IR 05000395/2004301

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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 ES-40M Quality Checkllst 5. 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 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:

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)

I Pressurizer Vapor Space Accident I3 000 0 1 0 'OOBA41.01 , Ability to operate and

/ or monitcr the following as they KIA Randomly Rejected ~ apply to (ABNORMAL PLANT EVOLUTION):(CFR:

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

/ 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:

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

/ 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:

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:

K1 K2 K3 Al A2 G KIA Number Question Twe KIA Tonic LOSS of Intsrmediate

' Continuous Dropped Control Rod / 1 inoperable/Stuc i k Control Rod / 1 1 0 Emergency Boration I1 I 1000 3 0 Pressurizer

~ 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:

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)

and the foiiowing:(CFR:

41.7 / 45.8) Power supplie including proper switch positions

~ 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:

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:

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:

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

""?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

/ 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:

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:

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

):(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 ~

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:

K1 KZ K3 K4 K5 K6 A1 A2 A3 A4 G WANumber QuestionType

\ \&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:

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?:

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:

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:

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:

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:

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

! Spray Fan motor thermal overiaadlhigh-speed

>peration Up. Rejected -~ D26A4.05 &&uaiy operate and/or monitor in the control ~ room:(CFR:

41.7 I45.5 to 45.8) ~~ ~ ___- Knowiedge of (SYSTEM) design feature@)

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-- .

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)

and or interlock(s)

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:

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) ~~~~~~~~~~~~

~~ 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

~ __ Pump head eff@cts when contrul valve I S 75 POI! -. Name I Safety Function:

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:

41.5/45.5)

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:

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)

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)

i'l-,/ ~~~ ~~~~ &Ac effect relationships between (SYSTEM) and the following:(CFR:

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:

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:

41.5 1 45.3) ,. - .,. -.--. - . . . . . . .. Know:edge of eiectfica:

power supplies 10 Ihe 1ol:owing:iCFR:

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:

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:

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:

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.