RHR into closed cooling water .8 System / 4 apply to ABNORMAL PLANT EVQLUTION):(CFR: 41.10 / system or into reactor building atmosphere 43.5/45.13),

~

I boss of D O 0 0 0 0 026AK301 Knowledge of the reasons for the following responses as KIA Randomly Uqected I 32 Component they apply lo (ABNORMAL PLANT EVOLUTION) (CFR Cooling Water / 41 5 / 4 5 6 )

I8 Isolation of PZR spray following loss of PZR heaters 35 38

'1 Pressurizer pressure Control System 0 0 hnowlcoge of the reasons for the fu owing responses as tnev apply to ,ABNORMAL PLAN1 FVOL'JT ON, (CFR

Malfunction I 3

75 Point Teh...

Pier *-Group I Name i Safely Function: Kt KZ K3 A I A2 G KIA Number ~ Question Type KIA Topic RO SRO IATWSII 029EK2 O&Knowledge ofthe interrelations between (EMERGENCY Breakers. relays, and disconnects .1 PLANT EVOLUTION) and the following (CFR 41 7 145 8)

h

. ,

Steam Ge Ability to operate and / o r monitor the following as they KIA Randomly Rejected .4

, Tube Rupture / amlv to EMEUGENCY PLANT EVOLUTION):(CFR: 4 I I3

!

Ueactivity effects of cooldown .4 Steam Line 0 0 0 1040AK1 05 Ruptuie -

1 Excessive Heat Transfer I 4 Loss of Main Feedwater / 4

,

. .

0 054AA1.02' -4 Ability lo operate and / o r monitor the following as they

~-

apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 /

45.6)

' Manual staltup of electric and steam-driven ARM pumps ~

I , ! &

\ = & I b / ~

Instruments and cantrols operable with only dc battery power 3.7 , Station 0 1 0 ,055EA2.04 Ability lo determine and interpret the following as they Blackout / 6 apply to (EMERGENCY PLANT EVOLUTICJN):(CFR: available 41.10 /43.5 /45,13H  !

Loss of Off-site Power 16 0 0 0 056AK1 03 -

Knowledae of theooerational a ~ ~ l ~ c a l i of co:icepls as they appy to me ARNORMhl. PLANT o nthe -

s followinQ Definition of subcwling: use of steam tables to determine it 3.1 , EVOLiTlONl (CFR 41 81041 10)

. . .

Loss Of V l k l 0 ! 0 1 '057AG his is a Generic, no stem statement is associate Ability to explain and apply all system limits and precautions. .8

AC lnst Bus 16 ,,

L(-& 4 i

~(?*&< ,

P I !

.~ -

o o o

~ O ~ ~ A K I . O $ 1 Knowledge of the operational applications of the following Battery charger equipment and instrumentation 28 31 Power 16 concepts as they apply to the (ABNORMAL PLANT

~ EVOLUTION):(CFR: 41.8 toAl.10)

0 1 0 %?AA2 C1 L'kbI 1y 111 oetermine and nterorel tho follow ng as lnoy Location of a leak in the SWS 2.9 j apply to ABNORMAI. PIAN1 EVCl.Lh'Olu, (CFH 41 10 '

75 Point Teb<..-

Tier W r o u p 1 Name I Safety Function: Kf K2 K3 A I A2 0 WANumhgr QueStiQnType WA Topic boss of Ability to operate and I or monitor the following as they Restoration of systems served by instrument air when Instrument Air / 41.7 / pressure is regained

  • ,

LOCAQutside , 1 0 0 Knowledge of the operational applications of the following Annunciators and conditions indicating signals, and remedial Containment / 3 ncepts as they apply to the EMERGENCY PLANT actions associated with the (LOCA Outside Containment).

EVOLUTION):(CFR: 41.8 to 4Z.10)  !\b

,I I 1 ~

,

~

,

LOSS of Emergency

/C4001ant Recirc i :

0 ' 0 ~0

!

i1 !

~

Knowledge of event based EOP mitigation strategie .1 .8

~

ET Steam Line 0 0 0 0 0 ' 0 ,M12EA2.1 , Ability to determine and interpret the following as they WA Randomly Rejected Rupture - ~ apply to (EMERGENCY PLANT EVQLUTION):(CFR:

Excessive Heat 41 . I O / 43.5 / 45.13)

Transfer I 4 ~

i l Inadequate 0 0 0 0 1 0 lWE05EA2. . Ability to detennitie and interpret the following asthey Adherence to appropriate procedures and operation within the Heat Transfer - y a p p l y to (EMERGENCY PLANT E V O L U T m ( C F R : limitations in the facility's license and amendment Lass of ~ 41 . I O I43.5 / 45.13) > /'

Secondary Heat Sink / 4

75 Point Tes.--

Name I Safety Tier ?--Group2 Function: K1 K2 K3 A l A2 G KIA Number Question T w e KIA Tonic RO SRO

' Continuous .9 I

Dropped Control Rod / 1 1 0 0 0 003AK1 01 %, Knowledge of the operational appilcations of the following COnCeptS as they apply to the (ABNORMAL PLANT Reason for turbrne following reador on dropped rod event I EVOLUTION) (CFR 41 8 to 41 IO)

inoperable/Stuc 3 0 0 0 085AK305 1 enowledge af the reasons for the following responses as Power limits on rod misaligflment .2

i k Control Rod / they appiy to (ABNORMAL PLANT EVOLUTiON):(CFR: ~ -?

. .

1 41.5 145.6) C<'v Lw<d%l.:l

.P- j 26 Emergency 0 0 024AK203

/

k:

Knowledge of the interrelations between (ABNORMAL

!

KIA Randomly Rejected , Boration I 1 PLANT EVOLUTION) and the foilowing:(CFR: 41.7 !45.8)

I Pressurizer ~ o 0 0 0 028AKI 01 Knowledge of the operational applications of the following KIA Randomly Rejected 2.8 ~ Level concepts as they apply to the (ABNORMAL PLANT Malfunction I 2 EVOLUTION) (CFR 41 8 to 41 IO)

1 ~ng;y;= i O 0 0 0 032AKZa Knowledge of the interrelations between (MINORMAL PLANT EVOLUTION) and the foiiowing:(CFR: 41.7 / 45.8) ~

Power supplies. including proper switch positions 2.7 ~ i " ,

! 1 I

LOSS of 0 Knowledge of the interrelations between (ABNORMAL KIA Randomly Rejected 0 0 Intsrmediate PLANT EVOLUTION) and the following (CFR 41 7 I 45 8)

1 Fuel Handling 0 0 10 ~036AG2.4.22 This is a Generic, no stem statement is associate KiA Randomly Rejected 3 4 Accident I &  ! :

i Steam 0 0 037AG2.4.31 This is a Generic, no stem Statement is associate KIA Randomly Rejected .4 Generator Tube Leak / 3 1 :

75 POIP~ re.

Name I Safety Tier ?-tSr~t.ip2 Function: K1 K2 K3 A I A2 G KIA Number Question Type KIA Topic RO SRO LOSS of Condenser Vacuum / 4 Acudental

"T" 0 0 0 0 0 0 059AK3 02 I

Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTiON):(CFR:41.10 /

43.5 /45.15)

Knowledge of the reasons for the following responses as Conditions requiring reactor and/or turbine trip WA Randomly Rejected 3.9 41 Llquld they apoiy to (ABNORMAL PMNT EVOLUTlONl (CFR

~ /RQadWasteRe1

!

Accidental 0 0 0 WA Randomly Rejected I Gaseous Radwaste Re1 19 ~

I ARM System Alarms / 7 10 1o ' 0 I

WA Randomly Rejected 34 36 Plant Fire On- 0 0 0 1 Bypass of a heat detector .7 I site / 9 8 Control Ueom 0 0 0 KIA Randomly Rejected 29 33 Evac / 8 I Loss ofCTMT Integrity / 5 0 0 0 0 1 0 069A41'01 I

'

' Ability to operate and I or monitor the following as they aPPIv to (ABNORMAL PLANT EVOLUTI0N):ICFR: 41.7 /

KJA Randomly Rejected Inad. Core 0 0 0 0 0 0 074FA1 OG Aoilly 10 Operate ard Ior monilo: rhe fo low8ngas they &A Ranaonily Re.ec1eo Cooling / 4 app:y tu .EMERGENCY PLANT EVOLUTi3N! (CFH 41 7

High Reactor a 1 0 0 0 0 076AK20 nowledee of the interrelations between (ABNORMAL Process radiation monitors 26 Coolant Activity PLANT &OLUTIOM) and the foilowlng (CFR 41 7 I 4 5 8)

/9

""?UP 2 I A2 G KIA Number Question Type KIA Topic Rediagnosis/3 0 0 0 0 0 1 WEOlEG2 This is a Generic, no stem statement is associated Knowledge of loss of cooling water procedures I Steam Generator

~ 0 0 0 0 0 0 'WE13EG2.1, This is a Generic. no stem Statement is associated,

~ KIA Randomly Rejected I ! !

I , ,

Components and funciiens of control and safety systems, 0 , 1 , 0 0 1WEi5A to operate and I or monitor the following as they ply to (EMEUGENCY PLANT EVOLUTiON):(CFR:4 including instrumentation signals, interlocks, failure modes i 145.6) and automatic and manual features

0 0 0 WE16EA Ability to operate and /or monitor the following as they KIA Randomly Rejected 29 High Containment 0 0 0 '

i l I apply to (EMERGENCY PLANT EVOLUTION):(CFR:4 Radiation / 9 I / 45.6)

. .

l SI Termination 0 0 Normal. abnormal and emergency operating procedures 33 associated with (SI Termination)

I 13 i EVOLUTION):(CFR:41.5 / 4 5 . 6 ) t LOCA 0 0 0 0 0 0 WE03EA2 I Ability to determine and interpret the following as they KIA Randomly Rejected 34 Cooidown - apply to (EMERGENCY' PLANT EVOLUTION):(CFR:

Depress I 4 41.10 / 43.5 145.13)

I I I Natural Circ I 4 0 0 0 0 0 0 WE09EA21 Aoility 10 aeterm ne and ntarpiet !ne follow.ny as ttiey KIA Randomly Rejected 31 apply 10 (MtHGENCY PLANT EVOLUT:ON, oCFR 41 : O I 43 5, 45 13)

NaturalCirc 0 0 0 This s d Geiiei c no olein st3lement IS assooa.:cJ KIA Randomly Rejected 34 3.8 1 With Seam Void/ 4 RCS 0 0 0 0 WE08EK2 2 Knowledge 01 lne inle.rela1ions Deheen iEMERGEhCY KIA Randomly Rejected 36 Overcooling PLAhl' EVOLUTION, and li~clo ow.ng (CFH 41 I 45 8, ~

PTS / 4

75 Point T& -.

Name I Safety Tier Tdroup 2 Function: K I K2 K3 A l A2 G KIANumber QuestionType KIA Topic RO SRO 41.10 143.5 /45.13)

Saturated Core Cooling Core 0 " "0' I 0 ' 0 0 0 ,WE07EG2.2. This is a Generic, no stern statement is associate i KIA Randomly Rejected

25 134

Cooling I 4 i

LossofCTMT lntegrdy / 5 0 0 0

, I

1 I

. 1 0 :wE14A I

, Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR:

1, I

KIA Randomly Rejected ,34 38 41 1 0 / 4 3 5 / 4 5 1 3 )

75 Point \,--

Name / Safety ,.-I-Tier z Group 1 Function: K1 KZ K3 K4 K5 K6 A1 A2 A3 A4 G WANumber QuestionType KIA Topic R5 SR5

!ChGiczand 0

~

~_

.

0 ~0 1-1 ; ~ / L! ~4~~~~

~ ~ ~~ __.__~~ ~

\\&ti-

~ ~ ~ ~ ~

Knowledge of the effect that a loss or malfunction of the I I id

' Volume Cmtrol following will have on the (SYSTEM):(CFR: 41.7 / 45.7)

Emergency 0 '0 0 10 ' 11 1 0 0 U 0 0 0DtiKfi.tB mafun:tiunof Ilie Core faoiing

~~~

~

_ ,1 :

, .. _.___ ~ ~ ~ ~_

Pressurizer 0 0 0 0 007A1.01 ity to predict and/or m6nitor changes in parameters Maintaining quench t a m water level 3.1 ~

Relief/Cltlench ociated with operating the (SYSTEM) controls within limits i Tank I

I including:(CFR: R 41.5 I45.5)

I 008K3.03 4 howiedge ofthe effect that a loss or malfunctionof the RCP I (SYSTEM) will have on the following:(CFf?: 41.7 I45.4)

r Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: f l . 2 lo 41.9 I45.7 to 45.8)

1 Reactor Ability10 predict andlor monitorchangesin parameters Trip setpoint adjustment j Protection associated with operating the (SYSTEM) mntrols 1 including:(CFR: 41.5 / 45.5) F, R--___-~ ~

ledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:(CFR: 41.7 / 45.4)

Features i ~~~.~~ . ~~

~____

75 Point 't Name / Safety Tier ~ G r o u pI Function:

-

K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G

- KIA NumhRr Question T..v ~ e

\ I KIA ToDic RO SUO

- Containment 0 0 lo (a) predict the impacts of the fo!lowing on the Fan motor thermal overiaadlhigh-speed Cooling STEM) and (b) based on those predictions. use >peration ures to correct, control. or mitigate th%

consequences of those abnormal operatlon:(CFR: 41.5 /

.- - - 45.6) -~ __

II

~

Ice Condenser 0 0 025K5 02 Knowledge of th@operational implications oFthe following Up. Rejected copCeptS as they apply to the (SYSTEM):(CFR: 41.5 I j .. -~ _ _ ~ -

Containment 0 0 D26A4.05 & & u a i y operate and/or monitor in the control 3mtsinment spray reset switches ! Spray ~ room:(CFR: 41.7 I45.5 to 45.8)

i""' w*+#&sm

... ...

..

.. .

......~~

.......................

0 'I 0 0

-.

~~

Knowiedge of (SYSTEM) design feature@)and of

~

interlock(s) which pmvide for the foHowing:(CFR: 41.7)

___- I -

0 0 0 0 9bllily to locate and operate components. ncluding local controls

~~ -

Main Feedwater 0 059Y1 02 I hiowledge of (he physica ccnnectms andlor c a s e -

affect relatioiishios between (SYSTEM) and the ~~ ~

-~

hdtty to mw:w ddomiltic operations of the (SYSTEM) Auxiii2rylEmerg 5' ency Feedwater (CF9 41 7 145 I )

i .

AC Electrical Distribution

- .

DIG

- __ .4

~- ___ _- .1

! o QC Eiectrical 063~d.03 ,Ability to manudly operate and/or rlionitor in the wntrui 3attery discharge rate Distribution mom:(CFH: 41 7 / 45.5 to 4 5 4 r\

I 1-f\.!;. .>

' ,

Y--

_...---

. .-

,

75 Point Te-..

Tier 2-Group 1

Name I Safety .-P Funetion:

I K1 K2 K3 K K5 K6 A I A2 A3 G WA Number Questian Type WATopic

-

RO SRO

-

3.3

~ Emergency o o Ability to manually operate andior monitor in the MntrOl Establishing power from the ring bus (to Diesel rmrn:(CFR 41.7 145.5 to45.8) relieve EBiG)

, Generator

~~

edge of the operationai i ons of the foilowing Radiation theory. including sources, %

M):(CFB: 41.5 / types. units and effects

, no stem statement is associate Ability to locate and operate components. .4 l including bcal control ~-- -

)78K2.02 power supplies to the Emergency air compressor .5 0 0

- .3 0 1 10362.4.4 fPQs is a Generic, no stem statement is associate Ability to recognize abnormal indications lo A / f w system operating parameters which are entry-level conditions for emergency and abnormal operating p:osedure ~ ~~~~

~ ~. ~- __ ~~~~

1 7 M r & n o w l e d g e of (SYSTEM) design feature(s) and or Automatic start features associated with .2 Service Water 0 0 0 , l 0 0 0 interlock(s) which prov.$e for the fallo-R: 41.7) SWS pump mntrois

~

I instrument AI^

-

o

..I-I io 0

~~~ ~ ~~~~~~

__ of the effect that a loss or malfunction of the (SYSTEM) will have on the Containment air system ~. .___ ___ .2 0 Io 0 o (a) predict the impacts of the following on the M) and (b) based on those predictions, use ures to correct. wntro e equenses of those abno (CFR: 41.5 I

~ ~~

__ .~~~~ .9 nowledge of eleclrical power supplies to the following:(CFR 41.7) /----

--

75 Paint T- .

Name I Safety Tierk Group 1 Function:

Emergency

--

KI K2 K5 K4 K5 K6 A I A2 A3 A4 G KIA Number Question Type KIA Topic Operating voltages. currents and RO BRO i Generator sociated wlth operating the (SYSTEM) contro!s cludmg:(CFR 41.5 / 45.5)

temueratures

~~~~~~~~~~~~ ~~ __ ~

0 0 the operational implications of the following Pump head eff@ctswhen contrul valve IS ency Feedwater ncepts as they apply to the (SYSTEM):(CFR 41.5 /

75 POI!

-.

Name ISafety Tier Group 2 Function: K1 K2 K3 K4 K5 K6 A 7 X 2 A3 A4 G KIA Number QuesttDoPt Type KIA Topie RO SRQ 1 Hydrogen TTq7 1 hbiiity to predict a n d h monitor changes in paramaters 028A1.02 KIA Randomly Rejected i j t

Recombiner and Purge Control 1 associated with operating the (SYSTEM) controls including:(CFR: 41.5/45.5) 3.4 ~ ~ ~ -- - ~ - - - __ -

Containment 0 0 0 029hZ.03 Ability to (a) predict the impacts of the foilovdng on the KIA Randomly Rejected 2.7 Purge (SYSTEM) and (b) based on these predictions. use procadures to correct, control, or mingate the Spent Fuel Pool Cooling

- - __

4lo

_ -

~ ~ .-

-.

~ ~

~

~.

consequences of th3se abnormal operation:(CFR 41.5/

~

~

~ _ _-~ - -

__

no stem Sfatement is associate ~~ -

__

KIA Randomly Rejected

~

- -

~

-

Fuel Handling 0 0 0 034K6.02 wledge of the effect that a io% or malfunction Radiation monitoring systems 1 Equipment owing will h,awon the (SYSTEM):(CFR: 41.7/45.7)

f-i i\ I L&,CL--.--

I 1 Steam

, Generator i 0 0 0

-. -~

wiedge of the physical connections andlur cause-ct relationships between (SYSTEM) and the h S F ll I

followingJCFR41.2 to41.9/45.71045.8) i 1I-.- /A- __ I

, Steam 1 Dump/Turbrne 0 0 0 341K1.02 1

~ L-~~- -

Knowledge of the ~5,vsicalwnnections andIa cause-eftzct rcliionshipi between (SYSTEM) and the i ihxid&y&iected I .

Bypass Control folfowing.(CF'R41.2 tu 41.9 145.7 tu 45.8)

I

,

-

Main Turbine Generator

~

4 1

~~~ ~~~ -~

I

Turbine Slop/govemo: valve closure on turbinetrip l -

Condenser Air -t 0 0 0 , 055K1.06 wledge of the physical connections andlor cause-ct relatiofwhips between (SYSTEM) and the PRM system i

Remavat owing:(CFR 61.2to41.9/45.7to45.8)

i'l-,/

& A c i_.~ ~~~ ~~~~ - - - -

Liquid 0 lo O I 0 edge of the physical wnnections and/or cause- KIA Randomly Rejected 1 Radwaste effect relationships between (SYSTEM) and the following:(CFR: 41.2 to 41.9I45.7to 45.8)

75 Point .-

Tier 2 Group 2 I

Name I Safety -,-.-

Function: K1 K2 K3 K4 K5 K6 A I A2 A3 A4 G KIA Number Question Type KIA Topie 190 SRO 071K6 K r f o w l a e of the effect that a loss or malfunction of the KIA Randomly Rejected 0 3 following wiil have on the (SYSTEM):(CFR: 41.7 / 45.7)

+ .- .~ __ -

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

0 07262.1.16 This is a Generi no stem statement is associete Knowledge of system status criteria Y whioh require the notiflcation of plant u' monne I

.~~-~

-

Circulating Water Statim Air

I, -

I 0 0 1' 075K1.02

-

079K2

-

b W l @ d Q of e the physical connections and/or cause-effect relationships betwean (SYSTEM) and the fdlowing:(CFR 41.2 to41.9 /45.7 to 45.8)

Knwrledge of e:edncat powet nupp!ies lo tho foliov!'r:g:(CFR: 41.7)

__

WA Randomly Rejected WA Randomly Rejected

__

__

___

~~~~

-

1t9

--p i

~- !i +T

~ ~

Fire Protection 0 0 0 086K5.03 nowledye 01 the operatioiiai imp:ications o! the fdlowinp Effect of water spray on electrical i c ~ p t sas Ibey apply lo the (SYSTEM):(CFR: 41.5 1 components L/ 45.3)

-

~

Control Rod Drive 0 0 O

0 0I 001K2.01

.,.., -.--.

- . ... . . ..

Know:edge of eiectfica: power supplies 10 Ihe 1ol:owing:iCFR: 41.7)

KIA Randomly Rejected jjs ~ . ~ .~~ ~ ~ _ _ ~ -~ . _- --

002K3.02 Knowledge of the effect that a loss or malfunction d the WA Randomly Rejected .5 Ueactor Coo!ant 0 0 0 0 (SYSTEM) will have on the following:(CFR: 41.7 / 45.4)

i

~_ -~ _- -

Ability to monitor automatic operations of the (SYSTEM) Charging and letdown .3 Pressurizer Level Control 0HA3.03j 'nduding:(CFR: 41.7 / 45.7)

h

__ - ~-

0 01 0 1 4 K 3 . 0 2 ~ knowledge of the effac: lhal a loss ar maifunctior, of the Plant computer .8 Rod Position 0 0 Indication (SVSIEM) will have on the fo lovnng (CFR 41 I I 4 5 4)

I

75 Point --

Name I Safety Tier L Group 2 Function:

I Nuclear

-

K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G W A Number Question TVDR .. KIA Topic

-

RO SRO 0 KIA Randomly Rejected

. ~ ~. ~~

~ ~

__

0 Ability to predict andlor monitor changes in parameters KIA Randomly Rejected 0 associated with operating the (SYSTEM) cOntrols including:(CFR: 41.5/45.5)

~ - ~

In-core 0 1 I 01782.2.22 H h i s is a Generic, no stem statement is associated Kmwledge of limiting conditions for Temperature operations and safety limit Monitor

-

Containment a 0 027A4.02 'lity to manually operate andlor monitor in the control Remote oDeratiin and handiinu of iodine Iodine Removal m:(CFB: 41.7 I45.5 to 45.8)

75 Point Test Tier 3 Category KA Number KIA Toplc RO SRO

.. __ ~~~

- - .-

Conduct of ility to make accurate. clear and concise verbal reports.

Operations

+ - -

~- ~

- 1 Conduct of ity to direct personnel activities inside the control room.

Qperatiins (g

.-

wledge of new and spent fuel movement procedure ons and safety limit ~

G o t IimGconditions for operations and safety limit ~

nowledge GEOP entry conditions and immediate adion steps.