IR 05000338/2008301

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Exam 05000338/2008301 - Final Outlines
ML082390032
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 08/22/2008
From:
NRC/RGN-II
To:
References
50-338/08-301, 50-339/08-301
Download: ML082390032 (13)
v • d • e


Text

Final Submittal (Blue Paper)

FINAL OUTLINES NORTH ANNA JUNE 2008 EXAM 05000338/2008301 & 05000339/2008301

PWR Examination Outline Form ES-401*2 FacilItY: NoR-r~ ANNA Date of Exam: ::rV.~E ,;(008 ROKJA PoInts SR D-OnIy Points TIer Group K K K K K K A A A A G A2 G* Total J 3 'I 2 3 4 5 6 1 3 3 2 3

  • 3 * Total 18 3 3 6 Emergency &

Abnormal 2 0 ;J ;; NlA :2 NlA I 9 :2 ~ 4 Plant ,...

Evolutions TlerTotills ~ S ~ 27 5 ~ 10 .. I 3 I I '-f 3 28 '). 3 5 Plant 2 ;). 0 I J 0 I 0 I I I I 10 'J I 3 Systeml 11erTotala 5 ~ ~ f.J ;. ;2 :3 ~ ~ 5 l/ 38 4 L{ 8 3. Generic Knowledge end AbIIltiea 1 2 3 4 10 1 2 3 4 7 Categorlea 3 .3 ~ ~ :;2 \ ~

Note: EnM'e thet at leut two Iopk:e from every epplIc:abIe I<IA catllgory ... umpIlId within eadltler of the RO CJ and SRQ.only outIInn (I.*.* UCIlIPt for on. ClIt8gofy In T1er 3 of the SRO<<1Iy outline. the "TIer T~o In eIICh KIA category lIhaII not be Ie.. th8n two). The point tcUI for elld1 group lind tler In the propoeed ouIIIne must matdllhat .pedfIed In the tabl The lInaI RO exam mwt IotaI 75 poIntI and the SRo-onty .um The tInaI point tDtIII for each ;roup and tier "I8'f devIDl by:t1 from Ih8t apecltled In the IabIe baled on NRC reYItIon muIt total 25 point . S~ wtlt*l eec:h group ... 1dentIlIed an hi auodllted oulIlne; ayatema 0I4Mllullona that do not eppIy et the fadlily IhouId be deleted and juatIfted; opel"8tlonelly 1mponwIt. aItHpecltIc .temal8YOlutloM that ere not Included on the outline ahouId be IIddlld. RefItr to Sedian D.1.b of E5-401 for guidance regarding the e1lm1ndan of Inappfopl1ate I<IA ateternenl ... Select topIca from .. many ~ and evcIUliona .. poAIbfe; umpIe every aystem Of evoMIon In the group befont eeledlng * eeIXJf1d topic for eny ~ 01 evoluIIo . AbIent a planHpedftc prtorIty. only Ihoee KIM hlr.1ng ." Irnpol1ance rating (IR) of 2.5 or higher IhalI be selecte uae the RO end SRO rdnge fOlthe RO and SR()..onIy por1lona. rwepedIwI . 5eIecI SAO tIopIc:a for TIers 1 and 2 from It1e aheded aystema and KIA c:.tegorIe ." The generic (0) I<lAa In n.. 1 and 2 INIl be IeIec:ted fram Sadlon 2 of the KIA catalog. but tha toplc:a mull be reIIrvant to the ,-cabIe evolution 01 syAtm. Reier to Sadlon D.1.b of E5-401 for the applk:able KI,... On the fcIIowlng JWVU, enter the KIA numbers. a brlef cle~ of Hch topic, the 1opIca' Imponance ratlnga (IRa)

far the applk:able Ilcenee 1lMII. and the point toWIa (.) tor Hch ayatem end calegOfy. Enter the group and tier tofU for uch categcwy In the Iab6e abov8: If fUel handling equipment II sampled In other than Category A2 or GO on the SR~ eum. enter It on the left aide of Cotumn A2 for TIer 2, Group 2 (Nate '1 doea not apply). U.. duplicate pagel for RO end SR().onIy UMl . FOI TIer 3. aeIect toplce from SectIon 2 of the I<IA cateIog, and enter the ~A nUmbera. detc:I1ptions. IR and DOint totaIa ttl on Fonn ES~1-3. UmlI SRO letedlons to KlAa lh8t are "nked to 10 CFR 55.4 ES-401, Page 21 of 33

ES401 2 ES-401 PWR ExIImlnaIIon 0IItIIne Fonn~1*2 and .Abnomlal PI8nt EvolutIon** TIer 1JGnluD 1 IRQ I SRO\

'. .. r; I:JAPE , I Name I SafetV Funcdon K K K A A 0 1 2 3 1 2 KIA Toplc(.) IR

- 0oo7 (BWIE02&E!O: CElE02) Reador I

Trio * Stabilization * I1 R 5 SOOSAG..l. 4.8( q~.5) ~ II.S'

- ']. 000008 PrwIaurtzar VIIP<< Space AccIdent I 3 R

RDOB "H~ J. :2'{ IU*y R... 5 J 000009 9mIIIl Break LOCA I 3 RI"9~1("1 2.4. '-I

... oo11 l.Moe Btw8k LOCA I 3 ~O\, [.~:J.02 ~."

Il oo15117 Rep MaIfUnctIonal ~ (1..D/.,11'1 11K 1.01 IU."

~

(, 000022 loA of Rx Coolant Makeuo / 2 P-. O;l.~ A '11-1. ~3.\

- 7 000025 loA of RHR SVIlWIl/4 ll. S ~ c,~jlA '."3 O;Jr-Atl ,.\:,

(.'iJ:S") ~:J*8 n.(g Po S S C'JIIAr;,~. I. ') ('11.5) S'I.?

- I 000028 loA of CClnlpoMnt COOlIng Watat/8 p-. o;lll AA J. 01 ~ q 000027 Preuurtzer P,..". Ccntrof

~ r.. 0,1'1 A(,,2.;2. 'i fP~

SYIltem MeIfunc:Uon / 3

['r {l.. O;lq El<..I.OS' Il ATWS /1 (j) oo38 Steam Gen. Tube RUDCUnt I 3

.$ ~ 03?,.£ A 1.. \'5 ( '4'3.1) S if.'i

.)

t

'"

0()()()4Q oo54 (BWIE06; CEJE05; W1E12)

Stum line Rupture * Ex1:leNtve HMt T,.."sfer I '"

(CEIE06) Lou of M8In Feedwater / iii oo55 Stallon Blackout /8 IR 1t R

i R

'WI! I ~ t: Ie.. '). \

R 05"1 A"" 3.0\

c;'S so £ /41.()1; 0*'1 It 4'*1 p. ...\

- I{

oo56 Lou of Off. . . Power Ie R S t o5"'A"~.

O~ M,:1.;1.'I# [Li3. 1.) ~ * " "'~ol I", oo57 LollI of VItal AC !nit. Bul/8

!f- R os'1 ACr ,. 4.1.fS" R- I~

I'? oo58 Lou of DC Powwr / 8 t<.OS'8AI:.I.OI *12*6

- ,Sf 000062 Lou of Nuclear Sve Weter /4 5 SOt;.;l A A ;l.ot; bns) ~.~

t~t 000065 Lou of InI1rUment ~ I 8 ~ R 0(,511'1'.3.03 AC.'

  • WIE04 LOCA OutsIde Contatnment f 3

. WlE11 LON of Emergency Coolant Redn:./4 If, R 'WIt 05' (';..3. 't fl.). '1

'1 BWIE04; wlEoe Inadequate .....

TI8Mfer * LoaI of HeatSHIf'"

oooon Generatar Voltage end EIectr1c I~ D'i'7 AA 1.01 ~3*(g 1"~ Grid Disturbances 16 KIA ca~ Totals: .. 3 III j 3 .) GIrlt.lb Point TobII: 1816 s .3 3 ES-401, Page 22 of 33

( ES-401 3 Form ES"1-2 ES-401 PWR ea... .ac.. 0utIne Fonn es..401~

8nd Abnclrm8l Pl8nt EvalUIIanI- 11er 1/Grnun 2 IRQ J SRO)

EJAPE * J NMIe I Safely Function K 1'< k A ~ b 1 2 3 1 2 KIA Toplc(.) IR

0oo1 CanIInucKa Rod WIIhcnwaI/1 000003 DronIliId COnIrClI Rod 11 000005 Control Rod 11 S S oo<:AAJ.Od.{.,J.S) 5 BcntIon/1 000028 P.-aurIZet L.nW MaIfwlcIlan I 2 000032 loA or Source R.naa HI , 7 ~ ~~;:t.A1l3.0\ ~.;.0 Loa of Inlermed.... RMae NI J 7 oo38 CBW/AOB) FuIII Accident/a R R O?!J) AA \. 01 ~13 000037 Sturn GeMndor TublIleak 13 000061 Loll of CondenIer VeaAIm , 4 5 SOSlAG-J. J.4'f(~3.51 os q,l-/

000059 AccIdentIIIIJauid R8dW.te ReI. 19

. 000060 AcciderUI ~~ ReI. I 9 IR RC~OAA.1.DS P. ).'1

. 000081 ARM SWIam AIMna 17 ~ Ill. R/XII AGo.2. '"I. ~ SQ('IAA~.o'l{4j3 so)

p 1,1

... joJ" 000087 PIInt FIre 0rHb I a ooooea fBW/A08) Control Room ev.c. I 8 oc:IOO89 fWlE141loA 01 CTMT Int8arttv J 5 000074 fWIE06&E07) lned. Cote CoaIna , .

/

000078 HkItl Reectar CooIft At:tMtv I 9 ~ R 0'761 All. J,o I {\.? ..

I WlE01 &E02 &61 T-.nlnatlan 13 WlE13 a-n GeoemDr Over 14 S" sow/Ell A (,,;/. '/. ~() {n.~ ~ ...3

, , I WlE15 ConIUvnent 15 ~ 1\ Wli IS "'~~. , Rz."

Ii WlE18 HIah Contalnme'll Redl8tIon 19 R 'Hli II. ,.1\. 3. \ p.J-~

BW/M1 Pt.m Runbedt 11 BW/N12ANJ3loA or NNI*X/Y , 7 BW/AD4 Twblne Trio 14 t' BW/MS DIeMI Actudon 18

"

BW/M7 Fkladlna 18 aWIE031 ItMraIn/.

C{

l BW/EOI' WIE03 tOCA CooIdown * 0..-.. 14 "'11:03 A I.]. R BWIE09: CEJA13' WlE09&E10 Nat\nl Clrc./. Il Po. ~Ir: 0'\ fA R3./

BWJE13&E14 EOP RuIeI and EnctolIUnII CEJA11' WIEOS RCS Ovwadna * PTS 14

.: CElA18 e... RCS tMbae 12 CEIEOV Functlon8l KIA Point ToIaI: I< 0 :2- 2. 2- '2. I GmuD PoInt Tot8I: 914 s 2 ES-401, Page 23 of 33

ES-401 . Fonn ES-401*2 \

I E5-401 I ~

, ~ S PWR Ex8mInIdkln OutlIne Plent Stsl8ms*Tier 2IGtoUD 1 IRQ J SROl 10 7 ) .. "G Form E5-401*2 Sya18m./N.-ne K K K K K K A It A A KIA TopIc(l) IR #

1 2 3 4 5 8 1 2 3 4

, fZ ~ o03A~. 0'1 R.2** ~

003 Reactor CooI8nt PumD R ~ oO"\G1,l. ~U

%. 004 ChemIcal 80d VoIwne Control

- J f( S> I~ 005G,t*.1.,,\P('1).l.('1J.5) 5 ".7 005 ReIIdu8I Hut Remov8I 00< \l. \. o

'f..). S 1,'} 12.)., 008 , 007 Pre8aurtzer RellefJQuench R S S 00'7G-J.,:1.39 (,,\3.1) sIU.~ 'f.~ Tank Roo"! ~ '3,01 ~ 00'1 A '/./0 11\:1,,- ~ ROoel'.'-l.OI IHI (, 008 Comoonent CoolIna Water

> R ROlot<-5".O\ ~3.s" 010 Pre8lurtzer PrnIunt Control IR- I~ OIj.F\Z.o'l("'I].S') ~ ~ 012 Reec
tor Protection S . ()1.J~(p*lJa ~.~

~. 013 Engineered s.tety FMtu,... R R R a I 3 ¥. 'i. 15 ll. 2./# Ac:tuation R c>l3 AI.O'] 6l. 3.11 - II, 022 Containment Coollna 1\ ~ I~~~~ ~;~~ "'ll' ;1. ~ ]: 025 Ice Ccndenser

~ I~ 02<. 1<.'.01 ~ 3.~ ~ 028 ConbIInment S - ~ oJ" A'I*ol l\ '1,S' R 12, 03') fS,2. I. 3; l\ '1 039 MaIn Ifld R.hut Steam R S .s O~GJ.I. ~ ~<. '11.;) s '\.'\ ,~ 059 MaIn FeecIW8ler .~ 05'q ..... ,. R9.'f .,; R ~ O~I ~j.O' f?3,. AwdIlaryJEmergency FeedWllhII' I.., 062 AC Electrtcal OlatrtbuUon R ~ ~ 0<1,1 Grot. I. 1 '" 01o;Z l'. ~. " :3 U.'l Cl.l.'1 ,., 063 DC EIectrtcaI Distribution R Po. 0(,3 Kli. 01 fl. IT' 064 EmelftltfteV DIeIef Generatcr rz R Oll'i 1<' 3.0.;2 t~. R 9- ~ o'1~ ¥..5.0,1 ~ \ 073 Procell RadI8tla'l MonItDllna R ~'13 A \.01 fl.1* !, 078 S8rvIca WatM IR R O'AJ A-I. o~ k2l.lI '!.! 078 Instrument Air F- << .~o~SI:.'4*03 C\O'lA A of 01 ll- fl.]. , ContaInment R t03A.3*01 It '),~ I KiA Cateaorv Point Totala: ~ 3 ~ ?;, ~ . . I II 3 GrouD Paint Tot8I: 2815 s 2 .3 ES-401, Page 24 of 33 ~~S":-40:';;'1.:- --::5:'- "':F~on :':':':' : E=S-40: : :='1':': .2 ES-401 PWR ExlInIIndcn OUtlIne Form ES-401*2 Pt.nlSIIRIfN - T1er ~2lRO J SRO\ System til Nine

  • t

,. of , " 7 >" K K K K K K A A A A G .. . I, KIA TopIc(a) IR tI 1 2 3 <4 5 8 1 2 3 '. , 001 Control Rod DrIve "R R 0'1 ~,lf.?1 1t'l, l 002 Re8dor CoolInt } 011 PYMaurizef Level Control

  • r 014 Rod PosItIan IndIc8tlon S' 015 NucIar InatrumentlIIiOn (, 016 NonoftIClNr Il'lItrUmentItion R ~ OllD \4 I. t 1.'{

S 501'1 AJ.ll.l.lof1t.') IS ' r 7 017 In-c:ont T Ma1Itar It 01' AIt.o:J R: . i' 027 Containment iodine RemcwaI ~ 5 O'?~;'J.25'(q,!,.J) S'l* IR R ~ew:.1.0l U,3 ., 028 Hydrogen RecambIner and PUrae ContraI R R o.2'1j!..~."3 ~"1 ..:l '0 029 Cont8Inment PunIe _I.~- 033 SIlent Fuel PoaI CoaIIna R " 03>~li*05 Il ' ~ S .::';'1 J\2.~3 {'i1 f J

,\0 034 Fuel

) .~ 035 St.rn Genemot ,., 041 Steam DumpITurbine ~ ~ O'-lt }(.(g. 0:3 11\1,'1 a_Control I,," 045 Main Turbine GenenIIor Ross A3. 0,3 f .~~ 05S CondenHr Air RernovaJ R I~ 058 CondenAte r< 068 Uauid Radwute Iq 071 W.... Ga DlIIDOUI e- IRO'!l A;(.O~ ~'3 to 072 MIa RadllItion t* 075 W8ter ?! 079 StatJon AIr ~. IRCllq 'It \*01 t'J*o I} 088 Fire Protection KIA cat.-v PoInt T~; f< ~ D\ .;l 0 \ 0 \ \ I I Gnlua Point Tote!: 1013 5 ES-401, Page 25 of 33 Generic Knowledge and Abilities Outline rn.._8';...3...) Fo_rm__.... ES ...-401- FacilItY: DatedExam: I Category KJA## Topic FH) ....,............. I IR ## IR ## R &2.1. 20 Y. . R G 2.I.LH I Condud R c,. J. '.37 of Operations S G-;1. r. 4 ('i 3, .1) . S> (;.). I. ~ (Lj3.5) 4,8, I Subtotal i~..,'-:.- <- CT;2. . .5 ~ G~.J.I"J .7.<1 I Equipment ~ (;,; , ~'i 3q Control f:?~. ). 3S (/.f3.J.) If*S- ~ Go.1.;r.1\ (LJ1.~) " .j} Subtotal

-.V R &~,3. ;,; . . R (,~,.3.l '5" .7~ I Radiation S (.).3. <., ('1),'1) 1.6> Control . . I Subtotal R &2,~. 3 ,(, R <; 2,'1* q 3*8 I Emergency S &- 2, '1*:27 t....n. s) 3.~ Procedures I ~ G). 4.1, ~ (Y1,S) ~I, rr Plan . I Subtotal I Tier 3 Point Tetal 10 7 ES-401, Page 26 of 33 ESw401 Record of ReJl::ect=ed::..:.::KI:.:;AI=- ...;.F..::o~nn~E;;;;S;...-40;.;;..;.1-i_ rterl Randomly Reason for Rejection Group selected KIA T1../<r1 011 EK \.0\ ¥.IA "'f'U

tc..~~'" <!
-BL<<~)

H ..\<c,ht1 dQtS "'* +it- l..\Ji~ £~ \.0 I(.'A il.: 0\ I Koi. O~. ~ Y-U\t:.... ~~"","" ~t..?,t.s, 1 1/(,/. OCIS n'i..J.oi ~f -' ..... \ ... ~ ~IA;,: OtiS A lI.. 3. . -r1./r, tJ.. "-I ~ ; VI ,""': ~ v;"" n. )*l. S * 0'1(, AV- '.08 t-\~ '#o~\fcwA ...,. ;c. ~ (\'1I.. A",j.o No "If. ~ :... ~ se.~"'..-'\ ... ~~ ~ >, z.. r~ /(';,1 ():lJ "fl. au . N_ * s~~ "'If\. ,,: 022¥'I.ot ~ It ,fts' ~;$ ~ ... a4.. ~, l.$'. 12/& i 0(, &\ ¥.S. O;l ~ ""~is~ O~'iy.,>.O~. ,.., "'A .'" ~ Sc,~ ..... ~ ...... r1t ~ l.~. TJI'i 0'18 A 1.0 It- 1'1"". ~~_..., ..u.c... kA ~I(\. i.: 0'18 \<,. '1.03 N. ",,,: ..... ~~ ..--...."........~ S1L ~ t. T,,1J(, L O'l8A,.o\ ~~ r" .. ,\0, .L..llJ~ ;&1 0'811'1.0' Nt "1\- , ..... ~\~ HcH_ ...... v.-:2:f, >* T"k).. (117 t'-.). ()\ 101-. r-.A._\., -..~..."<.l ..." .~ ~ 0 I') II 'to o.:l T2/(,. ~ .. t"'- "'A-~ ~:s. Sfc";~ "",-- ~). "33 \(,5. oS' rJ~"""",""....w '~.L~ "-IA- :~1 013\1.'\,05 "'PIer'}.. IJ, f.Ut , ... ~,. tech....... ,10-. '*" 1.$. Or'Jq A 3. 0 ~ IJ~ ttl. L \#" "iA;, '. . 0"1'\ ~ 1.0\ ,.."" II\- ~'" ~ k ,..*..... ~.~ ~**Z*,. 1').!fr'J., ()55' n I. D~ lJ~ ~ ". ,,\.kl "/~~" "5'~ 11I").0"3 ~\,-- .r d LLo ~ ""'-e, t,u ""-f e... - . * Z/(,I Dol G z.:1... ~ J.. ~ '-S. .. (' p~ .,R:.,....: (4..NPCJtt.-..L.'i h-\.c.o",,- 'TeT\.. S i f T ' $GLE;'-Tt:-b "1 \ g , c> ~ NJ:PS OQ't Fo~ p~,... G z.l,4'-/ . '*' . S f'J APS 11t) t39~ 'r ('f 11 V ~,.,." Ji7"1; Tel"-t. ~ l) ,"/H~T Ttl~5 tt/e" , 0\'- 1<. b.oi -rlfi-o ~'l>~("1 ~:rt$J> I~A- biZ- 1<6,0'-' I' '" "ot. fa II o-v...> I "" 'l '>J GL S o..dl6. p ~ +c..\ c. 0-... 5 - \ '\ -OR' T2(<:,1 ,~ (o ..,.,("{ ... c+4~iJ~(()P rliscrt.... jl'<t to"'), sP-O 1,.p.>0& { tt(}t':~~ s 001 (0.2. "2.L.f'-\ Ncl/.,) r-,..rvpOt-o-t..'( 5cH~CTf::-r> IA. (1- obI{ 62.2.. ':$3 ES401. Page 27 of 33 {. 1 * \~

  • ES-401 Facility: North Anna Written Examination Quality Checklist Date of Exam: 6124/08 Form ES-401*6 Exam Level: ROIXl SRO Initial IRI Item Description a b* c' Questions and answers are technicallv accurate and aPDlicable to the facillt . NRC KlAs are referenced for all question Facility learning objectives are referenced as availabl . SRO auestions are appropriate in accordance with section D.2.d of ES-401 The sampling process was random and systematic (If more than 4 RO or 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR OL program office). Question duplication from the license screening/audit exam was controlled as Indicated below (check the item that applies) and appears appropriate:

~e audit exam was systematically and randomly developed; or _ the audit exam was completed before the license exam was started; or _ the examinations were developed independently; or _ the licensee certifies that there Is no duplication; or _ other (explain) , Bank use meets limits (no more than 75 percent Bank Modified New from the bank, at least 10 percent new, and the rest new or modified); enter the actual RO I SRO-only /1., 0 auestlon distribution!s) at righ . Between 50 and 60 percent of the questions on the RO Memory CIA exam are written at the comprehension! analysis level; the SRO exam may exceed 60 percent if the randomly selected KlAs support the higher cognitive levels; enter Ij-O I 1'1 the actual RO / SRO question distributlon(s) at right Referenceslhandouts provided do not give away answers or aid in the elimination of distractor . Question content conforms with specific KIA statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justifie . Question psychometric quality and format meet the guidelines in ES ADoendix ~ I/IJ f'1 . The exam contains the required number of one-point, multiple choioe items; the total is correct and agrees with the value on the cover shee Print~~ame / Signature Date Author '5' (LPt:tl~/~ '!4/0f Facility Reviewer (*) IIl_rL L"L . ..." J 1~".,Jj~ ,J * " A -" I-c. NRC Chief Examiner (#) H'M- A."'JI'fI5-> /dJ..J.£T:~/" .lro r.,mpnC.1h **11 /, tj,'!9fof NRC Regional Supervisor 1'- ." '//1':\. * ol!/J,,r Note: * The facility reviewer's initials/signature are not applicable for NRC-developed examination # Independent NRC reviewer initial items in Column *c"; chief examiner concurrence reauire ., .J' Administrative Topics Outline Form ES-301-1

ES-301 Facility: North Anna Power Station Date of Examination: 6/2008 Examination Level: Combined (See Below) Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (KA) (see Note) Code* M,R Determine the Quadrant Power Tilt Ratio by hand calculation Conduct of Operations (1-PT-23) and determine maximum allowable power level based on the calculatio (ALL) (G2.1.7, RO 4.4/ SRO 4.7) N,R Determine minimum RHR flow based on time after shutdown Conduct of Operations and determine minimum RCS level to support that flowrate (using 1-AP-11, Loss of RHR). (ALL) (G2.1.25, RO 3.9/ SRO 4.2) N,R Evaluate and apply Tech Specs and procedure requirements Equipment Control based on UNSAT condition from QTRLY PORV Block valve surveillance (1-PT-44.7). (1) (ALL) (G2.2.40. RO 3.4/ SRO 4.7) N,R Select appropriate RWP and calculate Stay Time Radiation Control (ALL) (G2.3.7, RO 3.5/ SRO 3.6) ) Emergency Plan M,R Classify event and determine PAR (modified, activity was performed on previous 2 exams) (SRO ONLY) (G2.4.41, RO 2.9/ SRO 4.6) NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are require * Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~3 for ROs; ~ 00 for SROs & RO retakes) (N)ew or (M)odified from bank (~ 1) (P)revious 2 exams (~ 1; randomly selected) (1) - For SRO Candidates there is one additional element that is not included in the RO JP \\ " \ " "" ~ '(1 .. . \" l,\ \. \'j- /\' - ,/../ .... ;,: f. ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: North Anna Date of Examination: 6/2008 Exam Level: RO 181 SRO-IO SRO-U 0 Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title (KA) Safety Type Code" Function Emergency Borate for stuck rods following Reactor Trip (1-ES-0.1) (MOV-1350 will not open) A, M, S, E, L 1 024 - AA2.01, Ability to determine and interpret the following as they apply to the Emergency Boration: Whether boron flow and/or MOVs are malfunctioning, from plant conditions (3.8/4.1) (CFR: 43.5 / 45.13) Respond to misaligned control rod, during realignment rod will drop causing negative rate trip; A,N,S,EN 2 (turbine fails to trip causing SI actuation, SI fails to automatically actuate but can be manually actuated). 013 - A4.03, Ability to manually operate and/or monitor in the control room: ESFAS initiation (4.5/4.7) (CFR: 41.7/45.5 to 45.8) Transfer an emergency bus from an emergency diesel generator to a reserve station service D,S 6 transformer 064-A4.07, Ability to manually operate and/or monitor in the control room: Transfer ED/G (with load) to grid (3.4/3.4) (CFR: 41.7/45.5 to 45.8) Respond to Loss of RHR in Mode 4 (1-AP-11) 4 (Pri) 005 - A2.03, Ability to (a) predict the impacts of the following malfunctions or operations on the A, M, P, L, S RHRS; and (b) based on those predictions, use procedures to correct, contrOl, or mitigate the consequences of those malfunctions or operations: RHR pump/motor Malfunction (2.9/3.1) (CFR: 41.5/43.5/45.3/45.5) Respond to failure of non-controlling 1* Stage pressure transmitter (1-AP-3); after transfer to A,M,S,P 4 (SEC) pressure mode controller setpoint fails low steam dumps must be placed in off (1-AP-38) 041 - A4.04, Ability to manually operate and/or monitor in the control room: Pressure Mode (2.7/2.7) (CFR: 41.7/45.5 to 45.8) Add Nitrogen to PRT D,S,P 5 007 - A1.02, Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including: Maintaining quench tank pressure (2.7/2.9) (CFR: 41.5/45.5) Respond to Recirc Spray Heat Exchanger radiation monitor alarm (1-AP-5) D,C,E 7 073 - A4.01, Ability to manually operate and/or monitor in the control room: Effluent release (3.9/3.9) (CFR: 41.7/45.5 to 45.8) Respond to loss of 1 or more Circ Water Pumps (1-AP-13) N,S 8 075 - A2.02, Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, contrOl, or mitigate the consequences of those malfunctions or operations: Loss of Circulating Water Pumps (2.5/2.7) (CFR: 41.5 1 43.5 1 45/3 145/13) In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) Open the residual heat removal heat exchanger cooling water return valves using a jumper (1- D,E,R 8 AP*28,0-FCA-1). 008-A2.05, Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effect of loss of instrument and control air on the position of the CCW valves that are air operated (3.3/3.5) (CFR: 41.51 43.51 45/3/45/13) Re-energize a 12Q-volt vital bus from its inverter (1-MOP-26.6, Q-AP-10) D,E 6 057 - AA1.01, Ability to operate and lor monitor the following as they apply to the Loss of Vital AC Instrument Bus: Manual Inverter Swapping (3.7/3.7) (CFR 41.7/45.5/45.6) Trip the reactor locally by opening the Reactor Trip Breakers or the rod-drive motor generator A,D,E 1 breakers 029 - EA1.12, Ability to operate and monitor the following as they apply to a ATWS: MIG set power supply and reactor trip breakers (4.114.0) (CFR 41.7/ 45.5 / 45.6) @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room .

  • Type Codes Criteria for RO 1SRO-II SRO-U (A)Jtemate path 4-6 1 4-6 12-3 (C)ontrol room (D)irect from bank ,-91,-81 4 (E)mergency or abnormal in-plant ~ 1/ ~ 1 1 1 (EN)gineered safety feature * / * 1 1 (control room system)

(L)ow-Power / Shutdown 1/ 11 1 (N)ew or (M)odified from bank including 1(A) 21 21 1 (P)revious 2 exams (similar topic) 31 31 2 (randomly selected) (R)CA 11 1 / 1 ISiimulator ), ) ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: North Anna Date of Examination: 6/2008 (~ Exam Level: RO 0 SRO-ll8I SRO-U 0 Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title (KA) Safety Type Code" Function Emergency Borate for stuck rods following Reactor Trip (1-ES-0.1) (MOV-1350 will not open) A,M,S,E,L 1 024 - AA2.01, Ability to determine and interpret the following as they apply to the Emergency Boration: Whether boron flow and/or MOVs are malfunctioning, from plant conditions (3.814.1) (CFR: 43.5/ 45.13) Respond to misaligned control rod, dUring realignment rod will drop causing negative rate trip; A,N,S,EN 2 (turbine fails to trip causing SI actuation, SI fails to automatically actuate but can be manually actuated). 013 - A4.03, Ability to manually operate and/or monitor in the control room: ESFAS initiation (4.5/4.7) (CFR: 41.7 / 45.5 to 45.8) Transfer an emergency bus from an emergency diesel generator to a reserve station service D,S 6 transformer 064-A4.07, Ability to manually operate and/or monitor in the control room: Transfer ED/G (with load) to grid (3.4/3.4) (CFR: 41.7/45.5 to 45.8) Respond to Loss of RHR in Mode 4 (1*AP-11) 4 (Pri) 005 - A2.03, Ability to (a) predict the impacts of the following malfunctions or operations on the A, M, P, L, S RHRS; and (b) based on those predictions, use procedures to correct. control, or mitigate the consequences of those malfunctions or operations: RHR pump/motor Malfunction (2.9/3.1) (CFR: 41.5/43.5/45.3/45.5) 11 Respond to failure of non-controlling 1 Stage pressure transmitter (1-AP-3); after transfer to A,M,S,P 4 (SEC) pressure mode controller setpoint fails low steam dumps must be placed in off (1-AP-38) 041 - A4.04, Ability to manually operate and/or monitor in the control room: Pressure Mode (2.7/2.7) (CFR: 41.7/45.5 to 45.8) Not used for SRO-j candidates N/A N/A Respond to Recirc Spray Heat Exchanger radiation monitor alarm (1-AP-5) D, A4.01, Ability to manually operate and/or monitor in the control room: Effluent release (3.9/3.9) (CFR: 41.7/45.5 to 45.8) Respond to loss of 1 or more Circ Water Pumps (1-AP-13) N,S 8 075 - A2.02, Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of Circulating Water Pumps (2.5/2.7) (CFR: 41.5/43.5/45/3/45/13) In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) Open the residual heat removal heat exchanger cooling water return valves using a jumper (1- D,E,R 8 AP-28,O-FCA-1). 008-A2.05, Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effect of loss of instrument and control air on the position of the CCW valves that are air operated (3.3/3.5) (CFR: 41.5/43.5/45/3/45/13) Re-energize a 120-volt vital bus from its inverter (1-MOP-26.6, 0-AP-10) D,E 6 057 - AA 1.01, Ability to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus: Manual Inverter Swapping (3.7/3.7) (CFR 41.7/45.5/45.6) Trip the reactor locally by opening the Reactor Trip Breakers or the rod-drive motor generator A,D,E 1 breakers 029 - EA1.12, Ability to operate and monitor the following as they apply to a ATWS: M/G set power supply and reactor trip breakers (4.1/4.0) (CFR 41.7/45.5/45.6) @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room .

  • Type Codes Criteria for RO 1 SRO-II SRO-U (A~temate path 4-6 14-6 12-3 (C}ontrol room (D)irect from bank ~9/~81 4 (E)mergency or abnormal in-plant ~ 11 ~ 11 1 (EN)gineered safety feature - 1- 1 1 (control room system)

(L)ow-Power 1 Shutdown 11 11 1 (N)ew or (M)odified from bank including 1(A) 21 21 1 (P)revious 2 exams (similar topic) 31 31 2 (randomly selected) (R)CA 11 11 1 (S)imulator /' ,I ,J ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: North Anna Date of Examination: 6/2008 () Exam Level: RO 0 SRO-IO SRO-U 181 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) Operating Test No.: 1 System / JPM Title (KA) Safety Type Code" Function Not used for SRO-U candidates N/A N/A Respond to misaligned control rod, during realignment rod will drop causing negative rate trip; A,N,S,EN 2 (turbine fails to trip causing SI actuation, SI fails to automatically actuate but can be manually actuated). 013 - A4.03, Ability to manually operate and/or monitor in the control room: ESFAS initiation (4.5/4.7) (CFR: 41.7/45.5 to 45.8) Transfer an emergency bus from an emergency diesel generator to a reserve station service D,S transformer 064-A4.07, Ability to manually operate and/or monitor in the control room: Transfer ED/G (with load) to grid (3.4/3.4) (CFR: 41.7/45.5 to 45.8) Respond to Loss of RHR in Mode 4 (1-AP-11) 4 (Pri) 005 - A2.03, Ability to (a) predict the impacts of the following malfunctions or operations on the A, M, P, L, S RHRS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: RHR pump/motor Malfunction (2.9/3.1) (CFR: 41.5/ 43.5 / 45.3 / 45.5) Not used for SRO-U candidates N/A N/A Not used for SRO-U candidates N/A N/A Not used for SRO-U candidates N/A N/A Not used for SRO-U candidates N/A N/A In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) Open the residual heat removal heat exchanger cooling water return valves using a jumper (1- D,E,R 8 AP-28, 0-FCA-1). 008-A2.05, Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effect of loss of instrument and control air on the position of the CCW valves that are air operated (3.3/3.5) (CFR: 41.5 / 43.5/ 45/3 / 45/13) Not used for SRO-U candidates N/A N/A Trip the reactor locally by opening the Reactor Trip Breakers or the rod-drive motor generator A,D,E 1 breakers 029 - EA1.12, Ability to operate and monitor the following as they apply to a ATWS: M/G set power supply and reactor trip breakers (4.1/4.0) (CFR 41.7 /45.5/45.6) @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overtap those tested in the control roo 'Type Codes Criteria for RO 1SRO-II SRO-U (A)lternate path 4-6 I 4-6 12-3 (C)ontrol room (O)irect from bank ~91~81~4 (E)mergency or abnormal in-plant  !. 1 I!. 1 I!. 1 (EN)gineered safety feature - 1 - I !. 1 (control room system) (L)ow-Power I Shutdown 11 1 I!. 1 (N)ew or (M)odified from bank including l(A) 21 21!.1 (P)revious 2 exams (similar topic) 31 31 ~ 2 (randomly selected) ,- (R)CA iSiimulator 1 1 1 I!. 1 (, \.

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